ML17265A566

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Rev 26 to QA Program for Station Operation.
ML17265A566
Person / Time
Site: Ginna Constellation icon.png
Issue date: 03/01/1999
From:
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17265A565 List:
References
NUDOCS 9903100117
Download: ML17265A566 (6)


Text

Attachment 2 ROCHESTER GAS AND ELECTRIC CORPORATION R.E. GINNA NUCLEAR POWER PLANT Quality Assurance Program for Station Operation Revision 26 DOCKET NO. SO-244 March 1, 1999 W~GSZooa<7 eqosoa .

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TABLE 17.1.7-1 (cont'd)

Standard Re uirement or Guide Conformance Remarks Status Regulatory Guide 1.144 Rev.(1)-Auditing of Quality Alternate RG 1.144 Rev.(1) incorporates ANSI N45.2.12-1977. Ginna conforms to RG 1.144 Rev.(1)

Assurance Programs for Nuclear Power Plants and...AI'Igrblj$@"';:I@Ipyy,: with the foilowtoglexceptionsf dtal-a gmm period of 90 days may be applied to the perfo~mce of triennial supplier audits and annual supplier evaluations described in Section C.3.b.(2).

a:::s'chc'dn'Ic'4:."daI'e",:fo','ore rbitiroi'ictooit Regulatory Guide 1.146 Rev.(0)-Qualification of QA Alternate RG 1.146 Rev.(0) incorporates ANSI N45.2.23-1978. Ginna conforms to RG 1.146 Rev.(0)

Progratn Audit Personnel for Nuclear Power Plants and::,Affgl":::II4$%@g.:.".I 9+0:: with the fdliowlng'aexceptionst that-a grace period of 90 days may be applied to the performance of annual lead auditor recertifications described in Sections 3.2 and 5.3~of,":A'NSI"::F49","2.".,'23";:,f978.

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.jiia1i fIed.:,:,ti,;::,IeatI:.":audtts'-'inna Regulatory Guide 1.152 Rev.(0)-Criteria for Alternative conforms to Generic Letter 95-02, and its endorsement of NUMARC/EPRI Report TR-Programmable Digital Computer System Software in 102348 "Guidelines on Licensing Digital Upgrades".

Safety-Related Systems of Nuclear Power Plants Regulatory Guide 4.15 Rev.(1)-Quality Assurance Adopted Ginna conforms to the intent of this Regulatory Guide as addressed in the Process Control for Radiological Monitoring Program (Normal Program and applicable to Ginna effluent and environmental radioactivity measurements.

Operations)-Effluent Streams and the Environment RG&E QAPSO, Revision 26 March 1, 1999

Enclosure 1 ROCHESTER GAS AND ELECTRIC CORPORATION R.E. QINNA NUCLEAR POWER PLANT Quality Assurance Program for Station Operation Revision 26 DOCKET NO. 50-244 March 1, 1999

TABLE 17.1.7-1 (cont'd)

Standard Re uirement or Guide Conformance Remarks Status Regulatory Guide 1.39 Rev.(2)-Housekeeping Conforms RG 1.39 Rev.(2) incorporates ANSI N45.2.3-1973.

Requirements for Water-Cooled Nuclear Power Plants Regulatory Guide 1.54 Rev.(0)-Quality Assurance Alternative Quality assurance requirements apply only when a coating performs a safety related function Requirements for Protective Coatings Applied to instead of the provisions stated in this Regulatory Guide and its referenced standard, ANSI Water-Cooled Nuclear Power Plants N101.4-1972.

See the UFSAR for quality assurance requirements used for existing coatings. For new coatings and configuration changes to existing coatings, either the quality assurance requirements of the UFSAR or the quality assurance requirements of 10CFR50, Appendix B are used instead of the detailed requirements included in this Regulatory Guide.

Regulatory Guide 1.58 Rev.(1)-Qualification of Alternate RG 1.58 Rev.(1) incorporates ANSI N45.2.6-1978. Ginna conforms to Reg. Guide 1.58 Nuclear Power Plant Inspection, Examination, and Rev.(1) and ANSI N45.2.6-1978 with the following exceptions:

Testing Personnel A 90 day grace period may be applied to the performance of annual evaluations of inspection, examination and testing personnel qualifications defined in Section 2.3 of ANSI N45.2.6-1978.

RG&E's ISI Plan endorses ASME Code Section XI. The version of the ASME code endorsed is updated periodically. ASME Code Section XI references standards for the qualification and certification of nondestructive testing personnel.Section XI of the.ASME Code contains specific requirements for nondestructive examination and also references the use of other supplementary standards for the qualification and certification of personnel performing nondestructive examinations. The applicable versions of the standards referenced in Section XI of the ASME code, as permitted for use by 10 CFR Part 50.55a, may be used for the qualification and certification of personnel performing nondestructive examinations required by Section III and Section XI of the ASME Code in lieu of the standard identified in Reg. Guide 1.58, Rev. 1, (SNT-TC-lA-1975) provided that other applicable rules contained in Section XI of the ASME Code are met.

Regulatory Guide 1.64 Rev.(1)-Quality Assurance Conforms RG 1.64 Rev.(1) incorporates ANSI N45.2.11-1974.

Requirements for Design of Nuclear Power Plants RG&E QAPSO, Revision 26 March 1, 1999

TABLE 17.1.7-1 (cont'd)

Standard Re uirement or Guide Conformance Remarks Status Regulatory Guide 1.144 Rev.(l)-Auditing of Quality Alternate RG 1.144 Rev.(1) incorporates ANSI N45.2.12-1977. Ginna conforms to RG 1.144 Rev.(1)

Assurance Programs for Nuclear Power Plants and ANSI N45.2.12-1977 with the following exceptions:

~ a grace period of 90 days may be applied to the performance of triennial supplier audits and annual supplier evaluations described in Section C.3.b.(2).

~ In lieu of the 30 day requirement of Section 4.5.1 of ANSI N45.2.12-1977 the following is used: Corrective action response due dates and priority shall be based on safety significance. For audit findings that are determined to be significant conditions adverse to quality, the audited organization's response shall be provided within 30 days. In the event that the corrective action for an audit finding cannot be completed by the response due date, the audited organization's. response shall include a scheduled date for corrective action.

Regulatory Guide 1.146 Rev.(0)-Qualification of QA Alternate RG 1.146 Rev.(0) incorporates ANSI N45.2.23-1978. Ginna conforms to RG 1.146 Rev.(0)

Program Audit Personnel for Nuclear Power Plants and ANSI N45.2.23-1978 with the following exceptions:

~ a grace period of 90 days may be applied to the performance of annual lead auditor recertifications described in Sections 3.2 and 5.3 of ANSI N45.2.23-1978.

~ In lieu of the requirements of 2.3.4 of ANSI N45.2.23-1978 the following is used:

Prospective lead auditors shall demonstrate their ability to effectively implement the audit process and effectively lead an audit team. RG&E will describe this demonstration process in written procedures and shall evaluate and document the results of the demonstration. Regardless of the methods used for the demonstration, the prospective lead auditor shall have participated in at least one nuclear quality assurance audit within the year preceding the individual's effective date of qualification. Upon successful demonstration of the ability to effectively implement the audit process and effectively lead audits, and having met the other provisions of Section 2.3 of ANSI N45.2.23-1978, the individual may be certified as being qualified to lead audits.

Regulatory Guide 1.152 Rev.(0)-Criteria for Alternative Ginna conforms to Generic Letter 95-02, and its endorsement of NUMARC/EPRI Report TR-Programmable Digital Computer System Software in 102348 "Guidelines on Licensing Digital Upgrades".

Safety-Related Systems of Nuclear Power Plants Regulatory Guide 4.15 Rev.(1)-Quality Assurance Adopted Ginna conforms to the intent of this Regulatory Guide as addressed in the Process Control for Radiological Monitoring Program (Normal Program and applicable to Ginna effluent and environmental radioactivity measurements.

Operations)-Effluent Streams and the Environment RG&E QAPSO, Revision 26 March 1, 1999