ML031420132
| ML031420132 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/21/2003 |
| From: | Kuo P, Lanning W, Richards S NRC/NRR/DIPM/IIPB, Division of Reactor Safety I |
| To: | Kuo P, Modes M NRC/NRR/DRIP/RLEP, Division of Reactor Safety I |
| Wang HB, NRR/DRIP/RLEP, 415-2958 | |
| References | |
| Download: ML031420132 (7) | |
Text
MEMORANDUM TO: Pao-Tsin Kuo, Program Director License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Michael C. Modes, Senior Reactor Inspector Division of Reactor Safety Region I FROM:
Stuart A. Richards, Chief Inspection Program Branch Office of Nuclear Reactor Regulation Wayne D. Lanning, Director Division of Reactor Safety Region I
SUBJECT:
R. E. GINNA LICENSE RENEWAL INSPECTIONS Attached is the final version of the R. E. Ginna Nuclear Power Plant License Renewal Inspection Plan. The plan, which was developed jointly by NRR and Region I, is hereby approved. You are directed to use this plan to prepare and conduct the license renewal inspections at the R. E. Ginna Nuclear Power Plant.
/Original signed by/
Date: 5/21/03 Stuart A. Richards, Chief Inspection Program Branch Division of Inspection Program Management Office of Nuclear Reactor Regulation
/Original signed by PTKuo for/
Date: 5/21/03 Wayne D. Lanning, Director Division of Reactor Safety Region I Attachments: Ginna License Renewal Inspection Plan
MEMORANDUM TO: Pao-Tsin Kuo, Program Director License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Michael C. Modes, Senior Reactor Inspector Division of Reactor Safety Region I FROM:
Stuart A. Richards, Chief Inspection Program Branch Office of Nuclear Reactor Regulation Wayne D. Lanning, Director Division of Reactor Safety Region I
SUBJECT:
R. E. GINNA LICENSE RENEWAL INSPECTIONS Attached is the final version of the R. E. Ginna Nuclear Power Plant License Renewal Inspection Plan. The plan, which was developed jointly by NRR and Region I, is hereby approved. You are directed to use this plan to prepare and conduct the license renewal inspections at the R. E. Ginna Nuclear Power Plant.
/Original signed by/
Date: 5/21/03 Stuart A. Richards, Chief Inspection Program Branch Division of Inspection Program Management Office of Nuclear Reactor Regulation
/Original signed by PTKuo for/
Date: 5/21/03 Wayne D. Lanning, Directo Division of Reactor Safety Region I Attachments: Ginna License Renewal Inspection Plan Distribution: See next page
- See previous concurrence DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML031420132.wpd OFFICE LA:RLEP:DRIP PM:RLEP:DRIP SC:RLEP:DRIP NAME Y Edmonds (ltr only)
H Wang S Lee DATE 5/ 14/03 5/ 1/03*
5/16/03 OFFICE TL:RI D:DRS:RI BC:IIPB:DIPM NAME M. Modes W Lanning (e-mail)
S Richards 5/20/03 5/21/03 5/21/03 OFFICIAL RECORD COPY
DISTRIBUTION: Ginna License Renewal Inspection, Dated: May 21, 2003 HARD COPY RLEP RF R. Arrighi H. Wang
R. E. Ginna Nuclear Power Plant LICENSE RENEWAL INSPECTION PLAN I
PURPOSE This inspection plan specifies methods for implementing Manual Chapter 2516 requirements for activities relating to 10 CFR Part 54 (herein after referred to as the rule) and the R. E. Ginna Nuclear Power Plant (Ginna Station) license renewal inspection program. This plan defines the scope of the inspections planned to verify that Ginna Stations license renewal program is in compliance with the requirements of the rule and is consistent with Rochester Gas and Electric Corporations (RG&Es) license renewal application (LRA) and the staffs safety evaluation of RG&Es LRA. The plan also provides guidance for inspection scheduling, inspector training, inspection activities, and resource requirements.
RG&Es LRA identified the systems and structures that RG&E determined were within the scope of the rule. Page 4 of this document lists the systems and structures selected for this inspection. The inspection team chose the items, after reviewing the scoping results provided in Ginna Stations LRA, on the basis of their risk significance, uniqueness to Ginna Station, and current issues. The scope and depth of inspections of these systems and structures may vary.
II OBJECTIVES The overall objective of this plan is to provide guidance for inspecting the implementation and effectiveness of the programs and activities associated with RG&Es license renewal program.
The inspection will verify that there is reasonable assurance that the effects of aging will be adequately managed so that the intended function(s) of structures, and components (SCs), for which an aging management review is required, will be maintained consistent with the current licensing basis (CLB) during the period of extended operation. Region I will implement the license renewal inspection plan (LRIP) at Ginna Station before NRR approves RG&Es LRA to verify that RG&E meets the requirements of the rule and has implemented license renewal programs and activities consistent with the rule, the LRA, and the staffs safety evaluation report (SER) on the LRA.
III INSPECTION ACTIVITIES Inspection Procedure (IP) 71002, License Renewal Inspections, will be the primary procedure used to inspect RG&Es implementation of the requirements of the rule. The latest revision of IP 71002 can be reviewed by accessing http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/ip71002.pdf 1.
The systems and structures groups to be inspected are identified in Page 4 of this plan.
The selection of these systems and structures is based on risk significance and the importance of the safety function performed. The inspection team will verify that RG&E has implemented the scoping and screening process consistent with the rule and RG&Es methodology, as described in the LRA submitted by letter dated July 30, 2002.
The inspection team will also inspect a sample of the systems and structures that RG&E Attachment
2 concluded were not within the scope of the rule, in order to verify that there is reasonable assurance that all systems and structures within the scope of 10 CFR 54.4 have been identified.
2.
The implementation of the screening activities required under 10 CFR 54.21(a)(1) will be inspected by reviewing system boundaries on plant drawings, intended functions, and the active/passive and short-/long-lived characteristics of the SCs listed in Page 4, within the scope of RG&Es aging management review.
3.
The inspection team will also walk down accessible portions of the systems and structures to identify any observable inconsistencies in the scoping and screening activities and any aging effects on the systems and structures that are not covered in the LRA. Aging effects identified by RG&E will be reviewed and evaluated during the NRR technical review. The inspection team will perform a sample audit of related maintenance records of the systems and structures listed in Page 4 to attempt to identify any previously unrecognized aging.
4.
The inspection team will inspect the aging management programs (AMPs), including AMPs where RG&E claims they are consistent with the Generic Aging Lessons Learned (GALL) report, for approximately half of the aging effects in each of the systems and structures listed in Enclosure. The inspection team will examine records for existing aging management programs to evaluate the programs effectiveness and will review plans for new aging management programs. The inspection team will then document its findings on the effectiveness of the aging management programs to maintain the systems and structures intended function(s) consistent with the CLB for the period of extended operation.
IV INSPECTION SCOPE The Ginna Station license renewal inspection activities will be implemented through two or more site inspections.
1.
The first inspection will last one week, or longer if necessary, and focus on the scoping and screening processes to verify that they have been implemented consistent with the rule, RG&Es methodology, and the staffs safety evaluation of RG&Es methodology.
This inspection should be performed after the staff has completed its safety evaluation of the scoping and screening methodology, but before the SER is issued. The inspection will verify that there is reasonable assurance that RG&Es scoping and screening processes have identified all of the systems, structures, and components for which an aging management review is required consistent with the requirements of the rule.
2.
In the second inspection, the team will spend one week at the site, return to the region for one week to review documents, begin to write the inspection report, adjust the inspection plan, if needed, and go back to the site for another week. This inspection will examine existing and proposed aging management programs and past results. To support the NRR review process, the report for the second inspection will be issued before the SER with open items is issued.
3 2.
If the regional administrator decides that the open inspection items from the first two inspections warrant a third inspection, the team will followup on previous inspection activities and inspect RG&E actions on any SER open items requested by NRR. This inspection will also focus on any portion of the LRA updated by the applicant as a result of recent plant modifications. The third inspection report will document the need for any future follow-up inspections.
V INSPECTION RESOURCES The inspection will need the following inspection resources:
1.
Inspectors
One team leader
Three inspectors from the region
One or more participants from the program office 2.
Skills The inspection team needs a cross-section of skills, including mechanical, material, civil/structural, and electrical engineering skills.
The scope of the third inspection (and, thus, the resources) will depend on how many open issues remain from the previous inspection activities.
4 SYSTEMS AND STRUCTURES SELECTED FOR INSPECTION SYSTEMS OR STRUCTURES WITHIN SCOPE Mechanical Systems Reactor Coolant, Core, and Internals Yes Non-Class 1 RCS Components Yes Containment Hydrogen Detectors and Recombiners Yes Containment Isolation Components Yes Containment Spray Yes Residual Heat Removal Yes Safety Injection Yes Chemical and Volume Control Yes Chilled Water No Component Cooling Water Yes Containment Ventilation Systems Yes Emergency Power Yes Fire Protection Yes Fuel Handling No Plant Air Systems No Service Water Yes Auxiliary Feedwater Yes Feedwater and Condensate Yes Main and Auxiliary Steam Yes Structures and Structural Components Auxiliary Building Yes Cable Tunnel Yes Component Supports Commodity Group Yes Containment Structures Yes Control Building Yes Diesel Building Yes Essential Buildings and Yard Structures Yes Essential Yard Structures Yes Intermediate Building Yes Non-Essential Buildings and Yard Structures No Screen House Building Yes Service Building Yes Standby Auxiliary Feedwater Building Yes Turbine Building Yes Electrical Components 120 VAC Vital Instrument Buses Yes 125 VDC Power Yes 4160 VAC Power Yes 480 VAC Power Yes Control Rod Drive and Process Instruments Yes Engineered Safety Features Actuation Yes Offsite Power Yes Plant Security No Reactor Protection Yes