ML16014A137

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Rancho Seco and ISFSI - Report of Changes to the Quality Assurance Program That Do Not Require Prior NRC Approval
ML16014A137
Person / Time
Site: Rancho Seco, 07200011
Issue date: 01/07/2016
From: Ronningen E T
Sacramento Municipal Utility District (SMUD)
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
DPG 16-002
Download: ML16014A137 (79)
v • d • e


Text

Powering forward.

Together.

  • SM UD.. ....r i. ..January 7, 2016DPG 16-002U.S. NRC Regulatory Commission Attn: Document Control DeskWashington, DC 20555Docket 50-312Rancho Seco Nuclear Generating StationLicense DPR-54Docket 72-11Rancho Seco Independent Spent Fuel Storage Installation License SNM-2510REPORT OF CHANGES TO THE RANCHO SECO QUALITY ASSURANCE PROGRAM THAT DO NOT REQUIRE PRIOR NRC APPROVALAttention:

Jack Parrott and Chris AllenIn accordance with 10 CFR 50.54(a)(3) and 10 CFR 50.4(b)(7),

we are required tosubmit a copy of changes to the Rancho Seco Quality Manual (RSQM) that do notreduce commitments in the quality assurance program previously accepted by theNRC. Changes to the quality program that do not reduce commitments in theprogram can be made without prior NRC approval.

During calendar year 2015, we revised the RSQM to reflect changes to thecorporate organization.

Specific portions of the RSQM that were revised include:1.2.3.4.5.Quality Assurance PolicyRSQM Chapter I "Organization" RSQM Chapter II "Quality Assurance Program"RSQM Chapter XVIII "Audits"Appendix A "10 CFR 50 Administrative Controls" The safety evaluation associated with these changes concluded that these changesdid not reduce any commitments and did not require prior NRC approval.

The RSQMcontinues to implement the requirements of 10 CFR Part 50, Appendix B and 10CFR Part 72, Subpart G. The individuals and organizations performing qualityassurance functions continue to have sufficient authority, organizational freedom,and independence from cost and schedule issues./¶Rancho Seco Nuclear Generating Station I14440 Twin Cities Road I Herald, GA 95638-9799 I 916.452.3211 Ismud.org DPG 16-002The document is being provided in its entirety because it does not include a List ofEffective Pages. However, changes are indicated by "revision bars" in the leftmargin to aid in review.If you or members of your staff have any questions requiring additional information or clarification, please contact me at (916) 732-4817.

Sincerely,

.Einar T. Ronningen

Manager, Rancho Seco Assets(RJIDTIBG)

Enclosures

-(1) Rancho Seco Quality Manual, RSLBD-01O Rev.2Cc: NRC, Region IV2 RANCHO SECO LICENSING BASIS DOCUMENTTITLE: RANCHO SECO QUALITY MANUALIEFFECTIVE DATE: 04/20/2015 NUMBER: RSLBD-010 REVISION:

2PAGE 1 OF 77REASON FOR CHANGE:* Reflect current corporate organization and responsibilities REVISION SUMMARY:* Revised QA policy Statement to Reflect current corporate organization andresponsibilities

  • Revised Section 4.0 of the RSQM to reflect new titles within the organization.

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 2 OF 77QUALITY ASSURANCE POLICYThe Sacramento Municipal Utility District's (SMUD) policy regarding quality assurance at theRancho Seco nuclear facility, which includes the Rancho Seco Nuclear Generating Station(RSNGS; licensed and undergoing decommissioning pursuant to 10 CFR 50) and the RanchoSeco Independent Spent Fuel Storage Installation (ISFSI; licensed and operated pursuant to10 CFR 72), is as follows:I. Organizations involved in QA Class 1 activities and the other Program Activity Areasspecified in Rancho Seco Quality Manual (RSQM)Section II, Attachment Il-1, shall bestructured,

managed, and operated to provide compliance with the RSQM. Procedures shall be prepared that implement the activities required to safely operate the RanchoSeco nuclear facility and achieve the following objectives:
a. Comply with government regulations and established SMUD management
policies, applying a systematic, disciplined, and uniform approach to qualityassurance.
b. Provide facilities
designed, modified, constructed, tested and operated inaccordance with specified requirements with reasonable assurance that failuresor malfunctions will not cause undue risk to public health and safety.c. Ensure prompt identification and resolution of actual and potential problems indesign, procurement, construction,
testing, operations, maintenance, andmodification of the structures,
systems, and components associated with QAClass 1 activities or other applicable Program Activity Areas specified in RSQMSection II, Attachment Il-i.Ill. The RSQM and implementing procedures constitute the Rancho Seco QualityAssurance Program (QAP). The QAP applies to activities, plans, and programsaffecting the operation and the quality of structures,
systems, components, and servicesaddressed in the RSQM. The QAP will be implemented by organizations responsible for achieving and verifying quality assurance.

IV. The Chief Generation and Grid Assets Officer has delegated the responsibility andauthority for developing the QAP to the Director, Power Generation and executing theQAP to the Director, Audit Services.

Any conflicts or questions involving interpretation of the requirements or resulting from the implementation of the QAP must be referred tothe Director, Audit Services.

Chris Moffitt Claire Rogers Frankie McDermott

Director, Power Generation
Director, Audit Services Chief Generation and GridAssets Officer RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 3 OF 77Table of ContentsI. ORGANIZATION 1.0 PURPOSE .................................................................

92.0 REFERENCES

............................................................

93.0 POLICY ....................................................................

94.0 ORGANIZATION AND REQUIREMENTS.............................

105.0 RESPONSIBILITIES

....................................................

11II. QUALITY ASSURANCE PROGRAM1.0 PURPOSE................................................................

1

22.0 REFERENCES

...........................................................

123.0 POLICY...................................................................

124.0 GENERAL REQUIREMENTS...........................................

135.0 RESPONSIBILITIES

....................................................

156.0 ATTACHMENTS.........................................................

15I1-1 Application of Rancho Seco Quality Assurance Program Criteria

........

1611-2 Regulatory Commitments................................................18 11-3 Exceptions

..............................................................

20II1. DESIGN CONTROL1.0 PURPOSE................................................................

2

72.0 REFERENCES

...........................................................

273.0 POLICY...................................................................

274.0 GENERAL REQUIREMENTS...........................................

285.0 RESPONSIBILITIES

....................................................

30 RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 4 OF 77IV. PROCUREMENT DOCUMENT CONTROL1.0 PURPOSE................................................................

3

12.0 REFERENCES

...........................................................

313.0 POLICY...................................................................

314.0 GENERAL REQUIREMENTS.......................................

315.0 RESPONSIBILITIES

....................................................

33V. INSTRUCTIONS, PROCEDURES.

AND DRAWINGS1.0 PURPOSE................................................................

3

52.0 REFERENCES

...........................................................

353=0 POLICY ...................................................................

354.0 GENERAL REQUIREMENTS...........................................

355.0 RESPONSIBILITIES

....................................................

36VI. DOCUMENT CONTROL1.0 PURPOSE.............................................................

3

72.0 REFERENCES

...........................................................

373.0 POLICY...................................................................

374.0 GENERAL REQUIREMENTS...........................................

375.0 RESPONSIBILITIES

....................................................

38 RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 5 OF 77VII. CONTROL OF PURCHASED MATERIAL.

EQUIPMENT.

ANDSERVICES1.0 PURPOSE ...........................................................

3

92.0 REFERENCES

...........................................................

393.0 POLICY...................................................................

394.0 GENERAL REQUIREMENTS

.........................................

395.0 RESPONSIBILITIES

....................................................

41VIII. IDENTIFICATION AND CONTROL OF MATERIALS.

PARTS. &COMPONENTS 1.0 PURPOSE................................................................

4

22.0 REFERENCES

...........................................................

423.0 POLICY...................................................................

424.0 GENERAL REQUIREMENTS...........................................

425.0 RESPONSIBILITIES

....................................................

43IX. CONTROL OF SPECIAL PROCESSES 1.0 PURPOSE...............................................................

4

52.0 REFERENCES

...........................................................

453.0 POLICY...................................................................

454.0 GENERAL REQUIREMENTS...........................................

455.0 RESPONSIBILITIES

....................................................

46 RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-01O REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 6 OF 77X. INSPECTION 1.0 PURPOSE................................................................

4

72.0 REFERENCES

................

...........................................

473.0 PO LIC Y .........................

......................................

474.0 GENERAL REQUIREMENTS...........................................

475.0 RESPONSIBILITIES

....................................................

49XI. TEST CONTROL1.0 PURPOSE................................................................

5

02.0 REFERENCES

...........................................................

503.0 POLICY...................................................................

504.0 GENERAL REQUIREMENTS...........................................

505.0 RESPONSIBILITIES

....................................................

52XII. CONTROL OF MEASURING AND TEST EQUIPMENT 1.0 PURPOSE................................................................

5

32.0 REFERENCES

...........................................................

533.0 POLICY...................................................................

534.0 GENERAL REQUIREMENTS...........................................

535.0 RESPONSIBILITIES

....................................................

54 RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: PANCHO SECO QUALITY MANUAL PAGE 7 OF 77XIII. HANDLING.

STORAGE.

AND SHIPPING1.0 PU R PO SE ...................

.............................................

5

52.0 REFERENCES

................

...........................................

553.0 POLICY...................................................................

554.0 GENERAL REQUIREMENTS...........................................

555.0 RESPONSIBILITIES

....................................................

56XIV. INSPECTION.

TEST. AND OPERATING STATUS .1.0 PU R PO SE ...................

.............................................

5

72.0 REFERENCES

...........................................................

573.0 PO LIC Y .....................

..............................................

574.0 GENERAL REQUIREMENTS...........................................

575.0 RESPONSIBILITIES

....................................................

58XV. NONCONFORMING MATERIALS.

PARTS. OR COMPONENTS 1.0 PU RPO SE ................................................................

5

92.0 REFERENCES

................

...........................................

593.0 POLICY...................,................................................

594.0 GENERAL REQUIREMENTS...........................................

595.0 RESPONSIBILITIES

....................................................

60 RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 8 OF 77XVI. CORRECTIVE ACTION1.0 PU R PO SE ................................................................

6

12.0 REFERENCES

...........................................................

613.0 POLICY ..............................................................

614.0) GENERAL REQUIREMENTS...........................................

615.0 RESPONSIBILITIES

................................................

62XVII. QUALITY ASSURANCE RECORDS1.0 PURPOSE ................................................................

6

32.0 REFERENCES

...........................................................

633.0 PO LIC Y .....................

..............................................

634.0 GENERAL REQUIREMENTS...........................................

635.0 RESPONSIBILITIES

..................................................

64XVIII. AUDITS1.0 PURPOSE ............................................................

6

52.0 REFERENCES

...........................................................

653.0 PO LIC Y .....................

..............................................

654.0 GENERAL REQUIREMENTS...........................................

655.0 RESPONSIBILITIES

....................................................

666.0 AUDITS AND AUDIT FREQUENCIES.................................

67Appendix A10 CFR 50 ADMINISTRATIVE CONTROLS

.......................

69 RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 9 OF 77I. ORGANIZATION 1.0 PURPOSEThis section describes the Sacramento Municipal Utility District (SMUD)organization and personnel responsible for establishing, implementing, andverifying the Quality Assurance Program (QAP) at the Rancho Seco nuclearfacility, which includes the Rancho Seco Nuclear Generating Station (RSNGS)licensed under 10 CFR Part 50 and the Rancho Seco Independent Spent FuelStorage Installation (ISFSI) licensed under 10 CFR Part 72.2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion I, Organization 2.2 ANSI N45.2-1 971, Section 3, Organization 2.3 Safety Guide 33/ANSI N18.7, Administrative Controls for Nuclear PowerPlants2.4 Rancho Seco Quality Manual, Appendix A2.5 10 CFR 71.103, Quality Assurance Organization 2.6 10 CFR 72.142, Quality Assurance Organization 3.0 POLICY3.1 The establishment and implementation of the Rancho Seco QAP, which iscomprised of this Rancho Seco Quality Manual (RSQM) and the RSQMimplementing procedures, shall be SMUD's responsibility.

Some QAPfunctions may be delegated to other SMUD approved external organizations, but overall responsibility for the QAP remains with SMUD.3.2 Definitive lines of authority, responsibility, and communication shall beestablished for those organizations involved in the QAP.3.3 Quality Assurance personnel assigned to the Rancho Seco nuclear facilityhave defined responsibilities and organizational freedom to identify problemsthat affect quality; to initiate, recommend, or provide solutions; and to verifyimplementation of solutions.

They have the authority to initiate action to stopunsatisfactory work pending implementation of necessary corrective action tobring the unsatisfactory conditions into conformance.

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 10 OF 773.4 The organizational structure and functional responsibility assignments shallbe such that attainment of program objectives is accomplished by individuals or groups who inspect,

examine, audit or otherwise verify conformance toestablished requirements, and who are independent of the individuals orgroups who performed the original activity.

4.0 ORGANIZATION AND REQUIREMENTS 4.1 The General Manager (GM) through the Chief Generation and Grid AssetsOfficer shall have corporate responsibility for overall safe operation of theRancho Seco nuclear facility and shall take any measures needed to ensureacceptable performance of the staff in providing long term monitoring of theremaining radioactive waste.4.2 The Manager, Rancho Seco Assets reports directly to the Director, PowerGeneration.

The Manager, Rancho Seco Assets ensures that the RanchoSeco nuclear facility is properly staffed and adequately budgeted to staff can safely carry out their responsibilities.

The Manager, Rancho Sec0.Assets also coordinates quality concerns with the Quality Assurance group.The Manager, Rancho Seco Assets is responsible for the safe and reliableoperation of RSNGS, pursuant to 10 CFR Part 50, and the ISFSI, pursuant to10 CER Part 72. The Manager, Rancho Seco Assets has the responsibility and authority to implement the QAP and ensure optimum qualityperformance of the Rancho Seco nuclear facility...

The Manager, Rancho Seco Assets is responsible for the administrative

actions necessary to ensure that the QAP is implemented by the groupsunder his direction.

To this extent, the Manager, Rancho Seco Assets shallmaintain continuing involvement in quality matters and shall assess thescope, status, implementation, and effectiveness of the QAP through thereview of Quality Assurance Audits and Surveillances.

4.3 The Director, Audit Services, through the Principal Quality Engineer, isresponsible for the Rancho Seco nuclear quality assurance program.

TheAudit and Quality Services group is independent from operating pressures orother lines of authority, and ensures an active QAP is implemented at theRancho Seco nuclear facility in accordance with regulatory requirements.

The Audit and Quality Services group has the authority to take any issueconcerning the quality of operations at the Rancho Seco nuclear facility tothe Director, Power Generation.

4.4 The Audit and Quality Services group shall have sufficient authority andorganizational freedom to identify problems that affect quality, recommend RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 11 OF 77solutions, and verify implementation of solutions, as appropriate.

Commensurate with this responsibility is the authority to initiate action to stopunsatisfactory work pending correction of the unsatisfactory condition.

Corporate and on-site organizational responsibilities are described in greaterdetail in Rancho Seco Administrative Procedure RSAP- 0101. Specific dutiesand responsibilities for organizations whose activities affect quality aredescribed in RSQM Sections II through XVIII and Appendix A.The Manager, Rancho Seco Assets advises the Director, Power Generation on matters related to the safety of operations at the Rancho Seco nuclearfacility.

The Manager, Rancho Seco Assets performs safety reviews and providesonsite management oversight of Rancho Seco nuclear facility activities.

The Manager, Rancho Seco Assets is responsible for reviewing all Potential;:

Deviations from Quality (PDQ) to determine if a condition is a Deviation from?:Quality (DQ) and requires determination of the cause, extent, remedialI corrective

actions, and actions to prevent recurrence.

The Manager, RanchoSeco Assets reviews and approves DQ dispositions and assigns corrective I actions identified in DQ dispositions.

The Manager, Rancho Seco Assetsalso determines whether a PDQ is potentially reportable pursuant to 10 CFR21.5.0 GENERAL RESPONSIBILITIES The nuclear organization is involved in the long term monitoring of the Rancho Seco nuclear facility and is responsible for describing and clearly defining theduties and authority of individuals whose work affects quality.

RSAP-01 01 definesthe Rancho Seco nuclear facility organization and the responsibilities associated with each onsite work group. Each work group has the responsibility to ensure thattheir procedures implement QAP requirements.

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD.-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 12 OF 77i1. QUALITY ASSURANCE PROGRAM1.0 PURPOSEThe purpose of this section is to describe the Rancho Seco QualityAssurance Program (QAP) implemented at the Rancho Seco nuclearfacility, which includes the Rancho Seco Nuclear Generating Station(RSNGS; licensed and undergoing decommissioning pursuant to 10 CFR50) and the Rancho Seco Independent Spent Fuel Storage Installation (ISFSI; licensed and operated pursuant to 10 CFR 72).

2.0 REFERENCES

2.1 10 CFR 50, Appendix B, Criterion II, Quality Assurance Program2.2 ANSI N45.2-1971, Section 2, Quality Assurance Program ,2.3 Safety Guide 33/ANSI N18.7, Administrative Controls for NuclearPower Plants2.4 10 CFR 71, Subpart H, Quality Assurance Requirements for Packaging and Transportation of Radioactive Material2.5 10 CFR 72, Subpart G, Quality Assurance Requirements for, theIndependent Storage of Spent Nuclear Fuel2.6 NRC Form 311, Quality Assurance Approval for Radioactive MaterialPackages, Approval No. 04893.0 POLICYThe QAP described herein is designed to ensure compliance with therequirements of 10 CFR 50, Appendix B, "Quality Assurance Criteria forNuclear Power Plants and Fuel Reprocessing Plants" including therequirements of applicable NRC Regulatory Guides and ANSI Standards.

Also, the QAP is designed to fulfill the quality requirements for (1) the useof radioactive material transport packages and (2) the operation of theRancho Seco Independent Spent Fuel Storage Installation (ISFSI) inaccordance with 10 CFR 71.101(f) and 10 CFR 72.140(d),

respectively.

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: PANCHO SECO QUALITY MANUAL PAGE 13 OF 774.0 GENERAL REQUIREMENTS 4.1 This Rancho Seco Quality Manual (RSQM) is organized to present the18 quality criteria in the order they are addressed in 10 CFR 50,Appendix B. The RSQM states the Rancho Seco policy for eachcriterion and describes how controls pertinent to each criterion are to becarried out.4.2 In accordance with 10 CFR 50.54(a),

SMUD submits an annual reportto the Nuclear Regulatory Commission (NRC) regarding RSQMchanges that do not reduce the commitments previously accepted bythe NRC. Also, in accordance with 10 CFR 50.54(a),

SMUD submitsRSQM changes that reduce commitments previously accepted to theNRC for their review and approval prior to implementation.

4.3 The QAP is implemented by organizations responsible for achieving quality and by organizations responsible for verifying quality.4.4 Engineering identifies the Quality Assurance (QA) classification ofstructures,

systenis, and components (SSCs) commensurate to theirimportance to safety.4.5 Quality Assurance classification 1 (QA Class 1) is assigned to SSCsthat are considered safety-related in accordance with 10 CFR 50,Appendix B.4.5.1 The QA Class I assignment includes 10 CFR 72 (ISFSl) and 10CFR 71 (Transportation Package)

SSCs as specified in RSAP-0302.

4.5.2 All 18 elements of the 10 CFR 50, Appendix B quality criteria applyto activities affecting QA Class I SSCs during operation, maintenance,

testing, and modifications.

4.6 Some 10 CFR 50, Appendix B quality criteria apply to non-QA Class 1programs and activities such as radiation protection, emergency preparedness, radioactive waste handling and shipping, fire protection, facility operations, environmental monitoring,

security, training, and 10CFR 71/72 important-to-safety, as indicated in RSQM-Section II,Attachment Il-I.4.6.1 Engineering identifies thel0 CFR 71 and 10 CFR 72 non-QA Class1 SSCs that are important-to-safety in accordance with RSAP-0302.

RANCHO SEWO LIUL;NSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 14 OF 774.6.2 SMUD activities performed under 10 CFR 71 shall be limited toprocurement, maintenance, repair, and use as authorized by theNRC Quality Assurance Program Approval for Radioactive MaterialPackages (NRC Form 311; Approval Number 0489).4.7 Attachment Il-I indicates the minimum QAP criteria that must beapplied to specific Program Activity Areas.4.8 Attachments 11-2 and 11-3 tabulate the NRC regulatory guides and ANSIstandards, with exceptions and applicable revisions, that SMUD iscommitted to meeting as part of its QAP.4.9 Activities associated with the safe operation of the Rancho Seconuclear facility are accomplished under controlled conditions.

Preparations for such activities include confirmation that prerequisites have been met.4.11 Development,

control, and use of computer programs associated-with the design and safe operation of the Rancho Seco nuclear facility aresubject to appropriate controls.

4.12 Training programs shall be established to ensure personnel responsible for performing and verifying activities that affect quality have therequired proficiency and qualifications to perform the assigned tasks.4.13 QAP Policy/Procedures/Instructions:

a. The QAP is documented in written policies, procedures, and .instructions.

The overall policies and general requirements areoutlined in the RSQM. Specific details related to implementation ofthe established QAP policies are contained in Rancho SecoAdministrative Procedures (RSAPs).

Organizations responsible forperforming QAP functions shall prepare additional implementing procedures as necessary.

Quality reviews RSAPs to ensure RSQMrequirements are accomplished in a controlled manner.b. Quality is responsible for RSQM preparation,

issuance, and control.The RSQM, including any changes, supplements, or attachments, isissued and maintained as a controlled document.
c. Quality and the Site Manager shall review and approve proposedRSQM changes.

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 15 OF 774.14 Resolution of Differences:

RSQM requirements take precedence over differing qualityrequirements specified in other work group procedures until Qualityevaluates the issue and determines which requirements must bemodified.

Questions or disputes involving RSQM interpretation or implementation must be referred to Quality for resolution.

4.15 Packaging and Transportation of Radioactive Material:

The QAP shall be applied to packaging and transportation ofradioactive material as specified in References 2.4 and 2.6.5.0 RESPONSIBILITIES General organizational responsibilities are described in RSQM Section I,ORGANIZATION

6.0 ATTACHMENTS

Il-I, Application of Rancho Seco Quality Assurance Program Criteria11-2, Regulatory Commitments 11-3, Exceptions RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 16 OF 77(A)(B)(C)Attachment I1-1 (Page 1 of 2)APPLICATION OF RANCHO SECO QUALITY ASSURANCE PROGRAM (QAP) CRITERIA (A, B, C)An 'X' means application of the RSQM requirements associated with the QAP Criteria is required.

No 'X' means application of the RSQM requirements associated with the QAP Criteria is optional.

RSQM implementing details are provided in the RSAPs and other QAP implementing procedures._______

QAP'CRITERIA

ProgramActivity Areas_____

__efrn s4,I I_1 Ill IV V VIl VIIJ VIIIl IX X Xl_ XIIl XIIIl XIV XV XV. I XVII XVIII References Safety Related / 10 CFR 71/72 ISFSI TS 5.4.1kImportant-to-Safety, Category A X X X X X X X X X X X X X X X X X X RSQM, APP. A,(QA Class 1) 10 CFR 50, APP. B______________________

____ ____RSAP-0302, Alr. 6Facility Operations (License ISFSI TS 5.4.1kCondition and Tech. Spec. x x X x X X x X X Xx RSQM Section XVllICompliance)

___10 CFR 50/72 LicensesISF5l TS 5.4,1kRadiation Protection X X X(2) X X X X X X 10OCFR 20_______ ___ _____RSQM, APP. ARadioactive Effluent Control ISFS1 TS 5.4.1kProgram (RECP) (3) X X X X X X X X X X Reg. Guide 4.15RSQM, APP. A______________________

_____10 CFR 50, APP. IRadiological Environmental ISFSI TS 5.4.1kMonitoring Program (REMP) (3) X X X14) X X X X X X X Reg. Guide 4.15____________________RSQM, APP. ARadwaste Handling and ISF51 TS 5.4.1kShipping (Including Process X X X X X X X X X X X X X 10 CFR 71Control Program)

()10 CFR 20.2006(d)

RSAP-0302, ATT. 6____________________RSQM, APP. AISFSI TS 5.4.1k & 5.7Fire Protection (6 X X X X X X X X RSQM, APP. A__________________________Decommissioning OrderISFSI TS 5.4.1kSecurity (7) X X X X X X X X 10OCFR 72.44 &18610 CFR 73ISFSI TS 5.4.1kEmergency Preparedness X X X X X X X X 10 CFR 50.54(t)10 CFR 50, APP. E__________RSOM, APP. AISFS1 TS 5.4.1kTraining X X X X X X X X 10OCFR 72.190____ RSQM, APP. A10 CFR 71/72 Important-to-ISFIS TS 5.4.1kSafety, Category B &C (5 X X X X X X X X X X X X X X RSAP-0302,ATT.

6(QA Class 2) 10 CFR 72.3 & 72.140________________________

__________

____ ___ _____ ___________10 CFR 71.101Attachment I1-1 (Page 1 of 2)

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 17 OF 77Footnotes:

(1) 10 CFR 50, Appendix B, Quality Criteria and corresponding RSQMsection titles:I. Organization II. Quality Assurance CriteriaIII. Design ControlIV. Procurement Document ControlV. Instruction, Procedures, and DrawingsVI. Document ControlVII. Control of Purchased

Material, Equipment, and ServicesVIII. Identification and Control of Materials, Parts, and Components IX. Control of Special Processes X. Inspection XI. Test ControlXII. Control of Measuring and Test Equipment XIII. Handling,
Storage, and ShippingXIV. Inspection, Test, and Operating StatusXV. Nonconforming Materials, Parts, or Components XVI. Corrective ActionXVII. Quality Assurance RecordsXVIII. Audits(2) Design Control as applied to permanent protective shielding.

(3) Rancho Seco applies the NRC Regulatory Guide 4.15 QA/QC program tothe RECP and REMP. This Regulatory Guide 4.15 program meets theapplicable 10 CFR 50, Appendix B QAIQC program requirements.

(4) As applied to environmental monitoring laboratory analysis services.

(5) As applied to 10 CFR 71 activities authorized pursuant to NRC Form 311,"Quality Assurance Approval for Radioactive Material Packages,"

Approval No. 0489. (Refer to RSQM Section II, Steps 4.3.2 and 4.4.2)(6) No Fire Protection equipment or services falls under the QAP.ATTACHMENT Il-1 (Page 2 of 2)REGULATORY COMMITMENTS

.RANCHO SECO LICENSING BASIS DOCUMENTNUMBER: RSLBD-010 REVISION:

2PAGE 18 OF 77TITLE: RANCHO SECO QUALITY MANUALSMUD commits to the requirements of the regulations and industry standards listedbelow with any exceptions identified in Attachment 11-3.DocumentRevision/Date Title1 Regulatory Guide1.82 Safety Guide 28ANSI N45.23 Regulatory Guide1.28ANSI/ASME NQA-Supplement 17S-14 Safety Guide 30ANSI N45.2.45 Safety Guide 336Regulatory Guide1.37ANSI N45.2.17 Regulatory Guide1.38ANSI N45.2.28 Regulatory Guide1.39ANSI N45.2.39/756/7/7219718/8519838/11/721972Personnel Selection and TrainingPer ISFSI Tech. Spec. 5.3Quality Assurance Requirements forNuclear Power PlantsSupplementary Requirements for QualityAssurance Records (See Attachment 11-3,Exception No. 1)Quality Assurance requirements for theinstallation, Inspection, and Testing ofInstrumentation and Electrical Equipment (See Attachment I1-3, Exception No. 2)11/3/72 Administrative Controls for Nuclear PowerPlants as Addressed in RSQM Appendix A3/16/7319733/16/7319723/16/731973Quality Assurance Requirements forCleaning Fluid Systems and Associated Components of Water-Cooled NuclearPower Plants (See Attachment 11-3,Exception No. 3)Quality Assurance Requirements forPackaging,

Shipping, Receiving, Storageand Handling of Items for Water-Cooled Nuclear Power Plants (See Attachment II-3, Exception No. 8)Housekeeping Requirements for Water-Cooled Nuclear Power Plants (SeeAttachment 11-3, Exception No. 4)ATTACHMENT 11-2 (Page 1 of 2)

PANCHO SECO LICENSING BASIS DOCUMENTTITLE: RANCHO SECO QUALITY MANUALNUMBER: RSLBD-010 REVISION:

2PAGE 19 OF 779 Regulatory Guide1.54ANSI N101.410 Regulatory Guide1.58ANSI N45.2.611 Regulatory Guide1.64ANSI N45.2.1112 Regulatory Guide1.74ANSI N45.2.1013 Regulatory Guide1.94ANSI N45.2.514 Regulatory Guide1.116ANSI N45.2.815 Regulatory Guide1.12016 Regulatory Guide1.123ANSI N45.2.1317 Regulatory Guide1.144ANSI N45.2.1218 Regulatory Guide1.146ANSI N45.2.236/7319729/80197810/7319742/741973Rev. 219786/76197511/777/7719761/7919778/801978Quality Assurance Requirements forProtective Coatings Applied to NuclearFacilities Qualification of Nuclear Power PlantInspection, Examination, and TestingPersonnel (See Attachment 11-3, Exception No. 5)Quality Assurance Requirements for theDesign of Nuclear Power Plants (SeeAttachment 11-3, Exception No. 6)Quality Assurance Terms and Definitions (See Attachment 11-3, Exception No. 7)Quality Assurance Requirements forInstallation, Inspection, and Testing ofStructural Concrete and Structural Steelduring the Construction Phase of NuclearPower PlantsQuality Assurance Requirements forInstallation, Inspection, and Testing ofMechanical Equipment and SystemsFire Protection Guidelines for NuclearPower PlantsQuality Assurance Requirements forControl of Procurement Items and Servicesfor Nuclear Power PlantsAuditing of Quality Assurance Programsfor Nuclear Power PlantsQualification of Quality Assurance ProgramAudit Personnel for Nuclear Power PlantsATTACHMENT 11-2 (Page 2 of 2)EXCEPTIONS:

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 20 OF 77EXCEPTION NO. 1: Regulatory Guide 1.28/NQA-1, Supplement 17S-1SMUD complies with the recommendations of this regulatory guide with the following clarifications:

With regard to Section 2.4 of Supplement 17S-1 titled Index: The phrase "anindex" is clarified to mean a collection of documents or indices which, when takentogether, supply the information attributed to "an index" in the standard.

The specific location of a record "within a storage area" may not be delineated (e.g., the specific location within a computer record file may not be constant;

further, SMUD may utilize a computer assisted random access filing systemwhere such location could not be readily "documented,"

or would such a locationbe "relevant.")

The storage location will be delineated, but where file locations change with time, the specific location of a record within that file may not alwaysbe documented.

With regard to Section 4.3, Supplement 17S-1 titled Safekeepincq:

Routine generaloffice and nuclear site security systems and access controls are provided:

Nospecial security systems are required to be established for record storage areas.With regard to Section 4.4, Supplement 17S-1, titled Facility:

This Sectionprovides no distinction between temporary and permanent facilities.

To covertemporary

storage, the following clarification is added: "Records completed butnot yet transferred for permanent storage may be temporarily stored in one-hourfire rated file cabinets.

In general, records shall not be maintained in suchtemporary storage for more than four months after completion without beingmicrofilmed or placed in permanent storage.

Open-ended documents revised orupdated on a more-or-less continuing basis over an extended period of time (e.g.personnel qualification and training documents, equipment history cards) whichare cumulative in nature (e.g. nonconforming item logs and control room logbooks) shall become QA records when they are issued as a specific revision (e.g.the master audit schedule);

when they are filled-up or discontinued (e.g. log booksor equipment history cards); on a predefined periodic basis when the completed portion of the ongoing document shall be transferred to records control as a"record" (e.g. training and qualification records).

ATTACHMENT 1I-3 ('Pacie 1 of 7)

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 21 OF 77EXCEPTION NO. 2: Regulatory Guide 1.30/ANSI N45.2.4-.72 Specific clarifications for ANSI N45.2.4-1 972 are indicated below by section:Section 1.4Definitions in this standard that are not included in ANSI N45.2.10 shall be used; alldefinitions which are included in ANSI N45.2.10 shall be used as clarified in SMUDcommitment to Regulatory Guide 1.74.Section 2.1Planninqi requirements, as determined by engineering, shall be incorporated intomodification procedures.

Section 2.3Procedures and Instructions shall be implemented as set forth in Sections II, III, V, X andXl of this program and by compliance with the Rancho Seco Plant Technical Specifications and Regulatory Guide 1.33 (ANSI N18.7).Section 2.4Results will be implemented as set forth in Sections X, Xl, and XVII of this program andby compliance with ANSI N18.7 in lieu of the requirements set forth here.Section 2.5.2Calibration and Control covers three classes of instrumentation used by SMUD: (1)M&TE (portable measuring instruments, test equipment, tools, gages, and non-destructive test equipment used in measuring and inspecting safety-related structures,

systems, and components);

(2) reference standards (primary, secondary,

transfer, andworking);

and (3) permanently installed process instrumentation (PI).With respect to the first sentence, M&TE and reference standards shall be included incalibration program and shall either be calibrated at prescribed intervals or shall becalibrated prior to use. With respect to the last sentence, personnel shall be trained andprocedures shall require that the calibration sticker shall be reviewed to determine calibration status prior to use: This label shall be considered to clearly identify equipment that is out of calibration.

Lack of a sticker shall require record review and affixing a new sticker based oncalibration data. M&TE and reference standards shall comply with sentences 2, 3, and4.ATTACHMENT II-3 (Paaie 2 of 7)

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 22 OF 77With respect to the third sentence, SMUD uniquely identifies each safety-related component of permanently installed process instrumentation.

This identification provides traceability to calibration data. These actions are SMUD's alternative to thetagging or labeling of items to indicate the calibration date and the identity of theperson who performed the calibration.

Permanently installed process instrumentation shall comply with sentences 1, 2, and 5.Section 3Pre-construction Verification will be implemented as follows:

(1) is required only formodifications, (2) no special checks are required to be made by the personwithdrawing a replacement part from the warehouse equivalent controls are ensuredby compliance with Regulatory Guide 1.38 (ANSI N45.2.2) as set forth in this table,and, (3) shall be complied with as determined by engineering, by individual technicians as part of the modification process.Section 5.1Inspections, including subsections 5.1.1, 5.1.2, and 5.1.3, will be implemented as setforth in Section X of this program.

The inspection program will incorporate,=

asdetermined by engineering and Quality those items listed in these subsections.

Section 5.2Tests, including subsections 5.2.1 through 5.2.3, will be implemented as set forth inSections IIl and Xl of this program.

In some cases Surveillance testing may be usedto meet the appropriate requirements of this section.Section 6Post Construction Verification is not generally considered applicable at operating facilities because of the scope of the work and the relatively short interval betweeninstallation and operation.

Where considered necessary by engineering andl Quality,the elements described in this Section will be used in the development andimplementation of inspection and testing programs as describe in Sections III, X, andXl of this program.Section 7Data Analysis and Evaluation will be implemented as stated herein after adding theclarifying phrase "Where used" at the beginning of that paragraph.

ATTACHMENT 11-3 (Paae 3 of 7)

.RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 23 OF 77EXCEPTION NO. 3: Regulatory Guide 1.37/ANSI N45.2.1-73 Specific clarifications for this Regulatory Guide and ANSI N45.2.1-1 973 are indicated below:With regard to Paragraph C.3 of Regulatory Guide 1.37: The water quality for finalflushing of fluid systems and associated components shall be at least equivalent tothe quality of the operating system water, except for the oxygen and nitrogen content;but this does not infer that chromate's or other additives, normally in the systemwater, will be added to the flush water.With regard to Paragraph 0.4 of Regulatory Guide 1.37: Expendable materials, suchas inks and related products; temperature indicating sticks; tapes; gummed labels;wrapping materials (other than polyethylene);

water soluble dam materials; lubricants; NDT penetrant materials and couplants, desiccants, which contactstainless steel or nickel alloy surfaces shall not contain lead, zinc, copper, mercury,cadmium and other low melting points metals, their alloys or compounds as basicand essential chemical constituents.

No more than 0.1 percent (1,000 ppm)halogens will be allowed where such elements are leachable or where they could bereleased by breakdown of the compounds under expected environmental conditions.

With regard to Section 5 of ANSI N45.2.1-1 973 titled Installation Cleaning:

Therecommendation that local rusting on corrosion resistant alloys be removed bymechanical methods is interpreted to mean that local rusting may be removedmechanically, but the use of other removal means is not precluded, as determined byEngineering or Chemistry.

EXCEPTION NO. 4: Regulatory Guide 1.39/ANSI N45.2.3-73

.Specific classifications for ANSI N45.2.3-73 are indicated for specific sections below:Section 1.4Definitions:

Definitions in this standard that are not included in Regulatory Guide 1.74(ANSI N45.2.10) will be used. All definitions that are included in ANSI N45.2.10 willbe used as clarified in SMUD's commitment to Regulatory Guide 1.74.Section 2.1 ..Planning:

SMUD may choose not to utilize the five-level zone designation system, butwill utilize standard janitorial and work practices to maintain a level of cleanliness commensurate with program requirements in the areas of housekeeping, plant andpersonnel safety, and fire protection.

ATTACHMENT II-3 ('Pane 4 of 7)

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 24 OF 77Cleanliness will be maintained, consistent with the work being performed, so as toprevent the entry of foreign material into safety-related systems.

This will include, as aminimum, documented cleanliness inspections that will be performed prior to systemclosure.

As necessary, (e.g. the opening is larger than the tools being used) control ofpersonnel, tools, equipment, and supplies will be established when the reactor systemis opened for inspection, maintenance, modification or repair.Additional housekeeping requirements will be implemented as required for control ofradioactive contamination.

Section 2.2Procedures and Instructions:

Appropriate procedures will be written and implemented.

Section 3.2Control of Facilities:

SMUD may choose not to utilize the five-level zone designation system, but will utilize standard janitorial and work practices to maintain a level ofcleanliness commensurate with program requirements in the areas of housekeeping, plant and personnel safety, and fire protection.

Cleanliness will be maintained, consistent with the work being performed,

'so as toprevent the entry of foreign material into safety-related systems.

This will include, as aminimum, documented cleanliness inspections that will be performed prior to systemclosure.

As necessary, (e.g. the opening is larger than the tools being used) control ofpersonnel, tools, equipment, and supplies will be established when the reactor systemis opened for inspection, maintenance, modification or repair.Additional housekeeping requirements will be implemented as required for control ofradioactive contamination.

EXCEPTION NO. 5: Regulatory Guide 1.58/ANSI N45.2.6SMUD complies with the recommendation of the regulatory guide with the following clarification:

With regard to Paragraph C.5: The Level II1 function of inspection

planning, reviewing and concurring with inspection, examination and testing procedures is performed bydesignated individuals from the Quality & Industrial Safety Department.

ATTFACHMENT II-3 (Paae 5 of 7)

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 25 OF 77EXCEPTION NO. 6: Regulatory Guide 1.64/ANSI N45.2.11SMUD complies with the recommendation of the regulatory guide with the following clarification:

With regard to Paragraph C.2: In exceptional circumstances, the designer's immediate supervisor can perform design verification, provided:

1. The supervisor is the only technically qualified individual available.
2. The need is individually documented and approved in advance by thesupervisor's management.
3. QA audits cover frequency and effectiveness of use of supervisors as designverifiers to guard against abuse.EXCEPTION NO. 7: Regulatory Guide 1.74/ANSI N45.2.10-73 SMUD complies with the recommendations of this regulatory guide with the following clarifications:

SMUD reserves the right to define additional words or phrases that are not includedin this Standard.

Such additional definitions will be documented in appropriate procedures.

In addition to the Standard's definition of "Inspection,"

SMUD will use the following definition when referring to activities that are NOT performed by QC personnel:

Examining, viewing closely, scrutinizing, looking over or otherwise checking activities.

Personnel performing these functions are not necessarily certified to Regulatory Guide 1.58 (ANSI N45.2.6).

When SMUD intends for Inspection to be performed in accordance with the QAProgram by personnel certified as required by that program and for activities definedby "inspection" in ANSI N45.2.10, appropriate references to the plant QCorganization or the procedures to be used for performing the activity will be made. Ifsuch references are NOT made, inspections are to be considered under theadditional definition given above."Independent Verification":

Verification by an individual other than the person whoperformed the operation or activity being verified that required actions have beencompleted.

Such verification may not necessarily require confirmation of the actionat the physical location if adequate remote indication of completion of action isavailable.

In determining the acceptability of remote verification, the consequences of the action not being 100% completed and the validity of the remote indication forATTACHMENT 11-3 (Pagje 6 of 7)

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 26 OF 77confirming the completion of the desired action will be considered.

Examplesinclude, but are not limited to: Verification of a breaker opening by observed remotebreaker indication lights; verification of a set point (made with a voltmeter or ammeterfor example) by observing the actuation of status or indicating lights at the requiredpanel-meter indicated value; verification that a valve has been positioned byobserving the starting or stopping of flow on meter indications or by remote valvepositions indicating lights."Will": (Not defined in any ANSI Standard)

-Means the same as "shall" except whenused to denote simple futurity.

When used to denote futurity, "will" is normallyfollowed by "be".EXCEPTION NO. 8: Regulatory Guide 1.38/ANSI N45.2.2Section 2.7Classification of Items -SMUD may choose not to utilize the four levels of item'classification, but will address packaging and storage requirements for. items basedon the needs of individual items and manufacturers recommendation.

ATTACHMENT 11-3 (Pa~ie 7 of 7)

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 27 OF 77III. DESIGN CONTROL1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established for control of design activities affecting applicable structures,

systems, and components at the Rancho Seco nuclear station, whichincludes the Rancho Seco Nuclear Generating Station (RSNGS; licensed andundergoing decommissioning pursuant to 10 CFR 50) and the Independent Spent Fuel Storage Installation (ISFSI; licensed and operated pursuant to 10CFR 72).In addition, this section defines the requirements for developing andimplementing control measures that ensure design functions affecting theperformance of operational, construction, and modification activities are carriedout in a planned, controlled, and orderly manner and are in compliance withapplicable regulatory commitments.

2.0 REFERENCES

2.1 10 CER 50, Appendix B, Criterion Ill, "Design Control"2.2 10 CFR 50.59, Changes, Tests and Experiments 2.3 Regulatory Guide 1.64/ANSI N45.2.1 1, 1974, Quality Assurance Requirements for the Design of Nuclear Power Plants (with exceptions noted in RSQM Section II)2.4 ANSI N45.2, Section 4, Design Control2.5 10 CFR 72.48, Changes, Tests, and Experiments 2.6 10 CFR 71.107, Package Design Control2.7 10 CFR 72.146, Design Control3.0 POLICYThe requirements specified in this section apply to all organizations performing design functions for modifications,

changes, replacement or addition ofstructures,
systems, or components at the Rancho Seco nuclear facility.

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 28 OF 774.0 GENERAL REQUIREMENTS Procedures shall be established and executed to control design activities.

Procedures covering design control activities shall include the following requirements:

4.1 Applicable design inputs such as design bases, regulatory requirements, codes and standards, methodology, and all assumptions with appropriate justifications are identified, documented, and correctly translated intodesign output documents such as specifications,

drawings, procedures, orinstructions.

4.2 Exceptions, waivers to or deviations from engineering requirements aredocumented and controlled.

4.3 Methods are specified for the selection and classification of suitablematerials, parts, equipment, and processes used in meeting applicable requirements for structures,

systems, and components.

Materials, parts, components, and equipment that are standard, commercial (off the shelf), or which have been previously approved forother similar applications are reviewed for suitability and appropriately classified.

4.4 Systematic methods are established for communicating and controlling theflow of related design information across the external and internal designinterfaces, including any changes to the design information as the workprogresses.

4.5 Interfaces between Engineering and other participating designorganizations (either internal or external to SMUD) are identified anddocumented.

This identification includes those organizations providing design inputs, design analyses, design specifications, and designverification for operational, construction and modification design activities.

4.6 Participating design organizations establish and describe the controlled methods for preparation, review, approval,

release, distribution, andrevision of documents (such as design analyses, specifications,
drawings, reports) involving design interfaces.

4.7 Design control measures shall provide for verifying or checking the adequacyof design modifications or design changes.

Acceptable verification methodsinclude, but are not limited to, design reviews, alternate calculations, orqualification testing.

If a test program is used to verify the adequacy of a RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: PANCHO SECO QUALITY MANUAL PAGE 29 OF 77design, it must include qualification testing of a prototype unit under the mostadverse design conditions.

4.8 Computer program codes used for design calculations are certified for useand their use is specified.

4.9 Design verification is to be performed by competent individuals or groupsother than those who performed the original design, but who may be fromthe same organization.

The originator's supervisor may perform thisverification provided the supervisor is the only technically qualified individual available and meets the appropriate clarification provisions ofReference 2.4. The results of the design verification efforts must bedocumented with the identification of the verifier clearly provided.

4.10 Provisions are specified for the control of design analyses such as; reactorphysics, stress, thermal, hydraulic, and accident analyses; compatibility ofmaterials; accessibility for in-service inspection, maintenance, and repair;and delineation of acceptance criteria for inspections and tests.4.11 Design problems that are identified during field installation or testingactivities shall be documented and forwarded to Engineering forevaluation and resolution.

4.12 Design and specification

changes, including field changes, receive thesame degree of control and approval as the original design unless anotherqualified, responsible organization is specifically designated.

4.13 Errors and deficiencies in the design process, including computerprograms that could adversely affect structures,

systems, or components are documented and corrective action is taken to preclude repetition.

4.14 Proposed modifications or design changes which involve an Unreviewed Safety Question or a change to Rancho Seco nuclear facility Licenses orTechnical Specifications are handled in accordance with 10 CFR 50.59,10 CFR 72.48, and 10 CFR 71.107(c),

as appropriate.

4.15 Modifications are reviewed by plant personnel for effect on plant operation prior to making the modification operational.

4.16 Design documents are reviewed for accessibility of equipment andcomponents for in-service inspection, tests, maintenance or modifications.

4.17 Design and/or test documentation must be obtained from all suppliers onprocurements of ASME code components used for replacement ormodification to the Rancho Seco nuclear facility.

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 I REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 30 OF 775.0 RESPONSIBILITIES General organizational responsibilities are described in Section I,ORGANIZATION.

5.1 Engineering is responsible for implementing a design control processper this section and to:a. Provide and control design change packages.

b. Ensure integrity and regulatory conformance of configuration control.c. Provide plant configuration control including establishing andmaintaining baseline documents.
d. Provide engineering support for facility computers.
e. Perform probabilistic analysis in support of plant design, whennecessary.
f. Provide engineering support to the Rancho Seco nuclearorganization.
g. Provide and maintain engineering procedures, standards andspecifications and drawings.
h. Prepare and maintain the Master Equipment List (MEL)described in RSQM Section I1.5.2 Quality Assurance is responsible for:a. Review and concurrence of design control procedures.
b. Monitoring implementation of the design control program.c. Auditing the design control program per RSQM Section XVIII.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 31 OF 77IV. PROCUREMENT DOCUMENT CONTROL1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established to control procurement documents for material, equipment, and services at the Rancho Seco nuclear facility, which includes the RanchoSeco Nuclear Generating Station (RSNGS; licensed and undergoing decommissioning pursuant to 10 CFR 50) and the Rancho Seco Independent Spent Fuel Storage Installation (ISFSI; licensed and operated pursuant to 10CFR 72).2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion IV, Procurement Document Control2.2 ANSI N45.2-1 971, Section 5, Procurement Document Control2.3 Regulatory Guide 1.123/ANSI N45.2.13-1976, Quality Assurance Requirements for Control of Procurement of Items and Services forNuclear Power Plants2.4 10 CFR 71.109, Procurement Document Control2.5 10 CFR 72.148, Procurement Document Control3.0 POLICYProcurement documents for applicable Rancho Seco nuclear facility materials, equipment, components/spares, or services shall include applicable technical requirements, quality requirements, regulatory requirements, and otherprovisions necessary to ensure that purchased items and services areadequately described to the supplier.

4.0 GENERAL REQUIREMENTS 4.1 Procedures shall be established and implemented to control thepreparation, review, approval and issuance of procurement documents.

4.2 Procurement documents shall include provisions for the following, asapplicable:

a. Description of item or service.

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 32 OF 77b. Identification of design specifications and technical requirements byreference to specific

drawings, codes, regulations, industrystandards, or other documentation, including the applicable revisionthereto that describe the items or services to be furnished.
c. Identification of test, inspection, and acceptance requirements, andany special instructions and requirements for activities such asdesign, fabrication, identification,
cleaning, erecting, packaging,
handling, shipping, and extended storage.d. Identification of applicable QAP criteria.
e. Applicability of 10 CFR Part 21.f. Identification of the documentation, such as drawings, specifications, procedures, fabrication and inspection plans,inspection and test records, personnel and procedure qualifications, and chemical and physical test reports to be prepared andmaintained by the supplier or contractor, and the requirement tosubmit this documentation to SMUD for review and approval.
g. Identification of those records to be retained, controlled, andmaintained by the supplier or contractor and those to be delivered to SMUD at the time of shipment of the procured item.h. SMUD's right of access to the supplier's facilities and records forinspection and audits.i. Extension of applicable requirements to lower tier subcontractors and suppliers, including SMUD's right of access to facilities andrecords.j. Supplier submittal of nonconforming items and SMUD approval for"Accept as is" or "Repair" dispositions of non-conformances.
k. SMUD's right to hold shipment if procurement documentrequirements, including those for documentation, have not beenfulfilled.

4.3 Technical and quality review by qualified personnel and approval bydesignated individuals shall be performed prior to issuance of theprocurement document.

The review and approval shall be documented and available for verification.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 33 OF 774.4 Review and concurrence by Quality Assurance shall be performed toensure adequacy of quality requirements and to verify that therequirements are correctly stated, inspectable, and controllable; that thereare adequate acceptance and rejection criteria; and that the procurement documents have been prepared,

reviewed, and approved in accordance with the requirements of the established procedures.

4.5 Revisions to procurement documents shall receive an equivalent reviewand approval as the original documents.

Exceptions to this includechanges in quantity, estimated price, cost codes, taxes, format or editorial changes that do not affect the quality of the item or service.4.6 Procurement documents for spare or replacement parts for QA Class 1structures,

systems, or components shall specify procurement controls atleast equivalent to those required for purchase of the original equipment.

4.7 Methods shall be established to ensure that the items received aretraceable to procurement documents.

5.0 RESPONSIBILITIES

General organizational responsibilities are described in Section I,ORGANIZATION.

5.1 General Services is responsible for:a. Purchase items in conformance with procurement documents.

b. Purchase safety-related (QA Class 1) items from approvedsuppliers.
c. Arrange for suppliers to be placed on an Approved Suppliers List(ASL). (Refer to RSQM Section VII, step 4.2 regarding ASL)d. Arrange for source inspection when specified on the procurement documents.

5.2 Engineering is responsible for:Maintain a staff of qualified engineers who provide technical and qualityrequirements for purchasing safety-related (QA Class 1) items.5.3 Quality Assurance is responsible for:a. Review and concurrence of material management procedures.

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010

+I REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 34 OF 77b. Review and concurrence of procurement documents for safety-related (QA Class 1) items.c. Auditing the procurement document control program per RSQMSection XVIII.d. Developing and maintaining the ASL.

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 35 OF 77V. INSTRUCTIONS, PROCEDURES, AND DRAWINGS1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established to ensure that activities affecting the quality or safety ofthe Rancho Seco nuclear facility, which includes the Rancho Seco NuclearGenerating Station (RSNGS; licensed and undergoing decommissioning pursuant to 10 CFR 50) and the Rancho Seco Independent Spent Fuel StorageInstallation (ISFSI; licensed and operated pursuant to 10 CFR 72), are described and accomplished in accordance with documented instructions, procedures,

drawings, or other documents appropriate to the circumstances.

2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, andDrawings2.2 ANSI N45.2-1 971, Section 6, Instructions, Procedures, and Drawings2.4 Safety Guide 33/ANSI N18.7, Administrative Controls for Nuclear PowerPlants2.4 10 CFR 71.150, Instructions, Procedures, and Drawings2.5 10 CFR 72.111, Instructions, Procedures, and Drawings3.0 POLICYActivities affecting quality performance or operational safety at the Rancho Seconuclear facility shall be described and implemented in accordance withdocumented instructions, procedures, and drawings.

4.0 GENERAL REQUIREMENTS 4.1 Written instructions, procedures,

drawings, or other documents appropriate to the circumstances shall be prepared to provide measuresfor complying with the provisions of the QAP.4.2 Instructions, procedures, or drawings shall include applicable quantitative and/or qualitative acceptance criteria for verifying that the activities havebeen satisfactorily accomplished.

4.3 Procedures shall be established for the review, approval,

issuance, change, and use of documents that specify quality requirements such as RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 36 OF 77instructions, procedures,

drawings, and other documents that implement the QAP.4.4 Activities affecting quality shall be accomplished in accordance withapproved instructions, procedures, and drawings.

5.0 RESPONSIBILITIES

General organizational responsibilities are described in Section I,ORGANIZATION.

5.1 Rancho Seco management is responsible for ensuring activities that affectquality are described in instructions, procedures, and drawings.

5.2 Quality Assurance is responsible for performing audits to verify that anyactivities affecting quality are described in instructions, procedures and,drawings.

Audits shall be conducted in accordance with RSQM SectionXVIII.

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 37 OF 77VI. DOCUMENT CONTROL1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established for the issuance and control of documents that controlactivities affecting quality at the Rancho Seco nuclear facility, which includes theRancho Seco Nuclear Generating Station (RSNGS; licensed pursuant to 10 CFR50) and the Independent Spent Fuel Storage Installation (ISFSI; licensed andoperated pursuant to 10 CFR 72).2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion VI, Document Control2.2 ANSI N45.2-1 971, Section 7, Document Control2.3 ANSI N45.2.1 1-1 974, Section 7, Document Control2.4 10 CFR 71.113, Document Control2.5 10 CFR 72.152, Document Control3.0 POLICYApplicable documents, including changes thereto, that prescribe activities affecting the quality operation at the Rancho Seco nuclear facility shall be issuedand controlled in a manner that precludes the use of inappropriate or outdateddocuments.

4.0 GENERAL REQUIREMENTS 4.1 The responsible organization shall establish procedures that defineresponsibilities and delineate the sequence of actions to be accomplished in preparation, review, approval, and control of instructions, procedures, ordrawings, or changes thereto.4.2 Procedures that establish document control measures shall include:a. Identification of documents to be controlled;

b. Identification of individuals or organizations responsible for thereview, approval,
issuance, and revision of documents; PANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 38 OF 77c. Criteria to ensure that adequate technical and quality requirements are incorporated prior to implementation;

d. Review of changes to documents by the same organizations thatperformed the initial review and approval or by the organizations designated in accordance with the applicable procedures.

4.3 Controlled documents, including

changes, shall be issued and distributed to organizations noted on distribution lists so that proper and currentdocuments are available as required, and obsolete or superseded documents are identified and not used for prescribed activities.

4.4 Master lists or equivalent means shall be used to identify the currentrevision of controlled documents and made available at work locations, asappropriate.

5.0 RESPONSIBILITIES

General organizational responsibilities are described in Section I,ORGANIZATION.

5.1 Site Document Control (SDC) is responsible for developing andimplementing a document control program in accordance with this section.5.2 Rancho Seco management is responsible for:a. Complying with document review, approval, and revision authority defined in plant administrative procedures.

b. Ensuring Quality Assurance review of documents with qualityassurance related aspects, as appropriate.

5.3 Quality Assurance is responsible for:a. Reviewing and concurring with document control procedures.

b. Reviewing and concurring with prOcedures, instructions, ordocuments that implement the QAP to ensure compliance withapplicable RSQM provisions.
c. Auditing the document control program per RSQM Section XVIII.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 39 OF 77VII. CONTROL OF PURCHASED

MATERIAL, EQUIPMENT, ANDSERVICES1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established to ensure that material, equipment, and servicespurchased for the Rancho Seco nuclear facility, which includes the Rancho SecoNuclear Generating Station (RSNGS; licensed and undergoing decommissioning pursuant to 10 CFR 50) and the Independent Spent Fuel Storage Installation (ISFSI; licensed and operated pursuant to 10 CFR 72), conform to theprocurement documents.

2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion VII, Control of Purchased

Material, Equipment, and Services2.2 ANSI N45.2-1 971, Section 8, Control of Purchased
Material, Equipment,.

and Services2.3 Regulatory Guide 1.123/ANSI N45.2.13-76, Quality Assurance Requirements for Control of Procurement of Items and Services forNuclear Power Plants2.4 10 CFR 71.115, Control of Purchased

Material, Equipment, and Services2.5 10 CFR 72.154, Control of Purchased
Material, Equipment, and 3.0 POLICYMeasures shall be established to ensure that material, equipment, and servicesconform to the specified requirements of the related procurement documents.

4.0 GENERAL REQUIREMENTS 4.1 Control of purchased

material, equipment, and Services shall include thefollowing, as appropriate:
a. Source evaluation and selection of suppliers.
b. Objective evidence of quality furnished by the supplier.
c. Source inspection, audit, and/or surveillance activities.

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IBASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 40 OF 77d. Examination of items or services upon delivery or completion.

4.2 Results of source evaluation and selection of suppliers shall bedocumented and retained on file.4.3 Procedures for control of materials, equipment, and services shall addressthe following:

a. Responsibilities of departments performing supplier technical andquality evaluations, and the method of evaluation.
b. Inspection activities that specify the characteristics or processes tobe witnessed, inspected or verified; the method of verification andthe extent of documentation required; and the organization responsible for implementing the inspection.
c. Auditing to verify conformance and implementation to requirements of this policy. Source inspection and audits may not be necessary when conformance of an item to procurement requirements can beverified by receipt inspection, review of test reports, certified reportsor other means specified by Quality Assurance.
d. Receipt inspection of supplier furnished items to ensure: (1) theproper identification of items on the receiving documentation, (2)that the items are inspected and judged acceptable in accordance with predetermined instructions prior to installation or use, (3) thatinspection records or certificates of conformance are available atthe plant site prior to installation or use of the items, and (4) thatitems accepted and released are identified as to their inspection status prior to storage or use.e. Review, acceptance, and maintenance of records to ensureadequacy of documentation that identifies the purchased item, andthat specific procurement requirements (e.g., codes, standards, specifications) have been met or satisfied.
f. Review and approval of documentation required to be submitted bythe procurement documents (CMTR's, Certificate of Compliance, Procedures, Specifications, etc.).g. Procurement control of spare or replacement parts for QA Class 1systems to ensure compliance with requirements that are (1)equivalent to the original requirements or (2) specified by a properlyreviewed and approved revision to the original requirements.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 41 OF 775.0 RESPONSIBILITIES General organizational responsibilities are described in Section I,ORGANIZATION.

5.1 Engineering is responsible for:a. Ensuring quality and qualifications of parts and materials by (1)developing quality specifications and (2) storing parts and materials in accordance with regulatory requirements and in coordination withappropriate nuclear organization groups.b. Ensuring regulatory compliance of materials and parts by managingprocurement documentation and reviewing (and implementing, asappropriate)

NRC and related parts/materials bulletins.

c. Examining items or services upon delivery or completion, asdeemed necessary to supplement or replace formal inspection activities.

5.2 Quality Assurance is responsible for:a. Developing and maintaining the ASL.b. Performing required inspections, evaluations, and audits.c. The review and concurrence with material management procedures.

d. Auditing the control of purchased
material, equipment, and servicesper RSQM Section XVIII.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 42 OF 77VIII. IDENTIFICATION AND CONTROL OF MATERIALS, PARTS, &COMPONENTS 1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established to provide for the identification and control of material, parts, and components for the Rancho Seco nuclear facility, which includes theRancho Seco Nuclear Generating Station (RSNGS; licensed and undergoing decommissioning pursuant to 10 CFR 50) and the Independent Spent FuelStorage Installation (ISFSI; licensed and operated pursuant tol10 CFR 72).2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion VIII, Identification and Control ofMaterials, Parts and Components 2.2 ANSI N45.2-1 971, Section 9, Identification and Control of Materials, Parts,and Components 2.3 10 CFR 71.117, Identification and Control of Materials, Parts, andComponents 2.4 10 CFR 72.156, Identification and Control of Materials, Parts, andComponents 3.0 POLICYProcedures shall be established and implemented to ensure that materials, parts,or components are properly identified and controlled to preclude the use ofincorrect or nonconforming items.4.0 GENERAL REQUIREMENTS 4.1 Materials, parts, or components, including partially fabricated subassemblies and consumables, shall be identified so they can berelated to their applicable

drawing, specification, purchase
document, andinspection records at any stage from initial receipt throughfabrication/construction, installation, repair, modification, or use.4.2 Identification
controls, implementation procedures, and documentation shall be used to ensure that only correct and accepted items are usedduring all stages of construction, installation, and operation.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 43 OF 774.3 Unique identification of items is required, e.g., by part number, serialnumber, heat number, drawing identification number, or other traceable coding methods.4.4 Identification is required to be maintained either on the item or on recordstraceable to the item. Physical identification such as by marking ortagging shall be used to the maximum extent practical.

4.5 When specified by codes, standards, procurement documents, or otherrequirements, identification is required such that items are traceable toappropriate documentation (e.g., specifications,

drawings, purchaseorders, manufacturing and inspection documents, nonconformance
reports, physical or chemical mill test reports).

4.6 Where identification marking is employed, the marking is required to beclear, unambiguous and indelible, and shall be applied such as not toaffect the fit, function, or quality of the item.4.7 Markings shall be transferred to each part of an item, if subdivided.

Themarkings shall not be obliterated or hidden by surface treatment orcoatings unless other means of identification are substituted.

4.8 Procedures are required to provide for the verification and documentation of correct identification of items prior to release for use. Items may beconditionally released under adequate procedural controls.

4.9 Bulk consumables (such as weld rod, chemicals,

reagents, gases, resins,lubricating oil and grease, fuel oil, cleaning
solvents, etc.) must beidentified and controlled in accordance with approved procedures thatspecify the applicable requirements for identification and use of theconsumables.

4.10 In the event the identification or traceability of an item is lost, it shall behandled in accordance with RSQM Section XV.5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I,ORGANIZATION.

5.1 General Services is responsible for identification and control of items fromprocurement through withdrawal from the warehouse.

5.2 Maintenance is responsible for maintaining identification and control ofitems from withdrawal from the warehouse through installation.

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2PAGE 44 OF 775.3 Quality Assurance is responsible for:a. Review and concurrence of procedures for controlling

material, parts, and components from procurement through storage,issuance, and installation.
b. Auditing the process for identification and control of materials, parts, and components in accordance with RSQM Section XVIII.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 45 OF 77IX. CONTROL OF SPECIAL PROCESSES 1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established to control special processes used at the Rancho Seconuclear facility, which includes the Rancho Seco Nuclear Generating Station(RSNGS; licensed and undergoing decommissioning pursuant to 10 CFR 50)and the Rancho Seco Independent Spent Fuel Storage Installation (ISFSI;licensed and operated pursuant to 10 CFR 72).2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion IX, Control of Special Processes 2.2 ANSI N45.2-1977, Section 10, Control of Special Processes 2.3 ASME Section V and IX2.4 10 CFR 71.119, Control of Special Processes 2.5 10 CFR 72.158, Control of Special Processes 3.0 POLICYPrior to performing any special processes, procedures shall be established andimplemented to ensure that special processes and equipment are controlled andthat qualified personnel and procedures accomplish required activities.

4.0 GENERAL REQUIREMENTS 4.1 Prior to performing any special processes, procedures shall be preparedto provide for proper control of special processes, which include welding,heat treating, chemical

cleaning, application of protective
coatings, andnondestructive examination (N DE).4.2 Controls shall be established to ensure that only approved materials andequipment are used to perform special processes.

4.3 Personnel who perform special processes shall be qualified in accordance with industry standards.

4.4 Special process requirements shall be prescribed in the controlling specifications,

drawings, procurement documents, or procedures.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 46 OF 775.0 RESPONSIBILITIES General organizational responsibilities are described in Section 1,ORGANIZATION.

5.1 Encilneerinci is responsible for:10a. Specifying the special processes on design documents governing maintenance/modification activities.

b. Developing, qualifying, and maintaining special process procedures in accordance with Step 4.1 of this RSQM section.c. Qualifying personnel or approving contract personnel to performspecial processes identified in Step 4.1 of this RSQM section.d. Performing NDE or approving contract personnel to perform NDE.5.2 Quality Assurance is responsible for:a. Review and concurrence of special process procedures.
b. Auditing the special process program in accordance with RSQMSection XVIII.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 47 OF 77X. INSPECTION 1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established to provide for the inspection of material, parts, andcomponents for the Rancho Seco nuclear facility, which includes the RanchoSeco Nuclear Generating Station (RSNGS; licensed and undergoing decommissioning pursuant to 10 CFR 50) and the Independent Spent FuelStorage Installation (ISFSI; licensed and operated pursuant to 10 CFR 72).2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion X, Inspection 2.2 ANSI N45.2-1971, Section 11, Inspection 2.3 Regulatory Guide 1.58/ANSI N45.2.6-78, Qualification of Nuclear PowerPlant Inspection, Examination and Testing Personnel with exceptions noted in RSQM Section II.2.4 Safety Guide 33/ANSI N18.7, Administrative Controls for Nuclear PowerPlants2.5 10 CER 71.121, Internal Inspection 2.6 10 CFR 72.160, Licensee Inspection 3.0 POLICYProcedures shall be established and implemented to ensure that inspections areperformed to verify compliance with specified requirements at the Rancho Seconuclear facility.

4.0 GENERAL REQUIREMENTS 4.1 Inspections shall be applied to receiving, maintenance, and modification activities to verify that items and activities conform to specified requirements.

4.2 Inspection planning documents shall be prepared or reviewed by QualityAssurance in accordance with established procedures.

Inspection planning documents shall identify the following as applicable:

a. Characteristics and activities to be inspected; RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 48 OF 77b. Inspection organization;

c. Accept/reject criteria;
d. Hold points and/or witness points;e. Inspection Methods;f. Provisions for recording objective evidence of inspection results;andg. Measuring and test equipment of the necessary accuracy forperforming inspection.

4.3 Process monitoring may be used where direct inspection alone isimpractical or inadequate.

Both inspection and process monitoring areperformed when control is inadequate without both.4.4 Training and qualification of personnel, who perform inspections including NDE, shall be performed in accordance with approved procedures.

4.5 Hold points are designated as mandatory inspection points whenconfirmation is needed that the work at the point is acceptable beforeadditional work can proceed.

Authorized personnel perform hold pointinspections and release work for further processing or use.4.6 Inspections, including any required hold points, are performed anddocumented in accordance with written procedures.

Inspection results aredocumented and evaluated by qualified personnel to verify acceptability.

4.7 Quality Assurance personnel perform inspections of receiving, maintenance, and modification activities.

4.8 Inspection records shall contain the following where applicable:

a. Item inspected;
b. The date of the inspection;
c. Inspector or data recorder identification;
d. Identification of M&TE used to perform inspections;
e. Type of observation; RANCHO SECO LICENSING BASIS DOCUMENTTITLE: RANCHO SECO QUALITY MANUALNUMBER: RSLBD-010 REVISION:

2PAGE 49 OF 77f. Results or acceptability; andg. Reference to information on action taken on non-conformances toresolve any discrepancies noted.5.0 RESPONSIBILITIES General organizational responsibilities are described in Section i,ORGANIZATION.

5.1 Quality Assurance is responsible for:a. Qualifying Quality Control Inspectors.

b. Preparing or reviewing inspection-planning documents formodification/maintenance activities.
c. Performing inspections per inspection plans.d. Auditing the inspection program in accordance with RSQM SectionXVIII.5.2 Maintenance is responsible for assuring:

a.b.5.3 Eacha.b.Inspections are performed as required by inspection planning.

Work does not proceed beyond inspector signoffs for hold points.organization is responsible for:Supporting inspection activities.

Providing prompt corrective action to any deficiencies found duringthe inspection.

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2TITLE: PANCHO SECO QUALITY MANUAL PAGE 50 OF 77Xl. TEST CONTROL1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established to provide for acceptance and surveillance test control atthe Rancho Seco nuclear facility, which includes the Rancho Seco NuclearGenerating Station (RSNGS; licensed and undergoing decommissioning pursuant to 10 CFR 50) and the Independent Spent Fuel Storage Installation (ISFSI; licensed and operated pursuant to 10 CFR 72).2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion Xl, Test Control2.2 ANSI N45.2-1971, Section 12, Test Control2.3 Safety Guide 33/ANSI N18.7, Administrative Controls for Nuclear Plants2.4 10 CFR 71.123, Test Control2.5 10 CFR 72.162, Test Control3.0 POLICYProcedures shall be established and implemented to ensure that required testingto demonstrate that structures,

systems, and components will performsatisfactorily in service is identified, performed and documented.

4.0 GENERAL REQUIREMENTS 4.1 Tests shall be performed in accordance with procedures and criteria thatdesignate when tests are required and how they are to be performed.

Such testing includes the following:

a. Qualification tests, as applicable, to verify design adequacy.
b. Tests of equipment and components to ensure their properoperation prior to delivery or pre-operational tests;c. Pre-operational tests to ensure proper and safe operation ofsystems and equipment prior to startup tests or operations; RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 51 OF 77d. Startup tests to ensure proper and safe operation of systems andequipment.

e. Surveillance tests to ensure continuing proper and safe operation ofsystems and equipment.
f. Maintenance tests after preventive or corrective maintenance.

4.2 Test procedures and instructions shall include provisions for the following, as applicable:

a. The requirements and acceptance limits contained in the applicable design and procurement documents;
b. Test prerequisites such as calibrated instrumentation, required testequipment, degree of completeness of the item to be tested,suitable and controlled environmental conditions, and provisions fordata collection and storage;c. Verifying that test prerequisites have been met;d. Instructions for performing the test;e. Any inspection points;f. Acceptance criteria;
g. Documenting or recording test data and results; andh. Verification of completion.

4.3 Test procedures and instructions shall be reviewed by the applicable organizations for technical content.4.4 Test results shall be documented and evaluated by responsible authorities to ensure that test requirements have been satisfied.

4.5 Test records shall contain the following information where applicable:

a. Item tested and type of observation;
b. The date and results of the test;c. Information related to deviations or non-conformances; RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 52 OF 77d. Identification of person recording the data;e. Evidence as to the acceptability of the results; andf. Action taken to resolve any deviations and non-conformances noted.5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I,ORGAN IZATION.5.1 Quality Assurance is responsible for auditing the test control program perRSQM Section XVIII.5.2 Engineering is responsible for:a. Establishing the procedure for acceptance and surveillance testing.b. Providing personnel to perform the testing and acceptance evaluations.

)

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 53 OF 77XlI. CONTROL OF MEASURING AND TEST EQUIPMENT 1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established to provide for the control of measuring and test equipment at the Rancho Seco nuclear facility, which includes the Rancho Seco NuclearGenerating Station (RSNGS; licensed and undergoing decommissioning pursuant to 10 CFR 50) and the Independent Spent Fuel Storage Installation (ISFSI; licensed and operated pursuant to 10 CFR 72).2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XII, Control of Measuring and TestEquipment 2.2 ANSI N45.2-1971, Section 13, Control of Measuring and Test Equipment 2.3 Safety Guide 33/ANSI N18.7, Administrative Controls for Nuclear PowerPlants.2.4 Regulatory Guide 1.30/ANSI N45.2.4-72, Quality Assurance Requirements for the Installation, Inspection, and Testing ofInstrumentation and Electric Equipment with exception noted in Section IIof this manual.2.5 10 CFR 71.125, Control of Measuring and Test Equipment 2.6 10 CFR 72.164, Control of Measuring and Test Equipment 3.0 POLICYProcedures shall be established and implemented to ensure that measuring andtesting devices used in final acceptance of activities affecting quality are properly~controlled, calibrated, and adjusted at specified intervals to maintain the desiredaccuracy.

4.0 GENERAL REQUIREMENTS 4.1 Procedures shall be established for calibration, maintenance, and controlof measuring and test equipment utilized in the operation, measurement, inspection, or monitoring of items.4.2 Measuring and Test Equipment (M&TE) shall be calibrated at specified intervals.

These intervals are based on the amount of use, stability,

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 54 OF 77characteristics and other conditions that could adversely affect therequired measurement accuracy.

Reference and secondary calibration standards shall be traceable to nationally recognized standards wherethey exist. Where national standards do not exist, provisions shall beestablished to document the basis for calibration.

4.3 M&TE used for calibrating plant process instrumentation (PI) shall havecalibration ranges, precessions, and accuracy's such that the PI can becalibrated from M&TE with an accuracy ratio of at least two-to-one (M&TEto PI). Calibration accuracy ratios of less than two but equal to or betterthan one shall be acceptable when equipment to meet specified requirements is not commercially available.

The basis of acceptance inthese cases shall be documented.

5.0 RESPONSIBILITIES

General organizational responsibilities are described in Section I,ORGANIZATION.

5.1 Maintenance is responsible for:a. Establishing methods for control of measuring and test equipment.

b. Determining the need for calibrated instruments and measuring devices in Rancho Seco nuclear facility activities.
c. Providing administrative procedures that address the requirements for calibration.
d. Control of measurement devices to ensure their use and accuracy.

5.2 Quality Assurance is responsible for auditing the control of measuring andtest equipment program per RSQM Section XVIII.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 55 OF 77XIII. HANDLING,

STORAGE, AND SHIPPING1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established to provide for the handling,
storage, shipping,
cleaning, and preservation of material and equipment at the Rancho Seco nuclear facility, which includes the Rancho Seco Nuclear Generating Station (RSNGS; licensedand undergoing decommissioning pursuant to 10 CFR 50) and the Independent Spent Fuel Storage Installation (ISFSI; licensed and operated pursuant to 10CFR 72).2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XIII, Handling,
Storage, and Shipping2.2 ANSI N45.2-1 971, Section 14, Handling,
Storage, and Shipping2.3 Regulatory Guide 1.38/ANSI N45.2.2-1 972, Packaging,
Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants withexceptions noted in Section II of this manual.2.4 10 CFR 71.127, Handling,
Storage, and Shipping2.5 10 CFR 72.166, Handling,
Storage, and Shipping3.0 POLICYProcedures shall be established and implemented to ensure that materials andequipment are properly
handled, stored, shipped,
cleaned, and preserved toprevent damage or deterioration.

4.0 GENERAL REQUIREMENTS 4.1 Procedures shall be established for assuring that proper handling,

storage, shipping, and preservation instructions are included in applicable drawings and/or specifications.

4.2 When required for specific items, special protective environments, such asinert gas atmosphere, specific moisture content levels, and temperature levels, shall be specified.

4.3 A shelf life program shall be in effect and monitored to prevent usage afterthe expiration date without re-certification for extension of shelf life.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 56 OF 774.4 Special material handling and preservation instructions shall be developed when required by applicable drawings and/or specifications.

4.5 Materials used for packaging,

shipment, and, storage of items that havethe potential for causing contamination or radiation exposure requiremarking and labeling to indicate the need for special radiological controls.

5.0 RESPONSIBILITIES

General organizational responsibilities are described in Section I,ORGANIZATION.

5.1 Engineering is responsible for establishing methods and procedures toensure that applicable drawings and/or specifications include handling,

storage, shipping, and preservation requirements.

5.2 Maintenance is responsible for:a. Establishing methods for special handling,

storage, andpreservation during maintenance activities.
b. Providing administrative procedures that specify the requiredcontrols.

5.3 Quality Assurance is responsible for auditing conformance to the handling,

storage, and shipping program per RSQM Section XVIII.5.4 General Services is responsible for maintaining material and warehousing control of items and equipment that require special handling and storage.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 57 OF 77XlV. INSPECTION, TEST, AND OPERATING STATUS1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established to provide for a system to identify the inspection, test, andoperating status of individual items at the Rancho Seco nuclear facility, whichincludes the Rancho Seco Nuclear Generating Station (RSNGS; licensed andundergoing decommissioning pursuant to 10 CFR 50) and the Independent Spent Fuel Storage Installation (ISFSI; licensed and operated pursuant to 10CFR 72).2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XIV, Inspection, Test and Operating Status2.2 ANSI N45.2-1 971, Section 15, Inspection, Test, and Operating Status2.3 10 CFR 71.129, Inspection, Test and Operating Status2.4 10 CFR 72.168, Inspection, Test and Operating Status3.0 POLICYProcedures shall be established and implemented to ensure that measures.

areprovided to indicate the status of inspections, tests, and operations.

4.0 GENERAL REQUIREMENTS 4.1 Procedures shall specify the degree of control required for the indication ofinspection and test status of items required for modification activities.

4.2 The sequence of inspections, tests, and other operations, and changesthereto, shall be controlled by procedures.

4.3 Procedures shall provide methods for identifying the nonconforming items,inoperable systems and components by tags, markings, labels, etc. toprevent inadvertent use.5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I,ORGANIZATION.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 58 OF 775.1 Maintenance is responsible for Clearance Program procedures to ensure:a. Safety of personnel and equipment during maintenance and testingactivities.

b. Installation and removal of test and operating status indicators.

5.2 Quality Assurance is responsible for:a. Identifying the quality status of applicable

material, parts, andcomponents.
b. Auditing the inspection, test, and operating status program perRSQM Section XVIII.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 59 OF 77XV. NONCONFORMING MATERIALS, PARTS, OR COMPONENTS 1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established for controlling

material, components, parts, or systems thatare not in conformance to specified requirements at the Rancho Seco nuclearfacility, which includes the Rancho Seco Nuclear Generating Station (RSNGS;licensed and undergoing decommissioning pursuant to 10 CFR 50) and theIndependent Spent Fuel Storage Installation (ISFSI; licensed and operatedpursuant to 10 CFR 72).2.0 REFERENCED DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XV, Nonconforming Materials, Parts orComponents 2.2 ANSI N45.2-1 971, Section 16, Nonconforming Items2.3 10 CFR 71.131, Nonconforming Materials, Parts or Components 2.4 10 CFR 72.170, Nonconforming Materials, Parts or Components 3.0 POLICYProcedures shall be established and implemented to ensure that materials, parts,or components that do not conform to specified requirements are controlled toprevent their inadvertent use or installation.

4.0 GENERAL REQUIREMENTS 4.1 Procedures shall be developed for controlling, documenting, and resolving items, services, or activities identified as nonconforming.

4.2 Marking,

tagging, segregating, or other means shall identifynonconforming items.4.3 Non-conformances shall be documented, processed, controlled andretained to provide records of the actions taken to resolve thenonconforming condition.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 60 OF 775.0 RESPONSIBILITIES General organizational responsibilities are described in Section I,ORGANIZATION.

5.1 Quality Assurance is responsible for:a. Reviewing identified conditions that are adverse to quality and thecorrective action associated with those conditions.

(Refer to RSQMSection XVI regarding corrective action program)b. Establishing methods for controlling and documenting non-conformances.

c. Ensuring expertise is available to disposition non-conformances.
d. Developing safety analyses that address the nonconforming condition, if required.
a. Auditing the nonconforming materials, parts, or components program per RSQM Section XVIII.5.2 Rancho Seco management is responsible for:a. Taking appropriate action to ensure operation of the plant inconformance to license requirements when a nonconformance identifies a condition prohibiting components, structures, or,systems from returning to an acceptable condition.
b. Determining the safety significance of the nonconforming condition on the status of the plant.c. Reviewing identified conditions that are adverse to quality and thecorrective action associated with those conditions.
d. Ensuring expertise is available to disposition non-conformances.
e. Developing safety analyses that address the nonconforming condition, if required.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 61 OF 77XVI. CORRECTIVE ACTION1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established to provide for a corrective action program to ensure thatconditions adverse to quality are promptly identified and corrected at the RanchoSeco nuclear facility, which includes the Rancho Seco Nuclear Generating Station (RSNGS; licensed and undergoing decommissioning pursuant to 10 CFR50) and the Independent Spent Fuel Storage Installation (ISFSI; licensed andoperated pursuant to 10 CFR 72).2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XVI, Corrective Action2.2 10 CFR 72, Subpart D, Records,

Reports, Inspections, and Enforcement.

2.3 ANSI N45.2-1 971, Section 17, Corrective Action2.4 10 CFR 71.133, Corrective Action2.5 10 CFR 72.172, Corrective Action3.0 POLICYProcedures shall be established and implemented to ensure that significant conditions adverse to quality are identified and that corrective action is taken topreclude repetition.

4.0 GENERAL REQUIREMENTS 4.1 Controls shall ensure conditions adverse to quality such as malfunctions, errors, deficiencies or non-conformances are identified, documented andappropriate corrective action taken. The controls shall ensure that thecorrective action is- implemented in a timely manner.4.2 For significant conditions adverse to quality, corrective action includesdetermining the cause and extent of the condition, taking corrective actionto remedy the condition and taking action to prevent recurrence.

Theseactions shall be reported to management personnel for review andassessment.

5.0 RESPONSIBILITIES RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 62 OF 77General organizational responsibilities are described in Section I,ORGANIZATION.

5.1 Rancho Seco management is responsible for:a. Formulating appropriate corrective actions.b. Implementing proposed corrective actions.c. Ensuring that proposed corrective action is effective.

5.2 Quality Assurance is responsible for:a. Auditing the Corrective Action Program per RSQM Section XVIII.

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 63 OF 77XVII. QUALITY ASSURANCE RECORDS1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established for the storage and maintenance of Quality Assurance Records that provide the documentary evidence of activities affecting qualityperformed at the Rancho Seco nuclear facility, which includes the Rancho SecoNuclear Generating Station (RSNGS; licensed and undergoing decommissioning pursuant to 10 CFR 50) and the Independent Spent Fuel Storage Installation (ISFSI; licensed and operated pursuant to 10 CFR 72).2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XVII, Quality Assurance Records2.2 ANSI N45.2-1 971, Section 18, Quality Assurance Records2.3 Safety Guide 33/ANSI N 18.7, Administrative Control for Nuclear PowerPlants, paragraph 5.22.4 Regulatory Guide 1.28/ANSI/ASME, NQA-1-1 983, Supplement 17S-1,Supplementary Requirements for Quality Assurance

Records, withexceptions as noted in RSQM Section II, Attachment 11-3.2.5 Rancho Seco Quality Manual, Appendix A2.6 10 CFR 71.135, Quality Assurance Records2.7 10 CFR 72.174, Quality Assurance Records3.0 POLICYProcedures shall be established and implemented to ensure storage andmaintenance of records that represent evidence of activities described in RSQMSection II, Step 4.4.4.0 GENERAL REQUIREMENTS 4.1 Quality Assurance records shall be permanently stored in a facility thatmeets the requirements of Reference 2.4 and 2.5.4.2 Quality Assurance records shall be protected during interim storage inaccordance with Reference 2.4.

RANCHO SECO LICENSINGi BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 64 OF 774.3 Documents that furnish evidence of the quality of items and services aregenerated and controlled in accordance with the procedures that governthose activities.

Such documents are considered Quality Assurance Records upon completion.

Quality Assurance Records are considered completed when they have been stamped, initialed, or signed and datedby authorized personnel or otherwise authenticated.

4.4 The record system shall provide for identification and retrievability of therecords to the extent that information can be obtained in a reasonable amount of time.4.5 The records program shall address records classification (retention period),

storage location and responsibility for retention and retrievability.

4.6 A records retention schedule shall be established which addresses therequirements in References 2.4 and 2.5.5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I,ORGAN IZATION5.1 Records Management is responsible for:a. Establishing methods for control of records.b. Providing administrative procedures that define the records storageprogram and provide for ready retrievability.

5.2 Rancho Seco management is responsible for:a. Transmitting completed records to Records Management.

b. Providing interim storage in accordance with Step 4.2 above andReference 2.4, prior to transmittal to Records Management.

5.3 Quality Assurance is responsible for auditing the records management system to ensure conformance to specified requirements per RSQMSection XVIII.

RANCHO SLECO LIUNI=N~NL UU)CUMINNI NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 65 OF 77XVIII. AUDITS1.0 PURPOSEDescribe the Rancho Seco Quality Assurance Program (QAP) measures that (1)establish a comprehensive system of planned and periodic audits, and (2)determine the effectiveness of the QAP at the Rancho Seco nuclear facility, which includes the Rancho Seco Nuclear Generating Station (RSNGS) licensedunder 10 CFR Part 50 and the Independent Spent Fuel Storage Installation (ISFSI) licensed under 10 CFR Part 72.2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XVIII, Audits2.2 Safety Guide 33/ANSI N18.7, Administrative Controls for Nuclear PowerPlants2.3 Regulatory Guide 1.144/ANSI N45.2.1 2-1977, Requirements for Auditing ofQuality Assurance Programs for Nuclear Power Plants2.4 Regulatory Guide 1.146/ANSI N45.2.23-1978, Qualification of QualityAssurance Program Audit Personnel for Nuclear Power Plants2.5 10 CFR 50.54(a),

Conditions of Licenses2.6 10 CFR 71.137, Audits2.7 10 CFR 72.176, Audits3.0 POLICYProcedures shall be established and implemented to ensure that planned andperiodic audits are conducted to verify compliance with all aspects of the QAP.4.0 GENERAL REQUIREMENTS 4.1 Quality Assurance shall establish a schedule for auditing the activities affecting quality.

The audit schedule shall be consistent with the auditrequirements and frequencies specified herein.4.2 The audit program shall be described in procedures that implement thisRSQM section.

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 66 OF 774.3 Audits shall be conducted to determine the adequacy and effectiveness ofprograms implemented for the design, procurement, modification, maintenance, and operational activities at the Rancho Seco nuclearfacility.

4.4 Audit plans shall be developed that identify the audit scope, therequirements, activities to be audited, organizations to be notified, theapplicable documents, and the audit schedule.

4.5 Audit reports shall be issued which identify the activity that was audited,the personnel that were contacted during the audit, and any conditions adverse to quality noted during the audit.4.6 Process conditions identified as adverse to quality using the Rancho SecoCorrective Action Program.4.7 Personnel conducting audits shall be trained and qualified in accordance with Reference 2.4. In addition, at least one individual participating in theSecurity audit will be knowledgeable and practiced in the accessauthorization program performance objectives.

4.8 Regularly scheduled audits shall be supplemented by specialaudits/surveillances when conditions that warrant special audits exist orwhen requested by SMUD management.

5.0 RESPONSIBILITIES

General organizational responsibilities are described in Section I,ORGANIZATION.

5.1 Quality Assurance is responsible for:a. Establishing a schedule for performance of required audits.b. Reviewing audit results to evaluate the effectiveness of the QAP.c. Implementation of the established audit program.d. Training and qualification of audit personnel.

5.2 SMUD management is responsible for:a. Supporting the audit activities.

1KANI2HO SECGO LIULNI-NU5NL VUGUMNI--

NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 67 OF 77b. Providing prompt response to any deviations from quality identified in the audit.6.0 AUDITS AND AUDIT FREQUENCIES 6.1 Audits of Rancho Seco nuclear facility activities shall be performed underthe cognizance of the Quality Assurance organization which reports to theDirector, Audit Services (AS). The required audits and audit performance frequencies are as follows:a. Conformance to the Rancho Seco nuclear facility Technical Specifications and associated license conditions at least once peryear;b. Performance and qualifications of the Rancho Seco nuclear facilitytechnical staff at least once every two years;c. Actions taken to correct deficiencies occurring in facility structures,

systems, components, or methods of operation associated with thesafe operation of the Rancho Seco Independent Spent Fuel StorageInstallation (ISFSI) at least once every two years for those deficiencies not previously audited (Corrective Action Program audit);d. Performance of activities required by the QAP to meet the 10 CFR 50,Appendix B criteria at least once every five years;e. Rancho Seco nuclear facility Emergency Plan and implementing procedures at least once every two years;f. 10 CFR 72 ISFSI Physical Protection Plan and implementing procedures at least once every two years;g. Other areas of Rancho Seco nuclear facility operation that the siteManager considers appropriate;
h. Compliance with fire protection requirements and implementing procedures at least once every two years;i. Radiological Environmental Monitoring Program (REMP) and theresults thereof at least once every two years;j. Off-site Dose Calculation Manual (ODCM) and implementing procedures at least once every two years; RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 68 OF 77k. Process Control Program (PCP) and implementing procedures forprocessing and packaging of radioactive wastes from liquid systems atleast once every two years;I.Performance of activities required by the Quality Assurance Programfor Effluent Control and Environmental Monitoring (Regulatory Guide4.15) at least once every two years; andm. Radiation Protection Program content and implementation once peryear.6.2 Changes to these audits and audit frequencies are subject to the requirements contained in 10 CFR 50.54(a).

In addition, frequencies specified in 10 CFR andrelated to the performance of specific audits may not be changed unless anexemption or waiver is obtained from the NRC.6.3 The audit reports resulting from items "a" through "in" above shall be forwarded to the site Manager, the Director, Power Generation, and the management positions responsible for the areas reviewed.

The report should be issued within30 days after completion.

RANCHO SECO LICENSiIN(G WASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: PANCHO SECO QUALITY MANUAL PAGE 69 OF 77Appendix A1.0 10 CFR 50 ADMINISTRATIVE CONTROLS1.1 Technical Review and Controla. Procedures, plans, manuals, and programs required by Section 1.4 shall beprepared,

reviewed, and approved.

Each such procedure, plan, manual, andprogram or change thereto shall be reviewed by an individual(s) other than thepreparer, but who may be from the same organization as the preparer of theprocedure, plan, manual and program or change thereto.

Programs, plans,manuals, and procedures other than administrative procedures will beapproved as delineated in writing by the Site Manager, but not lower than adirect report to the Site Manager.

Such procedures, plans, manuals andprograms shall be reviewed periodically in accordance with administrative procedures.

The Site Manager will approve administrative procedures and Emergency PlanImplementing Procedures.

b. Proposed changes or modifications to systems or equipment described in theRADSAR shall be reviewed by an individual(s) other than the individual(s) whodesigned the modification, but who may be from the same organization as theindividual(s) who designed the modifications.

Such modifications shall beapproved by the Site Manager or his designee as delineated in writing, but notlower than a direct report to the Site Manager.c. Individual(s),

other than the individual(s) who prepare proposed tests orexperiments shall review proposed tests and experiments that are notaddressed in the RADSAR. Such tests or experiments shall be approved bythe Site Manager or his designee as delineated in writing, but not lower than adirect report to the Site Manager.d. Individuals responsible for reviews performed in accordance with Section 1.1 a,b, and c shall meet or exceed the qualification requirements of Section 4,"Qualifications,"

of ANSI N 18.1-1971, excluding Sections 4.5.2 "Technicians" and 4.5.3 "Repairmen."

The Site Manager shall establish the list of qualified reviewers for the independent reviews described in a, b, and c above.e. Events reportable pursuant to Section 1.5.5 and violations of Technical Specifications shall be investigated and a report prepared which evaluates theevent and which provides recommendations to prevent recurrence.

The SiteManager shall review these reports.

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 70 OF 771.2 Audits (See RSQM Section XVIIl)Specific audit requirements, including frequencies and administrative

controls, are addressed in Rancho Seco Quality Manual (RSQM)Section XVIII, "Audits."

1.3 Licensee Event Report ActionThe following actions shall be taken for events that are reportable as LicenseeEvent Reports:a. The Commission shall be notified and a report submitted per Section 1.5.5,pursuant to the requirements of 10 CFR 20.2203 and 50.73, andb. Each Licensee Event Report shall be reviewed and approved by the SiteManager or designee.

1.4 Procedures, Plans, Manuals, and Programs1.4.1 Written procedures, plans, manuals, and programs shall be established, implemented and maintained 1 covering the activities referenced below:a. The applicable procedures recommended in Appendix "A" of SafetyGuide 33, November 1972.b. Emergency Plan implementation.

c. Fire Protection Program Plan implementation.

-d. POP implementation.

e. ODCM implementation.
f. REMP MANUAL implementation.
g. Quality Assurance Program for Effluent Control and Environmental Monitoring using the guidance of Regulatory Guide 4.15, Revision 1,February 1979.h. Quality Assurance Program implementation.
g. Radiation Protection Program implementation.

1 Note: These procedures, plans, manuals, and programs may coexist within a single document.

RANCHO SECO LICENSING3 BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 71 OF 771.4.2 Each procedure, plan, manual, and program of Section 1.4.1 above andchanges thereto shall be reviewed and approved as set forth in Section1.1.1.4.3 The following programs shall be established, implemented, andmaintained:

1.4.3.1 Radioactive Effluent Controls ProaramThere are no longer any radioactive liquid or gaseous effluents discharged from the site. The Offsite Dose Calculation Manual(ODOM) has been reduced in scope and the associated administrative and implementing procedures have been deleted.

TheODCM will require that if radioactive effluents need to be released inthe future, a program must be implemented that meets therequirements in 10 CFR 50.36a, 20.1301, 20.1302, 10 CFR Part 50,Appendix I, and any other applicable regulations 1.4.3.2 Radioloqical Environmental Monitoringq Progqram (REMP)There are no longer any liquid or gaseous radioactive effluents discharged from the site. The radiation source term is limited toradioactive materials stored in the Interim Onsite Storage Building(IOSB) and the Independent Spent Fuel Storage Installation (ISFSI).Accordingly, the only exposure pathway is by direct radiation.

With the completion of the first phase of decommissioning, the directradiation pathway is the only pathway still monitored by the REMP.Accordingly, there is no longer any requirement to participate in anInter-laboratory Comparison Program (ICP). The vendor supplying the direct radiation monitoring devices must be certified under aNational Voluntary Laboratory Accreditation Program (NVLAP).

TheNational Institute of Standards and Technology (NI1ST) administers the NVLAP, which provides third-party accreditation to testing andcalibration laboratories.

1.4.4 The changes to the REMP shall be reviewed and approved as set forthin Sections 1.1 and 1.9.

RANCHO SECO LICEN;51NU L3A$IS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: PANCHO SECO QUALITY MANUAL PAGE 72 OF 771.5 Reporting Requirements 1.5.1 Routine ReportsIn addition to the applicable reporting requirements of Title 10, Code ofFederal Regulations, the following reports shall be submitted to the RegionalAdministrator of the Region IV Office unless otherwise noted.1.5.2 Annual Radiological ReportsAnnual reports covering the activities of the unit, as described below, for theprevious calendar year shall be submitted as follows:1.5.2.1 Annual Individual Monitoring Results ReportThe Annual Individual Monitoring Results Report for the previous calendaryear shall be submitted to the Commission by April 30 of each year incompliance with 10 CFR 20.2206.1.5.2.2 Annual Exposure ReportThe Annual Exposure Report for the previous calendar year shall besubmitted to the Commission within the first calendar quarter of eachcalendar year in accordance with the guidance contained in Regulatory Guide 1.16.1.5.2.3 Annual Radioloqical Environmental Operating ReportThe Annual Radiological Environmental Operating Report covering theoperation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The materialprovided shall be consistent with the objectives outlined in the REMPManual.1.5.3 Annual Radioactive Effluent Release ReportAlthough there are no longer any radioactive effluents discharged from thesite, the Annual Radioactive Effluent Release Report, covering the operation of the unit during the previous 12 months, shall be submitted within 90 daysafter January 1 of each year. The report will continue to be submitted until theNRC grants a specific exemption from 10 CFR 50.36a.

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 73 OF 771.5.4 Biennial ReportA routine report consisting of shutdown statistics, narrative summary ofshutdown experience, and tabulations of facility

changes, tests or, experiments required pursuant to 10 CFR 50.59(d) shall be submitted at intervals not toexceed 24 months to the U. S. Nuclear Regulatory Commission, DocumentControl Desk, Washington, D.C. 20555, with a copy to the Regional Office,postmarked no later than 30 days following the 24 month period covered by thereport.1.5.5 Licensee Event ReportThe types of events listed in 10 CFR 20.2203 and 50.73 shall be the subjectof Licensee Event Reports, submitted to the U.S. Nuclear Regulatory Commission (NRC), Document Control Desk, Washington, D.C. 20555, withinthe time requirements of 10 CFR 20.2203 and 50.73. An additional copy shallalso be submitted to the Regional Administrator of the Region IV Officel.

Thewritten report shall include a completed copy of a Licensee Event Reportform, pursuant to 10 CFR 20.2203, 50.73 and the guidance of NUREG-1022, and a description of corrective actions and measures to prevent recurrence.

Supplemental reports may be required to fully describe final resolution of theoccurrence.

For corrected or supplemental

reports, a Licensee Event Reportshall be completed and reference shall be made to the original report date,pursuant to the requirements of 10 CFR 20.2203 or 50.73, as appropriate.

1.5.6 Environmental Reportsa. When a change to the plant design or operation is planned which wouldhave a significant adverse effect on the environment or which involvesan environmental matter or question not previously reviewed andevaluated by the NRC, a report on the change will be made to the NRCprior to implementation.

The report will include a description andevaluation of the change, including a supporting benefit-cost analysis.

b. Changes or additions to permits and certificates required by Federal,State, local and regional authorities for the protection of the environment will be reported.

The request for permit and certificate changes oradditions submitted to the concerned agencies for approval will also besubmitted to the NRC. The submittal will be made for the reporting period during which the changes or additions occurred.

The submittal willinclude an evaluation of the environmental impact of the change(s).

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 74 OF 771.5.7 Special ReportsSpecial reports shall be submitted to the Regional Administrator of theRegion IV Office within the time period specified for each report.1.6 Record Retention 1.6.1 The following records shall be retained for the duration of the 10 CFR Part 50and 10 CFR Part 72 Operating Licenses:

a. Records and logs of facility operation covering time interval at eachpower level.b. Records and logs of principal maintenance activities, inspections, repair,and replacement of principal items of equipment related to NUCLEARSAFETY, as they relate to the 10 CFR Part 72 licensed facility.
c. Licensee Event Reports.d. Records of surveillance activities, inspections and calibrations requiredby these Technical Specifications.
e. Records of changes made to Operating Procedures, as they relate to the10 CFR Part 72 licensed facility.
f. Records of radioactive shipments.
g. Records of sealed source leak tests and results.h. Records of annual physical inventory of all sealed source materialof record.i. Records and logs of facility activities in the Permanently Defueled Mode.j. Record and drawing changes reflecting facility design modifications made to systems and equipment described in the Updated SafetyAnalysis Report.k. Records of new and irradiated fuel inventory, fuel transfers andassembly burn-up histories.

I. Records of facility radiation and contamination surveys.m. Records of radiation exposure for all individuals entering radiation control areas.

RANCHO SECO LICENSING~

BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 75 OF 77n. Records of gaseous and liquid radioactive material released to theenvirons.

o. Records of training and qualification for current members of theoperating staff.p. Records of quality assurance activities required by the RSQM.q. Records of reviews performed for changes made to procedures orequipment or reviews of tests and experiments pursuant to10 CFR 50.59 and 10 CFR 72.48.r. Records of meetings of the Plant Review committee (PRC) andManagement Safety Review Committee (MSRC).s. Records for the Radiological Environmental Monitoring Program.t. Records of reviews performed for changes made to the ODCM, REMPMANUAL, and the PCP.u. Records of plant closure and decommissioning activities performed.

1.7 Radiation Protection ProgramProcedures for personnel radiation protection shall be prepared consistent with therequirements of 10 CFR 19 and 10 CFR 20, and shall be approved, maintained andadhered to for all operations involving personnel radiation exposure.

1.8 Process Control Program (PCP)Licensee-initiated changes to the POP:a.Shall be documented and records of reviews performed shall be retained asrequired by Section 1.6.1.t.

This documentation shall contain:

.. ...1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and2) A determination that the change will maintain the overall conformance ofthe processed waste product to existing requirements of Federal, State, orother applicable regulations.

I b.Shall become effective after approval by the Site Manager.

RANCHO SECU LlICNI-N5N(i LVUUMPN I NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 76 OF 771.9 Off-Site Dose Calculation and Radiological Environmental Monitoring Program ManualsLicensee-initiated changes to the ODCM or REMP Manual: shall be documented and records of reviews performed shall be retained as required by Section1.6.1 .t. This documentation shall contain sufficient information to support thechange together with the appropriate analyses or evaluations justifying thechange.Changes to the REMP become effective after approval by the Site Manager andwill be submitted to the Commission in the form of a complete, legible copy of theentire manual.1.10 Liquid Hold-up TanksThere are no longer any liquid hold-up tanks. Accordingly, this section has beendeleted.1.11 Sealed Source Contamination Each sealed source containing radioactive material either in excess of100 microcuries of beta and/or gamma emitting material or 5 microcuries of alphaemitting material shall be free of_> 0.005 microcuries of removable contamination.

Applicability:

At All TimesAction:With a sealed source having removable contamination in excess of the abovelimits, immediately withdraw the sealed source from use and:a. Either decontaminate and repair the sealed source, orb. -Dispose of the sealed source-in accordance with NRC Regulations.

Surveillance Requirements:

Test Requirements Each sealed source shall be tested for leakage and/or contamination by:a. The Licensee, orb. Other persons specifically authorized by the NRC or an Agreement State.

KANUHU. SI-W VU()UML-N I NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 77 OF 77The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.Test Freqiuencies Each category of sealed sources shall be tested at the frequency described below.a. For sources in use at least once every six months or all sealed sourcescontaining radioactive material:

1. With a half-life greater than 30 days (excluding Tritium),

and2. In any form other than gas.b. For stored sources not in use each sealed source shall be tested prior touse or transfer to another licensee unless tested within the previous sixmonths. Sealed sources transferred without a certificate indicating the lasttest date shall be tested prior to being placed into use.

Powering forward.

Together.

  • SM UD.. ....r i. ..January 7, 2016DPG 16-002U.S. NRC Regulatory Commission Attn: Document Control DeskWashington, DC 20555Docket 50-312Rancho Seco Nuclear Generating StationLicense DPR-54Docket 72-11Rancho Seco Independent Spent Fuel Storage Installation License SNM-2510REPORT OF CHANGES TO THE RANCHO SECO QUALITY ASSURANCE PROGRAM THAT DO NOT REQUIRE PRIOR NRC APPROVALAttention:

Jack Parrott and Chris AllenIn accordance with 10 CFR 50.54(a)(3) and 10 CFR 50.4(b)(7),

we are required tosubmit a copy of changes to the Rancho Seco Quality Manual (RSQM) that do notreduce commitments in the quality assurance program previously accepted by theNRC. Changes to the quality program that do not reduce commitments in theprogram can be made without prior NRC approval.

During calendar year 2015, we revised the RSQM to reflect changes to thecorporate organization.

Specific portions of the RSQM that were revised include:1.2.3.4.5.Quality Assurance PolicyRSQM Chapter I "Organization" RSQM Chapter II "Quality Assurance Program"RSQM Chapter XVIII "Audits"Appendix A "10 CFR 50 Administrative Controls" The safety evaluation associated with these changes concluded that these changesdid not reduce any commitments and did not require prior NRC approval.

The RSQMcontinues to implement the requirements of 10 CFR Part 50, Appendix B and 10CFR Part 72, Subpart G. The individuals and organizations performing qualityassurance functions continue to have sufficient authority, organizational freedom,and independence from cost and schedule issues./¶Rancho Seco Nuclear Generating Station I14440 Twin Cities Road I Herald, GA 95638-9799 I 916.452.3211 Ismud.org DPG 16-002The document is being provided in its entirety because it does not include a List ofEffective Pages. However, changes are indicated by "revision bars" in the leftmargin to aid in review.If you or members of your staff have any questions requiring additional information or clarification, please contact me at (916) 732-4817.

Sincerely,

.Einar T. Ronningen

Manager, Rancho Seco Assets(RJIDTIBG)

Enclosures

-(1) Rancho Seco Quality Manual, RSLBD-01O Rev.2Cc: NRC, Region IV2 RANCHO SECO LICENSING BASIS DOCUMENTTITLE: RANCHO SECO QUALITY MANUALIEFFECTIVE DATE: 04/20/2015 NUMBER: RSLBD-010 REVISION:

2PAGE 1 OF 77REASON FOR CHANGE:* Reflect current corporate organization and responsibilities REVISION SUMMARY:* Revised QA policy Statement to Reflect current corporate organization andresponsibilities

  • Revised Section 4.0 of the RSQM to reflect new titles within the organization.

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 2 OF 77QUALITY ASSURANCE POLICYThe Sacramento Municipal Utility District's (SMUD) policy regarding quality assurance at theRancho Seco nuclear facility, which includes the Rancho Seco Nuclear Generating Station(RSNGS; licensed and undergoing decommissioning pursuant to 10 CFR 50) and the RanchoSeco Independent Spent Fuel Storage Installation (ISFSI; licensed and operated pursuant to10 CFR 72), is as follows:I. Organizations involved in QA Class 1 activities and the other Program Activity Areasspecified in Rancho Seco Quality Manual (RSQM)Section II, Attachment Il-1, shall bestructured,

managed, and operated to provide compliance with the RSQM. Procedures shall be prepared that implement the activities required to safely operate the RanchoSeco nuclear facility and achieve the following objectives:
a. Comply with government regulations and established SMUD management
policies, applying a systematic, disciplined, and uniform approach to qualityassurance.
b. Provide facilities
designed, modified, constructed, tested and operated inaccordance with specified requirements with reasonable assurance that failuresor malfunctions will not cause undue risk to public health and safety.c. Ensure prompt identification and resolution of actual and potential problems indesign, procurement, construction,
testing, operations, maintenance, andmodification of the structures,
systems, and components associated with QAClass 1 activities or other applicable Program Activity Areas specified in RSQMSection II, Attachment Il-i.Ill. The RSQM and implementing procedures constitute the Rancho Seco QualityAssurance Program (QAP). The QAP applies to activities, plans, and programsaffecting the operation and the quality of structures,
systems, components, and servicesaddressed in the RSQM. The QAP will be implemented by organizations responsible for achieving and verifying quality assurance.

IV. The Chief Generation and Grid Assets Officer has delegated the responsibility andauthority for developing the QAP to the Director, Power Generation and executing theQAP to the Director, Audit Services.

Any conflicts or questions involving interpretation of the requirements or resulting from the implementation of the QAP must be referred tothe Director, Audit Services.

Chris Moffitt Claire Rogers Frankie McDermott

Director, Power Generation
Director, Audit Services Chief Generation and GridAssets Officer RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 3 OF 77Table of ContentsI. ORGANIZATION 1.0 PURPOSE .................................................................

92.0 REFERENCES

............................................................

93.0 POLICY ....................................................................

94.0 ORGANIZATION AND REQUIREMENTS.............................

105.0 RESPONSIBILITIES

....................................................

11II. QUALITY ASSURANCE PROGRAM1.0 PURPOSE................................................................

1

22.0 REFERENCES

...........................................................

123.0 POLICY...................................................................

124.0 GENERAL REQUIREMENTS...........................................

135.0 RESPONSIBILITIES

....................................................

156.0 ATTACHMENTS.........................................................

15I1-1 Application of Rancho Seco Quality Assurance Program Criteria

........

1611-2 Regulatory Commitments................................................18 11-3 Exceptions

..............................................................

20II1. DESIGN CONTROL1.0 PURPOSE................................................................

2

72.0 REFERENCES

...........................................................

273.0 POLICY...................................................................

274.0 GENERAL REQUIREMENTS...........................................

285.0 RESPONSIBILITIES

....................................................

30 RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 4 OF 77IV. PROCUREMENT DOCUMENT CONTROL1.0 PURPOSE................................................................

3

12.0 REFERENCES

...........................................................

313.0 POLICY...................................................................

314.0 GENERAL REQUIREMENTS.......................................

315.0 RESPONSIBILITIES

....................................................

33V. INSTRUCTIONS, PROCEDURES.

AND DRAWINGS1.0 PURPOSE................................................................

3

52.0 REFERENCES

...........................................................

353=0 POLICY ...................................................................

354.0 GENERAL REQUIREMENTS...........................................

355.0 RESPONSIBILITIES

....................................................

36VI. DOCUMENT CONTROL1.0 PURPOSE.............................................................

3

72.0 REFERENCES

...........................................................

373.0 POLICY...................................................................

374.0 GENERAL REQUIREMENTS...........................................

375.0 RESPONSIBILITIES

....................................................

38 RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 5 OF 77VII. CONTROL OF PURCHASED MATERIAL.

EQUIPMENT.

ANDSERVICES1.0 PURPOSE ...........................................................

3

92.0 REFERENCES

...........................................................

393.0 POLICY...................................................................

394.0 GENERAL REQUIREMENTS

.........................................

395.0 RESPONSIBILITIES

....................................................

41VIII. IDENTIFICATION AND CONTROL OF MATERIALS.

PARTS. &COMPONENTS 1.0 PURPOSE................................................................

4

22.0 REFERENCES

...........................................................

423.0 POLICY...................................................................

424.0 GENERAL REQUIREMENTS...........................................

425.0 RESPONSIBILITIES

....................................................

43IX. CONTROL OF SPECIAL PROCESSES 1.0 PURPOSE...............................................................

4

52.0 REFERENCES

...........................................................

453.0 POLICY...................................................................

454.0 GENERAL REQUIREMENTS...........................................

455.0 RESPONSIBILITIES

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46 RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-01O REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 6 OF 77X. INSPECTION 1.0 PURPOSE................................................................

4

72.0 REFERENCES

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473.0 PO LIC Y .........................

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474.0 GENERAL REQUIREMENTS...........................................

475.0 RESPONSIBILITIES

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49XI. TEST CONTROL1.0 PURPOSE................................................................

5

02.0 REFERENCES

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503.0 POLICY...................................................................

504.0 GENERAL REQUIREMENTS...........................................

505.0 RESPONSIBILITIES

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52XII. CONTROL OF MEASURING AND TEST EQUIPMENT 1.0 PURPOSE................................................................

5

32.0 REFERENCES

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533.0 POLICY...................................................................

534.0 GENERAL REQUIREMENTS...........................................

535.0 RESPONSIBILITIES

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54 RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: PANCHO SECO QUALITY MANUAL PAGE 7 OF 77XIII. HANDLING.

STORAGE.

AND SHIPPING1.0 PU R PO SE ...................

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5

52.0 REFERENCES

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553.0 POLICY...................................................................

554.0 GENERAL REQUIREMENTS...........................................

555.0 RESPONSIBILITIES

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56XIV. INSPECTION.

TEST. AND OPERATING STATUS .1.0 PU R PO SE ...................

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573.0 PO LIC Y .....................

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574.0 GENERAL REQUIREMENTS...........................................

575.0 RESPONSIBILITIES

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58XV. NONCONFORMING MATERIALS.

PARTS. OR COMPONENTS 1.0 PU RPO SE ................................................................

5

92.0 REFERENCES

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593.0 POLICY...................,................................................

594.0 GENERAL REQUIREMENTS...........................................

595.0 RESPONSIBILITIES

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60 RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 8 OF 77XVI. CORRECTIVE ACTION1.0 PU R PO SE ................................................................

6

12.0 REFERENCES

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613.0 POLICY ..............................................................

614.0) GENERAL REQUIREMENTS...........................................

615.0 RESPONSIBILITIES

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62XVII. QUALITY ASSURANCE RECORDS1.0 PURPOSE ................................................................

6

32.0 REFERENCES

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633.0 PO LIC Y .....................

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634.0 GENERAL REQUIREMENTS...........................................

635.0 RESPONSIBILITIES

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64XVIII. AUDITS1.0 PURPOSE ............................................................

6

52.0 REFERENCES

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653.0 PO LIC Y .....................

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654.0 GENERAL REQUIREMENTS...........................................

655.0 RESPONSIBILITIES

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666.0 AUDITS AND AUDIT FREQUENCIES.................................

67Appendix A10 CFR 50 ADMINISTRATIVE CONTROLS

.......................

69 RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 9 OF 77I. ORGANIZATION 1.0 PURPOSEThis section describes the Sacramento Municipal Utility District (SMUD)organization and personnel responsible for establishing, implementing, andverifying the Quality Assurance Program (QAP) at the Rancho Seco nuclearfacility, which includes the Rancho Seco Nuclear Generating Station (RSNGS)licensed under 10 CFR Part 50 and the Rancho Seco Independent Spent FuelStorage Installation (ISFSI) licensed under 10 CFR Part 72.2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion I, Organization 2.2 ANSI N45.2-1 971, Section 3, Organization 2.3 Safety Guide 33/ANSI N18.7, Administrative Controls for Nuclear PowerPlants2.4 Rancho Seco Quality Manual, Appendix A2.5 10 CFR 71.103, Quality Assurance Organization 2.6 10 CFR 72.142, Quality Assurance Organization 3.0 POLICY3.1 The establishment and implementation of the Rancho Seco QAP, which iscomprised of this Rancho Seco Quality Manual (RSQM) and the RSQMimplementing procedures, shall be SMUD's responsibility.

Some QAPfunctions may be delegated to other SMUD approved external organizations, but overall responsibility for the QAP remains with SMUD.3.2 Definitive lines of authority, responsibility, and communication shall beestablished for those organizations involved in the QAP.3.3 Quality Assurance personnel assigned to the Rancho Seco nuclear facilityhave defined responsibilities and organizational freedom to identify problemsthat affect quality; to initiate, recommend, or provide solutions; and to verifyimplementation of solutions.

They have the authority to initiate action to stopunsatisfactory work pending implementation of necessary corrective action tobring the unsatisfactory conditions into conformance.

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 10 OF 773.4 The organizational structure and functional responsibility assignments shallbe such that attainment of program objectives is accomplished by individuals or groups who inspect,

examine, audit or otherwise verify conformance toestablished requirements, and who are independent of the individuals orgroups who performed the original activity.

4.0 ORGANIZATION AND REQUIREMENTS 4.1 The General Manager (GM) through the Chief Generation and Grid AssetsOfficer shall have corporate responsibility for overall safe operation of theRancho Seco nuclear facility and shall take any measures needed to ensureacceptable performance of the staff in providing long term monitoring of theremaining radioactive waste.4.2 The Manager, Rancho Seco Assets reports directly to the Director, PowerGeneration.

The Manager, Rancho Seco Assets ensures that the RanchoSeco nuclear facility is properly staffed and adequately budgeted to staff can safely carry out their responsibilities.

The Manager, Rancho Sec0.Assets also coordinates quality concerns with the Quality Assurance group.The Manager, Rancho Seco Assets is responsible for the safe and reliableoperation of RSNGS, pursuant to 10 CFR Part 50, and the ISFSI, pursuant to10 CER Part 72. The Manager, Rancho Seco Assets has the responsibility and authority to implement the QAP and ensure optimum qualityperformance of the Rancho Seco nuclear facility...

The Manager, Rancho Seco Assets is responsible for the administrative

actions necessary to ensure that the QAP is implemented by the groupsunder his direction.

To this extent, the Manager, Rancho Seco Assets shallmaintain continuing involvement in quality matters and shall assess thescope, status, implementation, and effectiveness of the QAP through thereview of Quality Assurance Audits and Surveillances.

4.3 The Director, Audit Services, through the Principal Quality Engineer, isresponsible for the Rancho Seco nuclear quality assurance program.

TheAudit and Quality Services group is independent from operating pressures orother lines of authority, and ensures an active QAP is implemented at theRancho Seco nuclear facility in accordance with regulatory requirements.

The Audit and Quality Services group has the authority to take any issueconcerning the quality of operations at the Rancho Seco nuclear facility tothe Director, Power Generation.

4.4 The Audit and Quality Services group shall have sufficient authority andorganizational freedom to identify problems that affect quality, recommend RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 11 OF 77solutions, and verify implementation of solutions, as appropriate.

Commensurate with this responsibility is the authority to initiate action to stopunsatisfactory work pending correction of the unsatisfactory condition.

Corporate and on-site organizational responsibilities are described in greaterdetail in Rancho Seco Administrative Procedure RSAP- 0101. Specific dutiesand responsibilities for organizations whose activities affect quality aredescribed in RSQM Sections II through XVIII and Appendix A.The Manager, Rancho Seco Assets advises the Director, Power Generation on matters related to the safety of operations at the Rancho Seco nuclearfacility.

The Manager, Rancho Seco Assets performs safety reviews and providesonsite management oversight of Rancho Seco nuclear facility activities.

The Manager, Rancho Seco Assets is responsible for reviewing all Potential;:

Deviations from Quality (PDQ) to determine if a condition is a Deviation from?:Quality (DQ) and requires determination of the cause, extent, remedialI corrective

actions, and actions to prevent recurrence.

The Manager, RanchoSeco Assets reviews and approves DQ dispositions and assigns corrective I actions identified in DQ dispositions.

The Manager, Rancho Seco Assetsalso determines whether a PDQ is potentially reportable pursuant to 10 CFR21.5.0 GENERAL RESPONSIBILITIES The nuclear organization is involved in the long term monitoring of the Rancho Seco nuclear facility and is responsible for describing and clearly defining theduties and authority of individuals whose work affects quality.

RSAP-01 01 definesthe Rancho Seco nuclear facility organization and the responsibilities associated with each onsite work group. Each work group has the responsibility to ensure thattheir procedures implement QAP requirements.

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD.-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 12 OF 77i1. QUALITY ASSURANCE PROGRAM1.0 PURPOSEThe purpose of this section is to describe the Rancho Seco QualityAssurance Program (QAP) implemented at the Rancho Seco nuclearfacility, which includes the Rancho Seco Nuclear Generating Station(RSNGS; licensed and undergoing decommissioning pursuant to 10 CFR50) and the Rancho Seco Independent Spent Fuel Storage Installation (ISFSI; licensed and operated pursuant to 10 CFR 72).

2.0 REFERENCES

2.1 10 CFR 50, Appendix B, Criterion II, Quality Assurance Program2.2 ANSI N45.2-1971, Section 2, Quality Assurance Program ,2.3 Safety Guide 33/ANSI N18.7, Administrative Controls for NuclearPower Plants2.4 10 CFR 71, Subpart H, Quality Assurance Requirements for Packaging and Transportation of Radioactive Material2.5 10 CFR 72, Subpart G, Quality Assurance Requirements for, theIndependent Storage of Spent Nuclear Fuel2.6 NRC Form 311, Quality Assurance Approval for Radioactive MaterialPackages, Approval No. 04893.0 POLICYThe QAP described herein is designed to ensure compliance with therequirements of 10 CFR 50, Appendix B, "Quality Assurance Criteria forNuclear Power Plants and Fuel Reprocessing Plants" including therequirements of applicable NRC Regulatory Guides and ANSI Standards.

Also, the QAP is designed to fulfill the quality requirements for (1) the useof radioactive material transport packages and (2) the operation of theRancho Seco Independent Spent Fuel Storage Installation (ISFSI) inaccordance with 10 CFR 71.101(f) and 10 CFR 72.140(d),

respectively.

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: PANCHO SECO QUALITY MANUAL PAGE 13 OF 774.0 GENERAL REQUIREMENTS 4.1 This Rancho Seco Quality Manual (RSQM) is organized to present the18 quality criteria in the order they are addressed in 10 CFR 50,Appendix B. The RSQM states the Rancho Seco policy for eachcriterion and describes how controls pertinent to each criterion are to becarried out.4.2 In accordance with 10 CFR 50.54(a),

SMUD submits an annual reportto the Nuclear Regulatory Commission (NRC) regarding RSQMchanges that do not reduce the commitments previously accepted bythe NRC. Also, in accordance with 10 CFR 50.54(a),

SMUD submitsRSQM changes that reduce commitments previously accepted to theNRC for their review and approval prior to implementation.

4.3 The QAP is implemented by organizations responsible for achieving quality and by organizations responsible for verifying quality.4.4 Engineering identifies the Quality Assurance (QA) classification ofstructures,

systenis, and components (SSCs) commensurate to theirimportance to safety.4.5 Quality Assurance classification 1 (QA Class 1) is assigned to SSCsthat are considered safety-related in accordance with 10 CFR 50,Appendix B.4.5.1 The QA Class I assignment includes 10 CFR 72 (ISFSl) and 10CFR 71 (Transportation Package)

SSCs as specified in RSAP-0302.

4.5.2 All 18 elements of the 10 CFR 50, Appendix B quality criteria applyto activities affecting QA Class I SSCs during operation, maintenance,

testing, and modifications.

4.6 Some 10 CFR 50, Appendix B quality criteria apply to non-QA Class 1programs and activities such as radiation protection, emergency preparedness, radioactive waste handling and shipping, fire protection, facility operations, environmental monitoring,

security, training, and 10CFR 71/72 important-to-safety, as indicated in RSQM-Section II,Attachment Il-I.4.6.1 Engineering identifies thel0 CFR 71 and 10 CFR 72 non-QA Class1 SSCs that are important-to-safety in accordance with RSAP-0302.

RANCHO SEWO LIUL;NSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 14 OF 774.6.2 SMUD activities performed under 10 CFR 71 shall be limited toprocurement, maintenance, repair, and use as authorized by theNRC Quality Assurance Program Approval for Radioactive MaterialPackages (NRC Form 311; Approval Number 0489).4.7 Attachment Il-I indicates the minimum QAP criteria that must beapplied to specific Program Activity Areas.4.8 Attachments 11-2 and 11-3 tabulate the NRC regulatory guides and ANSIstandards, with exceptions and applicable revisions, that SMUD iscommitted to meeting as part of its QAP.4.9 Activities associated with the safe operation of the Rancho Seconuclear facility are accomplished under controlled conditions.

Preparations for such activities include confirmation that prerequisites have been met.4.11 Development,

control, and use of computer programs associated-with the design and safe operation of the Rancho Seco nuclear facility aresubject to appropriate controls.

4.12 Training programs shall be established to ensure personnel responsible for performing and verifying activities that affect quality have therequired proficiency and qualifications to perform the assigned tasks.4.13 QAP Policy/Procedures/Instructions:

a. The QAP is documented in written policies, procedures, and .instructions.

The overall policies and general requirements areoutlined in the RSQM. Specific details related to implementation ofthe established QAP policies are contained in Rancho SecoAdministrative Procedures (RSAPs).

Organizations responsible forperforming QAP functions shall prepare additional implementing procedures as necessary.

Quality reviews RSAPs to ensure RSQMrequirements are accomplished in a controlled manner.b. Quality is responsible for RSQM preparation,

issuance, and control.The RSQM, including any changes, supplements, or attachments, isissued and maintained as a controlled document.
c. Quality and the Site Manager shall review and approve proposedRSQM changes.

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 15 OF 774.14 Resolution of Differences:

RSQM requirements take precedence over differing qualityrequirements specified in other work group procedures until Qualityevaluates the issue and determines which requirements must bemodified.

Questions or disputes involving RSQM interpretation or implementation must be referred to Quality for resolution.

4.15 Packaging and Transportation of Radioactive Material:

The QAP shall be applied to packaging and transportation ofradioactive material as specified in References 2.4 and 2.6.5.0 RESPONSIBILITIES General organizational responsibilities are described in RSQM Section I,ORGANIZATION

6.0 ATTACHMENTS

Il-I, Application of Rancho Seco Quality Assurance Program Criteria11-2, Regulatory Commitments 11-3, Exceptions RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 16 OF 77(A)(B)(C)Attachment I1-1 (Page 1 of 2)APPLICATION OF RANCHO SECO QUALITY ASSURANCE PROGRAM (QAP) CRITERIA (A, B, C)An 'X' means application of the RSQM requirements associated with the QAP Criteria is required.

No 'X' means application of the RSQM requirements associated with the QAP Criteria is optional.

RSQM implementing details are provided in the RSAPs and other QAP implementing procedures._______

QAP'CRITERIA

ProgramActivity Areas_____

__efrn s4,I I_1 Ill IV V VIl VIIJ VIIIl IX X Xl_ XIIl XIIIl XIV XV XV. I XVII XVIII References Safety Related / 10 CFR 71/72 ISFSI TS 5.4.1kImportant-to-Safety, Category A X X X X X X X X X X X X X X X X X X RSQM, APP. A,(QA Class 1) 10 CFR 50, APP. B______________________

____ ____RSAP-0302, Alr. 6Facility Operations (License ISFSI TS 5.4.1kCondition and Tech. Spec. x x X x X X x X X Xx RSQM Section XVllICompliance)

___10 CFR 50/72 LicensesISF5l TS 5.4,1kRadiation Protection X X X(2) X X X X X X 10OCFR 20_______ ___ _____RSQM, APP. ARadioactive Effluent Control ISFS1 TS 5.4.1kProgram (RECP) (3) X X X X X X X X X X Reg. Guide 4.15RSQM, APP. A______________________

_____10 CFR 50, APP. IRadiological Environmental ISFSI TS 5.4.1kMonitoring Program (REMP) (3) X X X14) X X X X X X X Reg. Guide 4.15____________________RSQM, APP. ARadwaste Handling and ISF51 TS 5.4.1kShipping (Including Process X X X X X X X X X X X X X 10 CFR 71Control Program)

()10 CFR 20.2006(d)

RSAP-0302, ATT. 6____________________RSQM, APP. AISFSI TS 5.4.1k & 5.7Fire Protection (6 X X X X X X X X RSQM, APP. A__________________________Decommissioning OrderISFSI TS 5.4.1kSecurity (7) X X X X X X X X 10OCFR 72.44 &18610 CFR 73ISFSI TS 5.4.1kEmergency Preparedness X X X X X X X X 10 CFR 50.54(t)10 CFR 50, APP. E__________RSOM, APP. AISFS1 TS 5.4.1kTraining X X X X X X X X 10OCFR 72.190____ RSQM, APP. A10 CFR 71/72 Important-to-ISFIS TS 5.4.1kSafety, Category B &C (5 X X X X X X X X X X X X X X RSAP-0302,ATT.

6(QA Class 2) 10 CFR 72.3 & 72.140________________________

__________

____ ___ _____ ___________10 CFR 71.101Attachment I1-1 (Page 1 of 2)

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 17 OF 77Footnotes:

(1) 10 CFR 50, Appendix B, Quality Criteria and corresponding RSQMsection titles:I. Organization II. Quality Assurance CriteriaIII. Design ControlIV. Procurement Document ControlV. Instruction, Procedures, and DrawingsVI. Document ControlVII. Control of Purchased

Material, Equipment, and ServicesVIII. Identification and Control of Materials, Parts, and Components IX. Control of Special Processes X. Inspection XI. Test ControlXII. Control of Measuring and Test Equipment XIII. Handling,
Storage, and ShippingXIV. Inspection, Test, and Operating StatusXV. Nonconforming Materials, Parts, or Components XVI. Corrective ActionXVII. Quality Assurance RecordsXVIII. Audits(2) Design Control as applied to permanent protective shielding.

(3) Rancho Seco applies the NRC Regulatory Guide 4.15 QA/QC program tothe RECP and REMP. This Regulatory Guide 4.15 program meets theapplicable 10 CFR 50, Appendix B QAIQC program requirements.

(4) As applied to environmental monitoring laboratory analysis services.

(5) As applied to 10 CFR 71 activities authorized pursuant to NRC Form 311,"Quality Assurance Approval for Radioactive Material Packages,"

Approval No. 0489. (Refer to RSQM Section II, Steps 4.3.2 and 4.4.2)(6) No Fire Protection equipment or services falls under the QAP.ATTACHMENT Il-1 (Page 2 of 2)REGULATORY COMMITMENTS

.RANCHO SECO LICENSING BASIS DOCUMENTNUMBER: RSLBD-010 REVISION:

2PAGE 18 OF 77TITLE: RANCHO SECO QUALITY MANUALSMUD commits to the requirements of the regulations and industry standards listedbelow with any exceptions identified in Attachment 11-3.DocumentRevision/Date Title1 Regulatory Guide1.82 Safety Guide 28ANSI N45.23 Regulatory Guide1.28ANSI/ASME NQA-Supplement 17S-14 Safety Guide 30ANSI N45.2.45 Safety Guide 336Regulatory Guide1.37ANSI N45.2.17 Regulatory Guide1.38ANSI N45.2.28 Regulatory Guide1.39ANSI N45.2.39/756/7/7219718/8519838/11/721972Personnel Selection and TrainingPer ISFSI Tech. Spec. 5.3Quality Assurance Requirements forNuclear Power PlantsSupplementary Requirements for QualityAssurance Records (See Attachment 11-3,Exception No. 1)Quality Assurance requirements for theinstallation, Inspection, and Testing ofInstrumentation and Electrical Equipment (See Attachment I1-3, Exception No. 2)11/3/72 Administrative Controls for Nuclear PowerPlants as Addressed in RSQM Appendix A3/16/7319733/16/7319723/16/731973Quality Assurance Requirements forCleaning Fluid Systems and Associated Components of Water-Cooled NuclearPower Plants (See Attachment 11-3,Exception No. 3)Quality Assurance Requirements forPackaging,

Shipping, Receiving, Storageand Handling of Items for Water-Cooled Nuclear Power Plants (See Attachment II-3, Exception No. 8)Housekeeping Requirements for Water-Cooled Nuclear Power Plants (SeeAttachment 11-3, Exception No. 4)ATTACHMENT 11-2 (Page 1 of 2)

PANCHO SECO LICENSING BASIS DOCUMENTTITLE: RANCHO SECO QUALITY MANUALNUMBER: RSLBD-010 REVISION:

2PAGE 19 OF 779 Regulatory Guide1.54ANSI N101.410 Regulatory Guide1.58ANSI N45.2.611 Regulatory Guide1.64ANSI N45.2.1112 Regulatory Guide1.74ANSI N45.2.1013 Regulatory Guide1.94ANSI N45.2.514 Regulatory Guide1.116ANSI N45.2.815 Regulatory Guide1.12016 Regulatory Guide1.123ANSI N45.2.1317 Regulatory Guide1.144ANSI N45.2.1218 Regulatory Guide1.146ANSI N45.2.236/7319729/80197810/7319742/741973Rev. 219786/76197511/777/7719761/7919778/801978Quality Assurance Requirements forProtective Coatings Applied to NuclearFacilities Qualification of Nuclear Power PlantInspection, Examination, and TestingPersonnel (See Attachment 11-3, Exception No. 5)Quality Assurance Requirements for theDesign of Nuclear Power Plants (SeeAttachment 11-3, Exception No. 6)Quality Assurance Terms and Definitions (See Attachment 11-3, Exception No. 7)Quality Assurance Requirements forInstallation, Inspection, and Testing ofStructural Concrete and Structural Steelduring the Construction Phase of NuclearPower PlantsQuality Assurance Requirements forInstallation, Inspection, and Testing ofMechanical Equipment and SystemsFire Protection Guidelines for NuclearPower PlantsQuality Assurance Requirements forControl of Procurement Items and Servicesfor Nuclear Power PlantsAuditing of Quality Assurance Programsfor Nuclear Power PlantsQualification of Quality Assurance ProgramAudit Personnel for Nuclear Power PlantsATTACHMENT 11-2 (Page 2 of 2)EXCEPTIONS:

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 20 OF 77EXCEPTION NO. 1: Regulatory Guide 1.28/NQA-1, Supplement 17S-1SMUD complies with the recommendations of this regulatory guide with the following clarifications:

With regard to Section 2.4 of Supplement 17S-1 titled Index: The phrase "anindex" is clarified to mean a collection of documents or indices which, when takentogether, supply the information attributed to "an index" in the standard.

The specific location of a record "within a storage area" may not be delineated (e.g., the specific location within a computer record file may not be constant;

further, SMUD may utilize a computer assisted random access filing systemwhere such location could not be readily "documented,"

or would such a locationbe "relevant.")

The storage location will be delineated, but where file locations change with time, the specific location of a record within that file may not alwaysbe documented.

With regard to Section 4.3, Supplement 17S-1 titled Safekeepincq:

Routine generaloffice and nuclear site security systems and access controls are provided:

Nospecial security systems are required to be established for record storage areas.With regard to Section 4.4, Supplement 17S-1, titled Facility:

This Sectionprovides no distinction between temporary and permanent facilities.

To covertemporary

storage, the following clarification is added: "Records completed butnot yet transferred for permanent storage may be temporarily stored in one-hourfire rated file cabinets.

In general, records shall not be maintained in suchtemporary storage for more than four months after completion without beingmicrofilmed or placed in permanent storage.

Open-ended documents revised orupdated on a more-or-less continuing basis over an extended period of time (e.g.personnel qualification and training documents, equipment history cards) whichare cumulative in nature (e.g. nonconforming item logs and control room logbooks) shall become QA records when they are issued as a specific revision (e.g.the master audit schedule);

when they are filled-up or discontinued (e.g. log booksor equipment history cards); on a predefined periodic basis when the completed portion of the ongoing document shall be transferred to records control as a"record" (e.g. training and qualification records).

ATTACHMENT 1I-3 ('Pacie 1 of 7)

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 21 OF 77EXCEPTION NO. 2: Regulatory Guide 1.30/ANSI N45.2.4-.72 Specific clarifications for ANSI N45.2.4-1 972 are indicated below by section:Section 1.4Definitions in this standard that are not included in ANSI N45.2.10 shall be used; alldefinitions which are included in ANSI N45.2.10 shall be used as clarified in SMUDcommitment to Regulatory Guide 1.74.Section 2.1Planninqi requirements, as determined by engineering, shall be incorporated intomodification procedures.

Section 2.3Procedures and Instructions shall be implemented as set forth in Sections II, III, V, X andXl of this program and by compliance with the Rancho Seco Plant Technical Specifications and Regulatory Guide 1.33 (ANSI N18.7).Section 2.4Results will be implemented as set forth in Sections X, Xl, and XVII of this program andby compliance with ANSI N18.7 in lieu of the requirements set forth here.Section 2.5.2Calibration and Control covers three classes of instrumentation used by SMUD: (1)M&TE (portable measuring instruments, test equipment, tools, gages, and non-destructive test equipment used in measuring and inspecting safety-related structures,

systems, and components);

(2) reference standards (primary, secondary,

transfer, andworking);

and (3) permanently installed process instrumentation (PI).With respect to the first sentence, M&TE and reference standards shall be included incalibration program and shall either be calibrated at prescribed intervals or shall becalibrated prior to use. With respect to the last sentence, personnel shall be trained andprocedures shall require that the calibration sticker shall be reviewed to determine calibration status prior to use: This label shall be considered to clearly identify equipment that is out of calibration.

Lack of a sticker shall require record review and affixing a new sticker based oncalibration data. M&TE and reference standards shall comply with sentences 2, 3, and4.ATTACHMENT II-3 (Paaie 2 of 7)

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 22 OF 77With respect to the third sentence, SMUD uniquely identifies each safety-related component of permanently installed process instrumentation.

This identification provides traceability to calibration data. These actions are SMUD's alternative to thetagging or labeling of items to indicate the calibration date and the identity of theperson who performed the calibration.

Permanently installed process instrumentation shall comply with sentences 1, 2, and 5.Section 3Pre-construction Verification will be implemented as follows:

(1) is required only formodifications, (2) no special checks are required to be made by the personwithdrawing a replacement part from the warehouse equivalent controls are ensuredby compliance with Regulatory Guide 1.38 (ANSI N45.2.2) as set forth in this table,and, (3) shall be complied with as determined by engineering, by individual technicians as part of the modification process.Section 5.1Inspections, including subsections 5.1.1, 5.1.2, and 5.1.3, will be implemented as setforth in Section X of this program.

The inspection program will incorporate,=

asdetermined by engineering and Quality those items listed in these subsections.

Section 5.2Tests, including subsections 5.2.1 through 5.2.3, will be implemented as set forth inSections IIl and Xl of this program.

In some cases Surveillance testing may be usedto meet the appropriate requirements of this section.Section 6Post Construction Verification is not generally considered applicable at operating facilities because of the scope of the work and the relatively short interval betweeninstallation and operation.

Where considered necessary by engineering andl Quality,the elements described in this Section will be used in the development andimplementation of inspection and testing programs as describe in Sections III, X, andXl of this program.Section 7Data Analysis and Evaluation will be implemented as stated herein after adding theclarifying phrase "Where used" at the beginning of that paragraph.

ATTACHMENT 11-3 (Paae 3 of 7)

.RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 23 OF 77EXCEPTION NO. 3: Regulatory Guide 1.37/ANSI N45.2.1-73 Specific clarifications for this Regulatory Guide and ANSI N45.2.1-1 973 are indicated below:With regard to Paragraph C.3 of Regulatory Guide 1.37: The water quality for finalflushing of fluid systems and associated components shall be at least equivalent tothe quality of the operating system water, except for the oxygen and nitrogen content;but this does not infer that chromate's or other additives, normally in the systemwater, will be added to the flush water.With regard to Paragraph 0.4 of Regulatory Guide 1.37: Expendable materials, suchas inks and related products; temperature indicating sticks; tapes; gummed labels;wrapping materials (other than polyethylene);

water soluble dam materials; lubricants; NDT penetrant materials and couplants, desiccants, which contactstainless steel or nickel alloy surfaces shall not contain lead, zinc, copper, mercury,cadmium and other low melting points metals, their alloys or compounds as basicand essential chemical constituents.

No more than 0.1 percent (1,000 ppm)halogens will be allowed where such elements are leachable or where they could bereleased by breakdown of the compounds under expected environmental conditions.

With regard to Section 5 of ANSI N45.2.1-1 973 titled Installation Cleaning:

Therecommendation that local rusting on corrosion resistant alloys be removed bymechanical methods is interpreted to mean that local rusting may be removedmechanically, but the use of other removal means is not precluded, as determined byEngineering or Chemistry.

EXCEPTION NO. 4: Regulatory Guide 1.39/ANSI N45.2.3-73

.Specific classifications for ANSI N45.2.3-73 are indicated for specific sections below:Section 1.4Definitions:

Definitions in this standard that are not included in Regulatory Guide 1.74(ANSI N45.2.10) will be used. All definitions that are included in ANSI N45.2.10 willbe used as clarified in SMUD's commitment to Regulatory Guide 1.74.Section 2.1 ..Planning:

SMUD may choose not to utilize the five-level zone designation system, butwill utilize standard janitorial and work practices to maintain a level of cleanliness commensurate with program requirements in the areas of housekeeping, plant andpersonnel safety, and fire protection.

ATTACHMENT II-3 ('Pane 4 of 7)

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 24 OF 77Cleanliness will be maintained, consistent with the work being performed, so as toprevent the entry of foreign material into safety-related systems.

This will include, as aminimum, documented cleanliness inspections that will be performed prior to systemclosure.

As necessary, (e.g. the opening is larger than the tools being used) control ofpersonnel, tools, equipment, and supplies will be established when the reactor systemis opened for inspection, maintenance, modification or repair.Additional housekeeping requirements will be implemented as required for control ofradioactive contamination.

Section 2.2Procedures and Instructions:

Appropriate procedures will be written and implemented.

Section 3.2Control of Facilities:

SMUD may choose not to utilize the five-level zone designation system, but will utilize standard janitorial and work practices to maintain a level ofcleanliness commensurate with program requirements in the areas of housekeeping, plant and personnel safety, and fire protection.

Cleanliness will be maintained, consistent with the work being performed,

'so as toprevent the entry of foreign material into safety-related systems.

This will include, as aminimum, documented cleanliness inspections that will be performed prior to systemclosure.

As necessary, (e.g. the opening is larger than the tools being used) control ofpersonnel, tools, equipment, and supplies will be established when the reactor systemis opened for inspection, maintenance, modification or repair.Additional housekeeping requirements will be implemented as required for control ofradioactive contamination.

EXCEPTION NO. 5: Regulatory Guide 1.58/ANSI N45.2.6SMUD complies with the recommendation of the regulatory guide with the following clarification:

With regard to Paragraph C.5: The Level II1 function of inspection

planning, reviewing and concurring with inspection, examination and testing procedures is performed bydesignated individuals from the Quality & Industrial Safety Department.

ATTFACHMENT II-3 (Paae 5 of 7)

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 25 OF 77EXCEPTION NO. 6: Regulatory Guide 1.64/ANSI N45.2.11SMUD complies with the recommendation of the regulatory guide with the following clarification:

With regard to Paragraph C.2: In exceptional circumstances, the designer's immediate supervisor can perform design verification, provided:

1. The supervisor is the only technically qualified individual available.
2. The need is individually documented and approved in advance by thesupervisor's management.
3. QA audits cover frequency and effectiveness of use of supervisors as designverifiers to guard against abuse.EXCEPTION NO. 7: Regulatory Guide 1.74/ANSI N45.2.10-73 SMUD complies with the recommendations of this regulatory guide with the following clarifications:

SMUD reserves the right to define additional words or phrases that are not includedin this Standard.

Such additional definitions will be documented in appropriate procedures.

In addition to the Standard's definition of "Inspection,"

SMUD will use the following definition when referring to activities that are NOT performed by QC personnel:

Examining, viewing closely, scrutinizing, looking over or otherwise checking activities.

Personnel performing these functions are not necessarily certified to Regulatory Guide 1.58 (ANSI N45.2.6).

When SMUD intends for Inspection to be performed in accordance with the QAProgram by personnel certified as required by that program and for activities definedby "inspection" in ANSI N45.2.10, appropriate references to the plant QCorganization or the procedures to be used for performing the activity will be made. Ifsuch references are NOT made, inspections are to be considered under theadditional definition given above."Independent Verification":

Verification by an individual other than the person whoperformed the operation or activity being verified that required actions have beencompleted.

Such verification may not necessarily require confirmation of the actionat the physical location if adequate remote indication of completion of action isavailable.

In determining the acceptability of remote verification, the consequences of the action not being 100% completed and the validity of the remote indication forATTACHMENT 11-3 (Pagje 6 of 7)

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 26 OF 77confirming the completion of the desired action will be considered.

Examplesinclude, but are not limited to: Verification of a breaker opening by observed remotebreaker indication lights; verification of a set point (made with a voltmeter or ammeterfor example) by observing the actuation of status or indicating lights at the requiredpanel-meter indicated value; verification that a valve has been positioned byobserving the starting or stopping of flow on meter indications or by remote valvepositions indicating lights."Will": (Not defined in any ANSI Standard)

-Means the same as "shall" except whenused to denote simple futurity.

When used to denote futurity, "will" is normallyfollowed by "be".EXCEPTION NO. 8: Regulatory Guide 1.38/ANSI N45.2.2Section 2.7Classification of Items -SMUD may choose not to utilize the four levels of item'classification, but will address packaging and storage requirements for. items basedon the needs of individual items and manufacturers recommendation.

ATTACHMENT 11-3 (Pa~ie 7 of 7)

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 27 OF 77III. DESIGN CONTROL1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established for control of design activities affecting applicable structures,

systems, and components at the Rancho Seco nuclear station, whichincludes the Rancho Seco Nuclear Generating Station (RSNGS; licensed andundergoing decommissioning pursuant to 10 CFR 50) and the Independent Spent Fuel Storage Installation (ISFSI; licensed and operated pursuant to 10CFR 72).In addition, this section defines the requirements for developing andimplementing control measures that ensure design functions affecting theperformance of operational, construction, and modification activities are carriedout in a planned, controlled, and orderly manner and are in compliance withapplicable regulatory commitments.

2.0 REFERENCES

2.1 10 CER 50, Appendix B, Criterion Ill, "Design Control"2.2 10 CFR 50.59, Changes, Tests and Experiments 2.3 Regulatory Guide 1.64/ANSI N45.2.1 1, 1974, Quality Assurance Requirements for the Design of Nuclear Power Plants (with exceptions noted in RSQM Section II)2.4 ANSI N45.2, Section 4, Design Control2.5 10 CFR 72.48, Changes, Tests, and Experiments 2.6 10 CFR 71.107, Package Design Control2.7 10 CFR 72.146, Design Control3.0 POLICYThe requirements specified in this section apply to all organizations performing design functions for modifications,

changes, replacement or addition ofstructures,
systems, or components at the Rancho Seco nuclear facility.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 28 OF 774.0 GENERAL REQUIREMENTS Procedures shall be established and executed to control design activities.

Procedures covering design control activities shall include the following requirements:

4.1 Applicable design inputs such as design bases, regulatory requirements, codes and standards, methodology, and all assumptions with appropriate justifications are identified, documented, and correctly translated intodesign output documents such as specifications,

drawings, procedures, orinstructions.

4.2 Exceptions, waivers to or deviations from engineering requirements aredocumented and controlled.

4.3 Methods are specified for the selection and classification of suitablematerials, parts, equipment, and processes used in meeting applicable requirements for structures,

systems, and components.

Materials, parts, components, and equipment that are standard, commercial (off the shelf), or which have been previously approved forother similar applications are reviewed for suitability and appropriately classified.

4.4 Systematic methods are established for communicating and controlling theflow of related design information across the external and internal designinterfaces, including any changes to the design information as the workprogresses.

4.5 Interfaces between Engineering and other participating designorganizations (either internal or external to SMUD) are identified anddocumented.

This identification includes those organizations providing design inputs, design analyses, design specifications, and designverification for operational, construction and modification design activities.

4.6 Participating design organizations establish and describe the controlled methods for preparation, review, approval,

release, distribution, andrevision of documents (such as design analyses, specifications,
drawings, reports) involving design interfaces.

4.7 Design control measures shall provide for verifying or checking the adequacyof design modifications or design changes.

Acceptable verification methodsinclude, but are not limited to, design reviews, alternate calculations, orqualification testing.

If a test program is used to verify the adequacy of a RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: PANCHO SECO QUALITY MANUAL PAGE 29 OF 77design, it must include qualification testing of a prototype unit under the mostadverse design conditions.

4.8 Computer program codes used for design calculations are certified for useand their use is specified.

4.9 Design verification is to be performed by competent individuals or groupsother than those who performed the original design, but who may be fromthe same organization.

The originator's supervisor may perform thisverification provided the supervisor is the only technically qualified individual available and meets the appropriate clarification provisions ofReference 2.4. The results of the design verification efforts must bedocumented with the identification of the verifier clearly provided.

4.10 Provisions are specified for the control of design analyses such as; reactorphysics, stress, thermal, hydraulic, and accident analyses; compatibility ofmaterials; accessibility for in-service inspection, maintenance, and repair;and delineation of acceptance criteria for inspections and tests.4.11 Design problems that are identified during field installation or testingactivities shall be documented and forwarded to Engineering forevaluation and resolution.

4.12 Design and specification

changes, including field changes, receive thesame degree of control and approval as the original design unless anotherqualified, responsible organization is specifically designated.

4.13 Errors and deficiencies in the design process, including computerprograms that could adversely affect structures,

systems, or components are documented and corrective action is taken to preclude repetition.

4.14 Proposed modifications or design changes which involve an Unreviewed Safety Question or a change to Rancho Seco nuclear facility Licenses orTechnical Specifications are handled in accordance with 10 CFR 50.59,10 CFR 72.48, and 10 CFR 71.107(c),

as appropriate.

4.15 Modifications are reviewed by plant personnel for effect on plant operation prior to making the modification operational.

4.16 Design documents are reviewed for accessibility of equipment andcomponents for in-service inspection, tests, maintenance or modifications.

4.17 Design and/or test documentation must be obtained from all suppliers onprocurements of ASME code components used for replacement ormodification to the Rancho Seco nuclear facility.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 30 OF 775.0 RESPONSIBILITIES General organizational responsibilities are described in Section I,ORGANIZATION.

5.1 Engineering is responsible for implementing a design control processper this section and to:a. Provide and control design change packages.

b. Ensure integrity and regulatory conformance of configuration control.c. Provide plant configuration control including establishing andmaintaining baseline documents.
d. Provide engineering support for facility computers.
e. Perform probabilistic analysis in support of plant design, whennecessary.
f. Provide engineering support to the Rancho Seco nuclearorganization.
g. Provide and maintain engineering procedures, standards andspecifications and drawings.
h. Prepare and maintain the Master Equipment List (MEL)described in RSQM Section I1.5.2 Quality Assurance is responsible for:a. Review and concurrence of design control procedures.
b. Monitoring implementation of the design control program.c. Auditing the design control program per RSQM Section XVIII.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 31 OF 77IV. PROCUREMENT DOCUMENT CONTROL1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established to control procurement documents for material, equipment, and services at the Rancho Seco nuclear facility, which includes the RanchoSeco Nuclear Generating Station (RSNGS; licensed and undergoing decommissioning pursuant to 10 CFR 50) and the Rancho Seco Independent Spent Fuel Storage Installation (ISFSI; licensed and operated pursuant to 10CFR 72).2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion IV, Procurement Document Control2.2 ANSI N45.2-1 971, Section 5, Procurement Document Control2.3 Regulatory Guide 1.123/ANSI N45.2.13-1976, Quality Assurance Requirements for Control of Procurement of Items and Services forNuclear Power Plants2.4 10 CFR 71.109, Procurement Document Control2.5 10 CFR 72.148, Procurement Document Control3.0 POLICYProcurement documents for applicable Rancho Seco nuclear facility materials, equipment, components/spares, or services shall include applicable technical requirements, quality requirements, regulatory requirements, and otherprovisions necessary to ensure that purchased items and services areadequately described to the supplier.

4.0 GENERAL REQUIREMENTS 4.1 Procedures shall be established and implemented to control thepreparation, review, approval and issuance of procurement documents.

4.2 Procurement documents shall include provisions for the following, asapplicable:

a. Description of item or service.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 32 OF 77b. Identification of design specifications and technical requirements byreference to specific

drawings, codes, regulations, industrystandards, or other documentation, including the applicable revisionthereto that describe the items or services to be furnished.
c. Identification of test, inspection, and acceptance requirements, andany special instructions and requirements for activities such asdesign, fabrication, identification,
cleaning, erecting, packaging,
handling, shipping, and extended storage.d. Identification of applicable QAP criteria.
e. Applicability of 10 CFR Part 21.f. Identification of the documentation, such as drawings, specifications, procedures, fabrication and inspection plans,inspection and test records, personnel and procedure qualifications, and chemical and physical test reports to be prepared andmaintained by the supplier or contractor, and the requirement tosubmit this documentation to SMUD for review and approval.
g. Identification of those records to be retained, controlled, andmaintained by the supplier or contractor and those to be delivered to SMUD at the time of shipment of the procured item.h. SMUD's right of access to the supplier's facilities and records forinspection and audits.i. Extension of applicable requirements to lower tier subcontractors and suppliers, including SMUD's right of access to facilities andrecords.j. Supplier submittal of nonconforming items and SMUD approval for"Accept as is" or "Repair" dispositions of non-conformances.
k. SMUD's right to hold shipment if procurement documentrequirements, including those for documentation, have not beenfulfilled.

4.3 Technical and quality review by qualified personnel and approval bydesignated individuals shall be performed prior to issuance of theprocurement document.

The review and approval shall be documented and available for verification.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 33 OF 774.4 Review and concurrence by Quality Assurance shall be performed toensure adequacy of quality requirements and to verify that therequirements are correctly stated, inspectable, and controllable; that thereare adequate acceptance and rejection criteria; and that the procurement documents have been prepared,

reviewed, and approved in accordance with the requirements of the established procedures.

4.5 Revisions to procurement documents shall receive an equivalent reviewand approval as the original documents.

Exceptions to this includechanges in quantity, estimated price, cost codes, taxes, format or editorial changes that do not affect the quality of the item or service.4.6 Procurement documents for spare or replacement parts for QA Class 1structures,

systems, or components shall specify procurement controls atleast equivalent to those required for purchase of the original equipment.

4.7 Methods shall be established to ensure that the items received aretraceable to procurement documents.

5.0 RESPONSIBILITIES

General organizational responsibilities are described in Section I,ORGANIZATION.

5.1 General Services is responsible for:a. Purchase items in conformance with procurement documents.

b. Purchase safety-related (QA Class 1) items from approvedsuppliers.
c. Arrange for suppliers to be placed on an Approved Suppliers List(ASL). (Refer to RSQM Section VII, step 4.2 regarding ASL)d. Arrange for source inspection when specified on the procurement documents.

5.2 Engineering is responsible for:Maintain a staff of qualified engineers who provide technical and qualityrequirements for purchasing safety-related (QA Class 1) items.5.3 Quality Assurance is responsible for:a. Review and concurrence of material management procedures.

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+I REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 34 OF 77b. Review and concurrence of procurement documents for safety-related (QA Class 1) items.c. Auditing the procurement document control program per RSQMSection XVIII.d. Developing and maintaining the ASL.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 35 OF 77V. INSTRUCTIONS, PROCEDURES, AND DRAWINGS1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established to ensure that activities affecting the quality or safety ofthe Rancho Seco nuclear facility, which includes the Rancho Seco NuclearGenerating Station (RSNGS; licensed and undergoing decommissioning pursuant to 10 CFR 50) and the Rancho Seco Independent Spent Fuel StorageInstallation (ISFSI; licensed and operated pursuant to 10 CFR 72), are described and accomplished in accordance with documented instructions, procedures,

drawings, or other documents appropriate to the circumstances.

2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, andDrawings2.2 ANSI N45.2-1 971, Section 6, Instructions, Procedures, and Drawings2.4 Safety Guide 33/ANSI N18.7, Administrative Controls for Nuclear PowerPlants2.4 10 CFR 71.150, Instructions, Procedures, and Drawings2.5 10 CFR 72.111, Instructions, Procedures, and Drawings3.0 POLICYActivities affecting quality performance or operational safety at the Rancho Seconuclear facility shall be described and implemented in accordance withdocumented instructions, procedures, and drawings.

4.0 GENERAL REQUIREMENTS 4.1 Written instructions, procedures,

drawings, or other documents appropriate to the circumstances shall be prepared to provide measuresfor complying with the provisions of the QAP.4.2 Instructions, procedures, or drawings shall include applicable quantitative and/or qualitative acceptance criteria for verifying that the activities havebeen satisfactorily accomplished.

4.3 Procedures shall be established for the review, approval,

issuance, change, and use of documents that specify quality requirements such as RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 36 OF 77instructions, procedures,

drawings, and other documents that implement the QAP.4.4 Activities affecting quality shall be accomplished in accordance withapproved instructions, procedures, and drawings.

5.0 RESPONSIBILITIES

General organizational responsibilities are described in Section I,ORGANIZATION.

5.1 Rancho Seco management is responsible for ensuring activities that affectquality are described in instructions, procedures, and drawings.

5.2 Quality Assurance is responsible for performing audits to verify that anyactivities affecting quality are described in instructions, procedures and,drawings.

Audits shall be conducted in accordance with RSQM SectionXVIII.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 37 OF 77VI. DOCUMENT CONTROL1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established for the issuance and control of documents that controlactivities affecting quality at the Rancho Seco nuclear facility, which includes theRancho Seco Nuclear Generating Station (RSNGS; licensed pursuant to 10 CFR50) and the Independent Spent Fuel Storage Installation (ISFSI; licensed andoperated pursuant to 10 CFR 72).2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion VI, Document Control2.2 ANSI N45.2-1 971, Section 7, Document Control2.3 ANSI N45.2.1 1-1 974, Section 7, Document Control2.4 10 CFR 71.113, Document Control2.5 10 CFR 72.152, Document Control3.0 POLICYApplicable documents, including changes thereto, that prescribe activities affecting the quality operation at the Rancho Seco nuclear facility shall be issuedand controlled in a manner that precludes the use of inappropriate or outdateddocuments.

4.0 GENERAL REQUIREMENTS 4.1 The responsible organization shall establish procedures that defineresponsibilities and delineate the sequence of actions to be accomplished in preparation, review, approval, and control of instructions, procedures, ordrawings, or changes thereto.4.2 Procedures that establish document control measures shall include:a. Identification of documents to be controlled;

b. Identification of individuals or organizations responsible for thereview, approval,
issuance, and revision of documents; PANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 38 OF 77c. Criteria to ensure that adequate technical and quality requirements are incorporated prior to implementation;

d. Review of changes to documents by the same organizations thatperformed the initial review and approval or by the organizations designated in accordance with the applicable procedures.

4.3 Controlled documents, including

changes, shall be issued and distributed to organizations noted on distribution lists so that proper and currentdocuments are available as required, and obsolete or superseded documents are identified and not used for prescribed activities.

4.4 Master lists or equivalent means shall be used to identify the currentrevision of controlled documents and made available at work locations, asappropriate.

5.0 RESPONSIBILITIES

General organizational responsibilities are described in Section I,ORGANIZATION.

5.1 Site Document Control (SDC) is responsible for developing andimplementing a document control program in accordance with this section.5.2 Rancho Seco management is responsible for:a. Complying with document review, approval, and revision authority defined in plant administrative procedures.

b. Ensuring Quality Assurance review of documents with qualityassurance related aspects, as appropriate.

5.3 Quality Assurance is responsible for:a. Reviewing and concurring with document control procedures.

b. Reviewing and concurring with prOcedures, instructions, ordocuments that implement the QAP to ensure compliance withapplicable RSQM provisions.
c. Auditing the document control program per RSQM Section XVIII.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 39 OF 77VII. CONTROL OF PURCHASED

MATERIAL, EQUIPMENT, ANDSERVICES1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established to ensure that material, equipment, and servicespurchased for the Rancho Seco nuclear facility, which includes the Rancho SecoNuclear Generating Station (RSNGS; licensed and undergoing decommissioning pursuant to 10 CFR 50) and the Independent Spent Fuel Storage Installation (ISFSI; licensed and operated pursuant to 10 CFR 72), conform to theprocurement documents.

2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion VII, Control of Purchased

Material, Equipment, and Services2.2 ANSI N45.2-1 971, Section 8, Control of Purchased
Material, Equipment,.

and Services2.3 Regulatory Guide 1.123/ANSI N45.2.13-76, Quality Assurance Requirements for Control of Procurement of Items and Services forNuclear Power Plants2.4 10 CFR 71.115, Control of Purchased

Material, Equipment, and Services2.5 10 CFR 72.154, Control of Purchased
Material, Equipment, and 3.0 POLICYMeasures shall be established to ensure that material, equipment, and servicesconform to the specified requirements of the related procurement documents.

4.0 GENERAL REQUIREMENTS 4.1 Control of purchased

material, equipment, and Services shall include thefollowing, as appropriate:
a. Source evaluation and selection of suppliers.
b. Objective evidence of quality furnished by the supplier.
c. Source inspection, audit, and/or surveillance activities.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 40 OF 77d. Examination of items or services upon delivery or completion.

4.2 Results of source evaluation and selection of suppliers shall bedocumented and retained on file.4.3 Procedures for control of materials, equipment, and services shall addressthe following:

a. Responsibilities of departments performing supplier technical andquality evaluations, and the method of evaluation.
b. Inspection activities that specify the characteristics or processes tobe witnessed, inspected or verified; the method of verification andthe extent of documentation required; and the organization responsible for implementing the inspection.
c. Auditing to verify conformance and implementation to requirements of this policy. Source inspection and audits may not be necessary when conformance of an item to procurement requirements can beverified by receipt inspection, review of test reports, certified reportsor other means specified by Quality Assurance.
d. Receipt inspection of supplier furnished items to ensure: (1) theproper identification of items on the receiving documentation, (2)that the items are inspected and judged acceptable in accordance with predetermined instructions prior to installation or use, (3) thatinspection records or certificates of conformance are available atthe plant site prior to installation or use of the items, and (4) thatitems accepted and released are identified as to their inspection status prior to storage or use.e. Review, acceptance, and maintenance of records to ensureadequacy of documentation that identifies the purchased item, andthat specific procurement requirements (e.g., codes, standards, specifications) have been met or satisfied.
f. Review and approval of documentation required to be submitted bythe procurement documents (CMTR's, Certificate of Compliance, Procedures, Specifications, etc.).g. Procurement control of spare or replacement parts for QA Class 1systems to ensure compliance with requirements that are (1)equivalent to the original requirements or (2) specified by a properlyreviewed and approved revision to the original requirements.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 41 OF 775.0 RESPONSIBILITIES General organizational responsibilities are described in Section I,ORGANIZATION.

5.1 Engineering is responsible for:a. Ensuring quality and qualifications of parts and materials by (1)developing quality specifications and (2) storing parts and materials in accordance with regulatory requirements and in coordination withappropriate nuclear organization groups.b. Ensuring regulatory compliance of materials and parts by managingprocurement documentation and reviewing (and implementing, asappropriate)

NRC and related parts/materials bulletins.

c. Examining items or services upon delivery or completion, asdeemed necessary to supplement or replace formal inspection activities.

5.2 Quality Assurance is responsible for:a. Developing and maintaining the ASL.b. Performing required inspections, evaluations, and audits.c. The review and concurrence with material management procedures.

d. Auditing the control of purchased
material, equipment, and servicesper RSQM Section XVIII.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 42 OF 77VIII. IDENTIFICATION AND CONTROL OF MATERIALS, PARTS, &COMPONENTS 1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established to provide for the identification and control of material, parts, and components for the Rancho Seco nuclear facility, which includes theRancho Seco Nuclear Generating Station (RSNGS; licensed and undergoing decommissioning pursuant to 10 CFR 50) and the Independent Spent FuelStorage Installation (ISFSI; licensed and operated pursuant tol10 CFR 72).2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion VIII, Identification and Control ofMaterials, Parts and Components 2.2 ANSI N45.2-1 971, Section 9, Identification and Control of Materials, Parts,and Components 2.3 10 CFR 71.117, Identification and Control of Materials, Parts, andComponents 2.4 10 CFR 72.156, Identification and Control of Materials, Parts, andComponents 3.0 POLICYProcedures shall be established and implemented to ensure that materials, parts,or components are properly identified and controlled to preclude the use ofincorrect or nonconforming items.4.0 GENERAL REQUIREMENTS 4.1 Materials, parts, or components, including partially fabricated subassemblies and consumables, shall be identified so they can berelated to their applicable

drawing, specification, purchase
document, andinspection records at any stage from initial receipt throughfabrication/construction, installation, repair, modification, or use.4.2 Identification
controls, implementation procedures, and documentation shall be used to ensure that only correct and accepted items are usedduring all stages of construction, installation, and operation.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 43 OF 774.3 Unique identification of items is required, e.g., by part number, serialnumber, heat number, drawing identification number, or other traceable coding methods.4.4 Identification is required to be maintained either on the item or on recordstraceable to the item. Physical identification such as by marking ortagging shall be used to the maximum extent practical.

4.5 When specified by codes, standards, procurement documents, or otherrequirements, identification is required such that items are traceable toappropriate documentation (e.g., specifications,

drawings, purchaseorders, manufacturing and inspection documents, nonconformance
reports, physical or chemical mill test reports).

4.6 Where identification marking is employed, the marking is required to beclear, unambiguous and indelible, and shall be applied such as not toaffect the fit, function, or quality of the item.4.7 Markings shall be transferred to each part of an item, if subdivided.

Themarkings shall not be obliterated or hidden by surface treatment orcoatings unless other means of identification are substituted.

4.8 Procedures are required to provide for the verification and documentation of correct identification of items prior to release for use. Items may beconditionally released under adequate procedural controls.

4.9 Bulk consumables (such as weld rod, chemicals,

reagents, gases, resins,lubricating oil and grease, fuel oil, cleaning
solvents, etc.) must beidentified and controlled in accordance with approved procedures thatspecify the applicable requirements for identification and use of theconsumables.

4.10 In the event the identification or traceability of an item is lost, it shall behandled in accordance with RSQM Section XV.5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I,ORGANIZATION.

5.1 General Services is responsible for identification and control of items fromprocurement through withdrawal from the warehouse.

5.2 Maintenance is responsible for maintaining identification and control ofitems from withdrawal from the warehouse through installation.

RANCHO SECO LICENSING BASIS DOCUMENTTITLE: RANCHO SECO QUALITY MANUALNUMBER: RSLBD-010 REVISION:

2PAGE 44 OF 775.3 Quality Assurance is responsible for:a. Review and concurrence of procedures for controlling

material, parts, and components from procurement through storage,issuance, and installation.
b. Auditing the process for identification and control of materials, parts, and components in accordance with RSQM Section XVIII.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 45 OF 77IX. CONTROL OF SPECIAL PROCESSES 1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established to control special processes used at the Rancho Seconuclear facility, which includes the Rancho Seco Nuclear Generating Station(RSNGS; licensed and undergoing decommissioning pursuant to 10 CFR 50)and the Rancho Seco Independent Spent Fuel Storage Installation (ISFSI;licensed and operated pursuant to 10 CFR 72).2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion IX, Control of Special Processes 2.2 ANSI N45.2-1977, Section 10, Control of Special Processes 2.3 ASME Section V and IX2.4 10 CFR 71.119, Control of Special Processes 2.5 10 CFR 72.158, Control of Special Processes 3.0 POLICYPrior to performing any special processes, procedures shall be established andimplemented to ensure that special processes and equipment are controlled andthat qualified personnel and procedures accomplish required activities.

4.0 GENERAL REQUIREMENTS 4.1 Prior to performing any special processes, procedures shall be preparedto provide for proper control of special processes, which include welding,heat treating, chemical

cleaning, application of protective
coatings, andnondestructive examination (N DE).4.2 Controls shall be established to ensure that only approved materials andequipment are used to perform special processes.

4.3 Personnel who perform special processes shall be qualified in accordance with industry standards.

4.4 Special process requirements shall be prescribed in the controlling specifications,

drawings, procurement documents, or procedures.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 46 OF 775.0 RESPONSIBILITIES General organizational responsibilities are described in Section 1,ORGANIZATION.

5.1 Encilneerinci is responsible for:10a. Specifying the special processes on design documents governing maintenance/modification activities.

b. Developing, qualifying, and maintaining special process procedures in accordance with Step 4.1 of this RSQM section.c. Qualifying personnel or approving contract personnel to performspecial processes identified in Step 4.1 of this RSQM section.d. Performing NDE or approving contract personnel to perform NDE.5.2 Quality Assurance is responsible for:a. Review and concurrence of special process procedures.
b. Auditing the special process program in accordance with RSQMSection XVIII.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 47 OF 77X. INSPECTION 1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established to provide for the inspection of material, parts, andcomponents for the Rancho Seco nuclear facility, which includes the RanchoSeco Nuclear Generating Station (RSNGS; licensed and undergoing decommissioning pursuant to 10 CFR 50) and the Independent Spent FuelStorage Installation (ISFSI; licensed and operated pursuant to 10 CFR 72).2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion X, Inspection 2.2 ANSI N45.2-1971, Section 11, Inspection 2.3 Regulatory Guide 1.58/ANSI N45.2.6-78, Qualification of Nuclear PowerPlant Inspection, Examination and Testing Personnel with exceptions noted in RSQM Section II.2.4 Safety Guide 33/ANSI N18.7, Administrative Controls for Nuclear PowerPlants2.5 10 CER 71.121, Internal Inspection 2.6 10 CFR 72.160, Licensee Inspection 3.0 POLICYProcedures shall be established and implemented to ensure that inspections areperformed to verify compliance with specified requirements at the Rancho Seconuclear facility.

4.0 GENERAL REQUIREMENTS 4.1 Inspections shall be applied to receiving, maintenance, and modification activities to verify that items and activities conform to specified requirements.

4.2 Inspection planning documents shall be prepared or reviewed by QualityAssurance in accordance with established procedures.

Inspection planning documents shall identify the following as applicable:

a. Characteristics and activities to be inspected; RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 48 OF 77b. Inspection organization;

c. Accept/reject criteria;
d. Hold points and/or witness points;e. Inspection Methods;f. Provisions for recording objective evidence of inspection results;andg. Measuring and test equipment of the necessary accuracy forperforming inspection.

4.3 Process monitoring may be used where direct inspection alone isimpractical or inadequate.

Both inspection and process monitoring areperformed when control is inadequate without both.4.4 Training and qualification of personnel, who perform inspections including NDE, shall be performed in accordance with approved procedures.

4.5 Hold points are designated as mandatory inspection points whenconfirmation is needed that the work at the point is acceptable beforeadditional work can proceed.

Authorized personnel perform hold pointinspections and release work for further processing or use.4.6 Inspections, including any required hold points, are performed anddocumented in accordance with written procedures.

Inspection results aredocumented and evaluated by qualified personnel to verify acceptability.

4.7 Quality Assurance personnel perform inspections of receiving, maintenance, and modification activities.

4.8 Inspection records shall contain the following where applicable:

a. Item inspected;
b. The date of the inspection;
c. Inspector or data recorder identification;
d. Identification of M&TE used to perform inspections;
e. Type of observation; RANCHO SECO LICENSING BASIS DOCUMENTTITLE: RANCHO SECO QUALITY MANUALNUMBER: RSLBD-010 REVISION:

2PAGE 49 OF 77f. Results or acceptability; andg. Reference to information on action taken on non-conformances toresolve any discrepancies noted.5.0 RESPONSIBILITIES General organizational responsibilities are described in Section i,ORGANIZATION.

5.1 Quality Assurance is responsible for:a. Qualifying Quality Control Inspectors.

b. Preparing or reviewing inspection-planning documents formodification/maintenance activities.
c. Performing inspections per inspection plans.d. Auditing the inspection program in accordance with RSQM SectionXVIII.5.2 Maintenance is responsible for assuring:

a.b.5.3 Eacha.b.Inspections are performed as required by inspection planning.

Work does not proceed beyond inspector signoffs for hold points.organization is responsible for:Supporting inspection activities.

Providing prompt corrective action to any deficiencies found duringthe inspection.

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2TITLE: PANCHO SECO QUALITY MANUAL PAGE 50 OF 77Xl. TEST CONTROL1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established to provide for acceptance and surveillance test control atthe Rancho Seco nuclear facility, which includes the Rancho Seco NuclearGenerating Station (RSNGS; licensed and undergoing decommissioning pursuant to 10 CFR 50) and the Independent Spent Fuel Storage Installation (ISFSI; licensed and operated pursuant to 10 CFR 72).2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion Xl, Test Control2.2 ANSI N45.2-1971, Section 12, Test Control2.3 Safety Guide 33/ANSI N18.7, Administrative Controls for Nuclear Plants2.4 10 CFR 71.123, Test Control2.5 10 CFR 72.162, Test Control3.0 POLICYProcedures shall be established and implemented to ensure that required testingto demonstrate that structures,

systems, and components will performsatisfactorily in service is identified, performed and documented.

4.0 GENERAL REQUIREMENTS 4.1 Tests shall be performed in accordance with procedures and criteria thatdesignate when tests are required and how they are to be performed.

Such testing includes the following:

a. Qualification tests, as applicable, to verify design adequacy.
b. Tests of equipment and components to ensure their properoperation prior to delivery or pre-operational tests;c. Pre-operational tests to ensure proper and safe operation ofsystems and equipment prior to startup tests or operations; RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 51 OF 77d. Startup tests to ensure proper and safe operation of systems andequipment.

e. Surveillance tests to ensure continuing proper and safe operation ofsystems and equipment.
f. Maintenance tests after preventive or corrective maintenance.

4.2 Test procedures and instructions shall include provisions for the following, as applicable:

a. The requirements and acceptance limits contained in the applicable design and procurement documents;
b. Test prerequisites such as calibrated instrumentation, required testequipment, degree of completeness of the item to be tested,suitable and controlled environmental conditions, and provisions fordata collection and storage;c. Verifying that test prerequisites have been met;d. Instructions for performing the test;e. Any inspection points;f. Acceptance criteria;
g. Documenting or recording test data and results; andh. Verification of completion.

4.3 Test procedures and instructions shall be reviewed by the applicable organizations for technical content.4.4 Test results shall be documented and evaluated by responsible authorities to ensure that test requirements have been satisfied.

4.5 Test records shall contain the following information where applicable:

a. Item tested and type of observation;
b. The date and results of the test;c. Information related to deviations or non-conformances; RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 52 OF 77d. Identification of person recording the data;e. Evidence as to the acceptability of the results; andf. Action taken to resolve any deviations and non-conformances noted.5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I,ORGAN IZATION.5.1 Quality Assurance is responsible for auditing the test control program perRSQM Section XVIII.5.2 Engineering is responsible for:a. Establishing the procedure for acceptance and surveillance testing.b. Providing personnel to perform the testing and acceptance evaluations.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 53 OF 77XlI. CONTROL OF MEASURING AND TEST EQUIPMENT 1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established to provide for the control of measuring and test equipment at the Rancho Seco nuclear facility, which includes the Rancho Seco NuclearGenerating Station (RSNGS; licensed and undergoing decommissioning pursuant to 10 CFR 50) and the Independent Spent Fuel Storage Installation (ISFSI; licensed and operated pursuant to 10 CFR 72).2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XII, Control of Measuring and TestEquipment 2.2 ANSI N45.2-1971, Section 13, Control of Measuring and Test Equipment 2.3 Safety Guide 33/ANSI N18.7, Administrative Controls for Nuclear PowerPlants.2.4 Regulatory Guide 1.30/ANSI N45.2.4-72, Quality Assurance Requirements for the Installation, Inspection, and Testing ofInstrumentation and Electric Equipment with exception noted in Section IIof this manual.2.5 10 CFR 71.125, Control of Measuring and Test Equipment 2.6 10 CFR 72.164, Control of Measuring and Test Equipment 3.0 POLICYProcedures shall be established and implemented to ensure that measuring andtesting devices used in final acceptance of activities affecting quality are properly~controlled, calibrated, and adjusted at specified intervals to maintain the desiredaccuracy.

4.0 GENERAL REQUIREMENTS 4.1 Procedures shall be established for calibration, maintenance, and controlof measuring and test equipment utilized in the operation, measurement, inspection, or monitoring of items.4.2 Measuring and Test Equipment (M&TE) shall be calibrated at specified intervals.

These intervals are based on the amount of use, stability,

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 54 OF 77characteristics and other conditions that could adversely affect therequired measurement accuracy.

Reference and secondary calibration standards shall be traceable to nationally recognized standards wherethey exist. Where national standards do not exist, provisions shall beestablished to document the basis for calibration.

4.3 M&TE used for calibrating plant process instrumentation (PI) shall havecalibration ranges, precessions, and accuracy's such that the PI can becalibrated from M&TE with an accuracy ratio of at least two-to-one (M&TEto PI). Calibration accuracy ratios of less than two but equal to or betterthan one shall be acceptable when equipment to meet specified requirements is not commercially available.

The basis of acceptance inthese cases shall be documented.

5.0 RESPONSIBILITIES

General organizational responsibilities are described in Section I,ORGANIZATION.

5.1 Maintenance is responsible for:a. Establishing methods for control of measuring and test equipment.

b. Determining the need for calibrated instruments and measuring devices in Rancho Seco nuclear facility activities.
c. Providing administrative procedures that address the requirements for calibration.
d. Control of measurement devices to ensure their use and accuracy.

5.2 Quality Assurance is responsible for auditing the control of measuring andtest equipment program per RSQM Section XVIII.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 55 OF 77XIII. HANDLING,

STORAGE, AND SHIPPING1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established to provide for the handling,
storage, shipping,
cleaning, and preservation of material and equipment at the Rancho Seco nuclear facility, which includes the Rancho Seco Nuclear Generating Station (RSNGS; licensedand undergoing decommissioning pursuant to 10 CFR 50) and the Independent Spent Fuel Storage Installation (ISFSI; licensed and operated pursuant to 10CFR 72).2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XIII, Handling,
Storage, and Shipping2.2 ANSI N45.2-1 971, Section 14, Handling,
Storage, and Shipping2.3 Regulatory Guide 1.38/ANSI N45.2.2-1 972, Packaging,
Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants withexceptions noted in Section II of this manual.2.4 10 CFR 71.127, Handling,
Storage, and Shipping2.5 10 CFR 72.166, Handling,
Storage, and Shipping3.0 POLICYProcedures shall be established and implemented to ensure that materials andequipment are properly
handled, stored, shipped,
cleaned, and preserved toprevent damage or deterioration.

4.0 GENERAL REQUIREMENTS 4.1 Procedures shall be established for assuring that proper handling,

storage, shipping, and preservation instructions are included in applicable drawings and/or specifications.

4.2 When required for specific items, special protective environments, such asinert gas atmosphere, specific moisture content levels, and temperature levels, shall be specified.

4.3 A shelf life program shall be in effect and monitored to prevent usage afterthe expiration date without re-certification for extension of shelf life.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 56 OF 774.4 Special material handling and preservation instructions shall be developed when required by applicable drawings and/or specifications.

4.5 Materials used for packaging,

shipment, and, storage of items that havethe potential for causing contamination or radiation exposure requiremarking and labeling to indicate the need for special radiological controls.

5.0 RESPONSIBILITIES

General organizational responsibilities are described in Section I,ORGANIZATION.

5.1 Engineering is responsible for establishing methods and procedures toensure that applicable drawings and/or specifications include handling,

storage, shipping, and preservation requirements.

5.2 Maintenance is responsible for:a. Establishing methods for special handling,

storage, andpreservation during maintenance activities.
b. Providing administrative procedures that specify the requiredcontrols.

5.3 Quality Assurance is responsible for auditing conformance to the handling,

storage, and shipping program per RSQM Section XVIII.5.4 General Services is responsible for maintaining material and warehousing control of items and equipment that require special handling and storage.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 57 OF 77XlV. INSPECTION, TEST, AND OPERATING STATUS1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established to provide for a system to identify the inspection, test, andoperating status of individual items at the Rancho Seco nuclear facility, whichincludes the Rancho Seco Nuclear Generating Station (RSNGS; licensed andundergoing decommissioning pursuant to 10 CFR 50) and the Independent Spent Fuel Storage Installation (ISFSI; licensed and operated pursuant to 10CFR 72).2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XIV, Inspection, Test and Operating Status2.2 ANSI N45.2-1 971, Section 15, Inspection, Test, and Operating Status2.3 10 CFR 71.129, Inspection, Test and Operating Status2.4 10 CFR 72.168, Inspection, Test and Operating Status3.0 POLICYProcedures shall be established and implemented to ensure that measures.

areprovided to indicate the status of inspections, tests, and operations.

4.0 GENERAL REQUIREMENTS 4.1 Procedures shall specify the degree of control required for the indication ofinspection and test status of items required for modification activities.

4.2 The sequence of inspections, tests, and other operations, and changesthereto, shall be controlled by procedures.

4.3 Procedures shall provide methods for identifying the nonconforming items,inoperable systems and components by tags, markings, labels, etc. toprevent inadvertent use.5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I,ORGANIZATION.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 58 OF 775.1 Maintenance is responsible for Clearance Program procedures to ensure:a. Safety of personnel and equipment during maintenance and testingactivities.

b. Installation and removal of test and operating status indicators.

5.2 Quality Assurance is responsible for:a. Identifying the quality status of applicable

material, parts, andcomponents.
b. Auditing the inspection, test, and operating status program perRSQM Section XVIII.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 59 OF 77XV. NONCONFORMING MATERIALS, PARTS, OR COMPONENTS 1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established for controlling

material, components, parts, or systems thatare not in conformance to specified requirements at the Rancho Seco nuclearfacility, which includes the Rancho Seco Nuclear Generating Station (RSNGS;licensed and undergoing decommissioning pursuant to 10 CFR 50) and theIndependent Spent Fuel Storage Installation (ISFSI; licensed and operatedpursuant to 10 CFR 72).2.0 REFERENCED DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XV, Nonconforming Materials, Parts orComponents 2.2 ANSI N45.2-1 971, Section 16, Nonconforming Items2.3 10 CFR 71.131, Nonconforming Materials, Parts or Components 2.4 10 CFR 72.170, Nonconforming Materials, Parts or Components 3.0 POLICYProcedures shall be established and implemented to ensure that materials, parts,or components that do not conform to specified requirements are controlled toprevent their inadvertent use or installation.

4.0 GENERAL REQUIREMENTS 4.1 Procedures shall be developed for controlling, documenting, and resolving items, services, or activities identified as nonconforming.

4.2 Marking,

tagging, segregating, or other means shall identifynonconforming items.4.3 Non-conformances shall be documented, processed, controlled andretained to provide records of the actions taken to resolve thenonconforming condition.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 60 OF 775.0 RESPONSIBILITIES General organizational responsibilities are described in Section I,ORGANIZATION.

5.1 Quality Assurance is responsible for:a. Reviewing identified conditions that are adverse to quality and thecorrective action associated with those conditions.

(Refer to RSQMSection XVI regarding corrective action program)b. Establishing methods for controlling and documenting non-conformances.

c. Ensuring expertise is available to disposition non-conformances.
d. Developing safety analyses that address the nonconforming condition, if required.
a. Auditing the nonconforming materials, parts, or components program per RSQM Section XVIII.5.2 Rancho Seco management is responsible for:a. Taking appropriate action to ensure operation of the plant inconformance to license requirements when a nonconformance identifies a condition prohibiting components, structures, or,systems from returning to an acceptable condition.
b. Determining the safety significance of the nonconforming condition on the status of the plant.c. Reviewing identified conditions that are adverse to quality and thecorrective action associated with those conditions.
d. Ensuring expertise is available to disposition non-conformances.
e. Developing safety analyses that address the nonconforming condition, if required.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 61 OF 77XVI. CORRECTIVE ACTION1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established to provide for a corrective action program to ensure thatconditions adverse to quality are promptly identified and corrected at the RanchoSeco nuclear facility, which includes the Rancho Seco Nuclear Generating Station (RSNGS; licensed and undergoing decommissioning pursuant to 10 CFR50) and the Independent Spent Fuel Storage Installation (ISFSI; licensed andoperated pursuant to 10 CFR 72).2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XVI, Corrective Action2.2 10 CFR 72, Subpart D, Records,

Reports, Inspections, and Enforcement.

2.3 ANSI N45.2-1 971, Section 17, Corrective Action2.4 10 CFR 71.133, Corrective Action2.5 10 CFR 72.172, Corrective Action3.0 POLICYProcedures shall be established and implemented to ensure that significant conditions adverse to quality are identified and that corrective action is taken topreclude repetition.

4.0 GENERAL REQUIREMENTS 4.1 Controls shall ensure conditions adverse to quality such as malfunctions, errors, deficiencies or non-conformances are identified, documented andappropriate corrective action taken. The controls shall ensure that thecorrective action is- implemented in a timely manner.4.2 For significant conditions adverse to quality, corrective action includesdetermining the cause and extent of the condition, taking corrective actionto remedy the condition and taking action to prevent recurrence.

Theseactions shall be reported to management personnel for review andassessment.

5.0 RESPONSIBILITIES RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 62 OF 77General organizational responsibilities are described in Section I,ORGANIZATION.

5.1 Rancho Seco management is responsible for:a. Formulating appropriate corrective actions.b. Implementing proposed corrective actions.c. Ensuring that proposed corrective action is effective.

5.2 Quality Assurance is responsible for:a. Auditing the Corrective Action Program per RSQM Section XVIII.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 63 OF 77XVII. QUALITY ASSURANCE RECORDS1.0 PURPOSEThis section describes the Rancho Seco Quality Assurance Program (QAP)measures established for the storage and maintenance of Quality Assurance Records that provide the documentary evidence of activities affecting qualityperformed at the Rancho Seco nuclear facility, which includes the Rancho SecoNuclear Generating Station (RSNGS; licensed and undergoing decommissioning pursuant to 10 CFR 50) and the Independent Spent Fuel Storage Installation (ISFSI; licensed and operated pursuant to 10 CFR 72).2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XVII, Quality Assurance Records2.2 ANSI N45.2-1 971, Section 18, Quality Assurance Records2.3 Safety Guide 33/ANSI N 18.7, Administrative Control for Nuclear PowerPlants, paragraph 5.22.4 Regulatory Guide 1.28/ANSI/ASME, NQA-1-1 983, Supplement 17S-1,Supplementary Requirements for Quality Assurance

Records, withexceptions as noted in RSQM Section II, Attachment 11-3.2.5 Rancho Seco Quality Manual, Appendix A2.6 10 CFR 71.135, Quality Assurance Records2.7 10 CFR 72.174, Quality Assurance Records3.0 POLICYProcedures shall be established and implemented to ensure storage andmaintenance of records that represent evidence of activities described in RSQMSection II, Step 4.4.4.0 GENERAL REQUIREMENTS 4.1 Quality Assurance records shall be permanently stored in a facility thatmeets the requirements of Reference 2.4 and 2.5.4.2 Quality Assurance records shall be protected during interim storage inaccordance with Reference 2.4.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 64 OF 774.3 Documents that furnish evidence of the quality of items and services aregenerated and controlled in accordance with the procedures that governthose activities.

Such documents are considered Quality Assurance Records upon completion.

Quality Assurance Records are considered completed when they have been stamped, initialed, or signed and datedby authorized personnel or otherwise authenticated.

4.4 The record system shall provide for identification and retrievability of therecords to the extent that information can be obtained in a reasonable amount of time.4.5 The records program shall address records classification (retention period),

storage location and responsibility for retention and retrievability.

4.6 A records retention schedule shall be established which addresses therequirements in References 2.4 and 2.5.5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I,ORGAN IZATION5.1 Records Management is responsible for:a. Establishing methods for control of records.b. Providing administrative procedures that define the records storageprogram and provide for ready retrievability.

5.2 Rancho Seco management is responsible for:a. Transmitting completed records to Records Management.

b. Providing interim storage in accordance with Step 4.2 above andReference 2.4, prior to transmittal to Records Management.

5.3 Quality Assurance is responsible for auditing the records management system to ensure conformance to specified requirements per RSQMSection XVIII.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 65 OF 77XVIII. AUDITS1.0 PURPOSEDescribe the Rancho Seco Quality Assurance Program (QAP) measures that (1)establish a comprehensive system of planned and periodic audits, and (2)determine the effectiveness of the QAP at the Rancho Seco nuclear facility, which includes the Rancho Seco Nuclear Generating Station (RSNGS) licensedunder 10 CFR Part 50 and the Independent Spent Fuel Storage Installation (ISFSI) licensed under 10 CFR Part 72.2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XVIII, Audits2.2 Safety Guide 33/ANSI N18.7, Administrative Controls for Nuclear PowerPlants2.3 Regulatory Guide 1.144/ANSI N45.2.1 2-1977, Requirements for Auditing ofQuality Assurance Programs for Nuclear Power Plants2.4 Regulatory Guide 1.146/ANSI N45.2.23-1978, Qualification of QualityAssurance Program Audit Personnel for Nuclear Power Plants2.5 10 CFR 50.54(a),

Conditions of Licenses2.6 10 CFR 71.137, Audits2.7 10 CFR 72.176, Audits3.0 POLICYProcedures shall be established and implemented to ensure that planned andperiodic audits are conducted to verify compliance with all aspects of the QAP.4.0 GENERAL REQUIREMENTS 4.1 Quality Assurance shall establish a schedule for auditing the activities affecting quality.

The audit schedule shall be consistent with the auditrequirements and frequencies specified herein.4.2 The audit program shall be described in procedures that implement thisRSQM section.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 66 OF 774.3 Audits shall be conducted to determine the adequacy and effectiveness ofprograms implemented for the design, procurement, modification, maintenance, and operational activities at the Rancho Seco nuclearfacility.

4.4 Audit plans shall be developed that identify the audit scope, therequirements, activities to be audited, organizations to be notified, theapplicable documents, and the audit schedule.

4.5 Audit reports shall be issued which identify the activity that was audited,the personnel that were contacted during the audit, and any conditions adverse to quality noted during the audit.4.6 Process conditions identified as adverse to quality using the Rancho SecoCorrective Action Program.4.7 Personnel conducting audits shall be trained and qualified in accordance with Reference 2.4. In addition, at least one individual participating in theSecurity audit will be knowledgeable and practiced in the accessauthorization program performance objectives.

4.8 Regularly scheduled audits shall be supplemented by specialaudits/surveillances when conditions that warrant special audits exist orwhen requested by SMUD management.

5.0 RESPONSIBILITIES

General organizational responsibilities are described in Section I,ORGANIZATION.

5.1 Quality Assurance is responsible for:a. Establishing a schedule for performance of required audits.b. Reviewing audit results to evaluate the effectiveness of the QAP.c. Implementation of the established audit program.d. Training and qualification of audit personnel.

5.2 SMUD management is responsible for:a. Supporting the audit activities.

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2TITLE: RANCHO SECO QUALITY MANUAL PAGE 67 OF 77b. Providing prompt response to any deviations from quality identified in the audit.6.0 AUDITS AND AUDIT FREQUENCIES 6.1 Audits of Rancho Seco nuclear facility activities shall be performed underthe cognizance of the Quality Assurance organization which reports to theDirector, Audit Services (AS). The required audits and audit performance frequencies are as follows:a. Conformance to the Rancho Seco nuclear facility Technical Specifications and associated license conditions at least once peryear;b. Performance and qualifications of the Rancho Seco nuclear facilitytechnical staff at least once every two years;c. Actions taken to correct deficiencies occurring in facility structures,

systems, components, or methods of operation associated with thesafe operation of the Rancho Seco Independent Spent Fuel StorageInstallation (ISFSI) at least once every two years for those deficiencies not previously audited (Corrective Action Program audit);d. Performance of activities required by the QAP to meet the 10 CFR 50,Appendix B criteria at least once every five years;e. Rancho Seco nuclear facility Emergency Plan and implementing procedures at least once every two years;f. 10 CFR 72 ISFSI Physical Protection Plan and implementing procedures at least once every two years;g. Other areas of Rancho Seco nuclear facility operation that the siteManager considers appropriate;
h. Compliance with fire protection requirements and implementing procedures at least once every two years;i. Radiological Environmental Monitoring Program (REMP) and theresults thereof at least once every two years;j. Off-site Dose Calculation Manual (ODCM) and implementing procedures at least once every two years; RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 68 OF 77k. Process Control Program (PCP) and implementing procedures forprocessing and packaging of radioactive wastes from liquid systems atleast once every two years;I.Performance of activities required by the Quality Assurance Programfor Effluent Control and Environmental Monitoring (Regulatory Guide4.15) at least once every two years; andm. Radiation Protection Program content and implementation once peryear.6.2 Changes to these audits and audit frequencies are subject to the requirements contained in 10 CFR 50.54(a).

In addition, frequencies specified in 10 CFR andrelated to the performance of specific audits may not be changed unless anexemption or waiver is obtained from the NRC.6.3 The audit reports resulting from items "a" through "in" above shall be forwarded to the site Manager, the Director, Power Generation, and the management positions responsible for the areas reviewed.

The report should be issued within30 days after completion.

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2TITLE: PANCHO SECO QUALITY MANUAL PAGE 69 OF 77Appendix A1.0 10 CFR 50 ADMINISTRATIVE CONTROLS1.1 Technical Review and Controla. Procedures, plans, manuals, and programs required by Section 1.4 shall beprepared,

reviewed, and approved.

Each such procedure, plan, manual, andprogram or change thereto shall be reviewed by an individual(s) other than thepreparer, but who may be from the same organization as the preparer of theprocedure, plan, manual and program or change thereto.

Programs, plans,manuals, and procedures other than administrative procedures will beapproved as delineated in writing by the Site Manager, but not lower than adirect report to the Site Manager.

Such procedures, plans, manuals andprograms shall be reviewed periodically in accordance with administrative procedures.

The Site Manager will approve administrative procedures and Emergency PlanImplementing Procedures.

b. Proposed changes or modifications to systems or equipment described in theRADSAR shall be reviewed by an individual(s) other than the individual(s) whodesigned the modification, but who may be from the same organization as theindividual(s) who designed the modifications.

Such modifications shall beapproved by the Site Manager or his designee as delineated in writing, but notlower than a direct report to the Site Manager.c. Individual(s),

other than the individual(s) who prepare proposed tests orexperiments shall review proposed tests and experiments that are notaddressed in the RADSAR. Such tests or experiments shall be approved bythe Site Manager or his designee as delineated in writing, but not lower than adirect report to the Site Manager.d. Individuals responsible for reviews performed in accordance with Section 1.1 a,b, and c shall meet or exceed the qualification requirements of Section 4,"Qualifications,"

of ANSI N 18.1-1971, excluding Sections 4.5.2 "Technicians" and 4.5.3 "Repairmen."

The Site Manager shall establish the list of qualified reviewers for the independent reviews described in a, b, and c above.e. Events reportable pursuant to Section 1.5.5 and violations of Technical Specifications shall be investigated and a report prepared which evaluates theevent and which provides recommendations to prevent recurrence.

The SiteManager shall review these reports.

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 70 OF 771.2 Audits (See RSQM Section XVIIl)Specific audit requirements, including frequencies and administrative

controls, are addressed in Rancho Seco Quality Manual (RSQM)Section XVIII, "Audits."

1.3 Licensee Event Report ActionThe following actions shall be taken for events that are reportable as LicenseeEvent Reports:a. The Commission shall be notified and a report submitted per Section 1.5.5,pursuant to the requirements of 10 CFR 20.2203 and 50.73, andb. Each Licensee Event Report shall be reviewed and approved by the SiteManager or designee.

1.4 Procedures, Plans, Manuals, and Programs1.4.1 Written procedures, plans, manuals, and programs shall be established, implemented and maintained 1 covering the activities referenced below:a. The applicable procedures recommended in Appendix "A" of SafetyGuide 33, November 1972.b. Emergency Plan implementation.

c. Fire Protection Program Plan implementation.

-d. POP implementation.

e. ODCM implementation.
f. REMP MANUAL implementation.
g. Quality Assurance Program for Effluent Control and Environmental Monitoring using the guidance of Regulatory Guide 4.15, Revision 1,February 1979.h. Quality Assurance Program implementation.
g. Radiation Protection Program implementation.

1 Note: These procedures, plans, manuals, and programs may coexist within a single document.

RANCHO SECO LICENSING3 BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 71 OF 771.4.2 Each procedure, plan, manual, and program of Section 1.4.1 above andchanges thereto shall be reviewed and approved as set forth in Section1.1.1.4.3 The following programs shall be established, implemented, andmaintained:

1.4.3.1 Radioactive Effluent Controls ProaramThere are no longer any radioactive liquid or gaseous effluents discharged from the site. The Offsite Dose Calculation Manual(ODOM) has been reduced in scope and the associated administrative and implementing procedures have been deleted.

TheODCM will require that if radioactive effluents need to be released inthe future, a program must be implemented that meets therequirements in 10 CFR 50.36a, 20.1301, 20.1302, 10 CFR Part 50,Appendix I, and any other applicable regulations 1.4.3.2 Radioloqical Environmental Monitoringq Progqram (REMP)There are no longer any liquid or gaseous radioactive effluents discharged from the site. The radiation source term is limited toradioactive materials stored in the Interim Onsite Storage Building(IOSB) and the Independent Spent Fuel Storage Installation (ISFSI).Accordingly, the only exposure pathway is by direct radiation.

With the completion of the first phase of decommissioning, the directradiation pathway is the only pathway still monitored by the REMP.Accordingly, there is no longer any requirement to participate in anInter-laboratory Comparison Program (ICP). The vendor supplying the direct radiation monitoring devices must be certified under aNational Voluntary Laboratory Accreditation Program (NVLAP).

TheNational Institute of Standards and Technology (NI1ST) administers the NVLAP, which provides third-party accreditation to testing andcalibration laboratories.

1.4.4 The changes to the REMP shall be reviewed and approved as set forthin Sections 1.1 and 1.9.

RANCHO SECO LICEN;51NU L3A$IS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: PANCHO SECO QUALITY MANUAL PAGE 72 OF 771.5 Reporting Requirements 1.5.1 Routine ReportsIn addition to the applicable reporting requirements of Title 10, Code ofFederal Regulations, the following reports shall be submitted to the RegionalAdministrator of the Region IV Office unless otherwise noted.1.5.2 Annual Radiological ReportsAnnual reports covering the activities of the unit, as described below, for theprevious calendar year shall be submitted as follows:1.5.2.1 Annual Individual Monitoring Results ReportThe Annual Individual Monitoring Results Report for the previous calendaryear shall be submitted to the Commission by April 30 of each year incompliance with 10 CFR 20.2206.1.5.2.2 Annual Exposure ReportThe Annual Exposure Report for the previous calendar year shall besubmitted to the Commission within the first calendar quarter of eachcalendar year in accordance with the guidance contained in Regulatory Guide 1.16.1.5.2.3 Annual Radioloqical Environmental Operating ReportThe Annual Radiological Environmental Operating Report covering theoperation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The materialprovided shall be consistent with the objectives outlined in the REMPManual.1.5.3 Annual Radioactive Effluent Release ReportAlthough there are no longer any radioactive effluents discharged from thesite, the Annual Radioactive Effluent Release Report, covering the operation of the unit during the previous 12 months, shall be submitted within 90 daysafter January 1 of each year. The report will continue to be submitted until theNRC grants a specific exemption from 10 CFR 50.36a.

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 73 OF 771.5.4 Biennial ReportA routine report consisting of shutdown statistics, narrative summary ofshutdown experience, and tabulations of facility

changes, tests or, experiments required pursuant to 10 CFR 50.59(d) shall be submitted at intervals not toexceed 24 months to the U. S. Nuclear Regulatory Commission, DocumentControl Desk, Washington, D.C. 20555, with a copy to the Regional Office,postmarked no later than 30 days following the 24 month period covered by thereport.1.5.5 Licensee Event ReportThe types of events listed in 10 CFR 20.2203 and 50.73 shall be the subjectof Licensee Event Reports, submitted to the U.S. Nuclear Regulatory Commission (NRC), Document Control Desk, Washington, D.C. 20555, withinthe time requirements of 10 CFR 20.2203 and 50.73. An additional copy shallalso be submitted to the Regional Administrator of the Region IV Officel.

Thewritten report shall include a completed copy of a Licensee Event Reportform, pursuant to 10 CFR 20.2203, 50.73 and the guidance of NUREG-1022, and a description of corrective actions and measures to prevent recurrence.

Supplemental reports may be required to fully describe final resolution of theoccurrence.

For corrected or supplemental

reports, a Licensee Event Reportshall be completed and reference shall be made to the original report date,pursuant to the requirements of 10 CFR 20.2203 or 50.73, as appropriate.

1.5.6 Environmental Reportsa. When a change to the plant design or operation is planned which wouldhave a significant adverse effect on the environment or which involvesan environmental matter or question not previously reviewed andevaluated by the NRC, a report on the change will be made to the NRCprior to implementation.

The report will include a description andevaluation of the change, including a supporting benefit-cost analysis.

b. Changes or additions to permits and certificates required by Federal,State, local and regional authorities for the protection of the environment will be reported.

The request for permit and certificate changes oradditions submitted to the concerned agencies for approval will also besubmitted to the NRC. The submittal will be made for the reporting period during which the changes or additions occurred.

The submittal willinclude an evaluation of the environmental impact of the change(s).

RANCHO SECO LICENSING BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 74 OF 771.5.7 Special ReportsSpecial reports shall be submitted to the Regional Administrator of theRegion IV Office within the time period specified for each report.1.6 Record Retention 1.6.1 The following records shall be retained for the duration of the 10 CFR Part 50and 10 CFR Part 72 Operating Licenses:

a. Records and logs of facility operation covering time interval at eachpower level.b. Records and logs of principal maintenance activities, inspections, repair,and replacement of principal items of equipment related to NUCLEARSAFETY, as they relate to the 10 CFR Part 72 licensed facility.
c. Licensee Event Reports.d. Records of surveillance activities, inspections and calibrations requiredby these Technical Specifications.
e. Records of changes made to Operating Procedures, as they relate to the10 CFR Part 72 licensed facility.
f. Records of radioactive shipments.
g. Records of sealed source leak tests and results.h. Records of annual physical inventory of all sealed source materialof record.i. Records and logs of facility activities in the Permanently Defueled Mode.j. Record and drawing changes reflecting facility design modifications made to systems and equipment described in the Updated SafetyAnalysis Report.k. Records of new and irradiated fuel inventory, fuel transfers andassembly burn-up histories.

I. Records of facility radiation and contamination surveys.m. Records of radiation exposure for all individuals entering radiation control areas.

RANCHO SECO LICENSING~

BASIS DOCUMENT NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 75 OF 77n. Records of gaseous and liquid radioactive material released to theenvirons.

o. Records of training and qualification for current members of theoperating staff.p. Records of quality assurance activities required by the RSQM.q. Records of reviews performed for changes made to procedures orequipment or reviews of tests and experiments pursuant to10 CFR 50.59 and 10 CFR 72.48.r. Records of meetings of the Plant Review committee (PRC) andManagement Safety Review Committee (MSRC).s. Records for the Radiological Environmental Monitoring Program.t. Records of reviews performed for changes made to the ODCM, REMPMANUAL, and the PCP.u. Records of plant closure and decommissioning activities performed.

1.7 Radiation Protection ProgramProcedures for personnel radiation protection shall be prepared consistent with therequirements of 10 CFR 19 and 10 CFR 20, and shall be approved, maintained andadhered to for all operations involving personnel radiation exposure.

1.8 Process Control Program (PCP)Licensee-initiated changes to the POP:a.Shall be documented and records of reviews performed shall be retained asrequired by Section 1.6.1.t.

This documentation shall contain:

.. ...1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and2) A determination that the change will maintain the overall conformance ofthe processed waste product to existing requirements of Federal, State, orother applicable regulations.

I b.Shall become effective after approval by the Site Manager.

RANCHO SECU LlICNI-N5N(i LVUUMPN I NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 76 OF 771.9 Off-Site Dose Calculation and Radiological Environmental Monitoring Program ManualsLicensee-initiated changes to the ODCM or REMP Manual: shall be documented and records of reviews performed shall be retained as required by Section1.6.1 .t. This documentation shall contain sufficient information to support thechange together with the appropriate analyses or evaluations justifying thechange.Changes to the REMP become effective after approval by the Site Manager andwill be submitted to the Commission in the form of a complete, legible copy of theentire manual.1.10 Liquid Hold-up TanksThere are no longer any liquid hold-up tanks. Accordingly, this section has beendeleted.1.11 Sealed Source Contamination Each sealed source containing radioactive material either in excess of100 microcuries of beta and/or gamma emitting material or 5 microcuries of alphaemitting material shall be free of_> 0.005 microcuries of removable contamination.

Applicability:

At All TimesAction:With a sealed source having removable contamination in excess of the abovelimits, immediately withdraw the sealed source from use and:a. Either decontaminate and repair the sealed source, orb. -Dispose of the sealed source-in accordance with NRC Regulations.

Surveillance Requirements:

Test Requirements Each sealed source shall be tested for leakage and/or contamination by:a. The Licensee, orb. Other persons specifically authorized by the NRC or an Agreement State.

KANUHU. SI-W VU()UML-N I NUMBER: RSLBD-010 REVISION:

2TITLE: RANCHO SECO QUALITY MANUAL PAGE 77 OF 77The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.Test Freqiuencies Each category of sealed sources shall be tested at the frequency described below.a. For sources in use at least once every six months or all sealed sourcescontaining radioactive material:

1. With a half-life greater than 30 days (excluding Tritium),

and2. In any form other than gas.b. For stored sources not in use each sealed source shall be tested prior touse or transfer to another licensee unless tested within the previous sixmonths. Sealed sources transferred without a certificate indicating the lasttest date shall be tested prior to being placed into use.

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