ML032820142

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Appendix a - Commitment Table (1).wpd - Safety Evaluation Report with Open Items Related to the License Renewal of the R.E. Ginna Nuclear Power Plant
ML032820142
Person / Time
Site: Ginna Constellation icon.png
Issue date: 10/31/2003
From: Kuo P
NRC/NRR/DRIP/RLEP
To: Mecredy R
Rochester Gas & Electric Corp
Kuo PT, NRR/DRIP/RLEP, 415-1183
Shared Package
ML032820021 List:
References
Download: ML032820142 (3)


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A-1 Appendix A Commitment Listing During the review of the Ginna License Renewal Application by the NRC staff, the applicant made commitments to provide aging management programs to manage the aging effects of structures and components prior to the extended period of operation, as well as other information. The following table lists these commitments, along with the implementation schedule and the location of the commitment.

ITEM NUMBER COMMITMENT IMPLEMENTATION SCHEDULE SOURCE 1

Submit new pressure-temperature limit curves.

December 2004 LRA Section 4.2.2; Letter 7/30/2002 and Letter 7/30/2003 2

Implement a Fatigue Monitoring Program to confirm that the number of operating cycles (causing fatigue) are fewer than the plant design cycles.

June 2004 LRA Section 4.3.1; Letter 7/30/2002 and Letter 7/30/2003 3

Provide an assessment of fatigue usage for nuclear sampling system B.31.1 piping, for the period of extended operation.

Completed LRA Section 4.3.2; Letter 7/30/2002 and Letter 7/30/2003 4

Provide a baseline NDE for the pressurizer surge line by inspecting all circumferential welds, and develop a methodology to employ NRC-approved augmented ISI for pressurizer surge line, or recalculate to determine acceptable CUF, or repair/replace surge line or subcomponents as necessary.

Completed reanalysis LRA Section 4.3.7; Letter 7/30/2002 and Letter 7/30/2003 5

Complete EQ calculations to extend the qualified life of EQ components from 40 to 60 years, for those components using TLAA criteria of 10 CFR 54.21 (c)(ii).

December 2004 LRA Section 4.4; Letter 7/30/2002 and Letter 7/30/2003

A-2 6

Retension 23 containment tendons as part of the 2005 tendon testing tendon program.

May 2005 LRA Section 4.5; Letter 7/30/2002 and Letter 7/30/2003 7

Perform one-time inspections of selected plant equipment to verify that current plant aging management programs are effective in managing the effects of aging.

Prior to September 2009 LRA Sections B.2.1.1; B.2.1.7; and B.2.1.21; Letter 7/30/2002 and Letter 7/30/2003 8

Enhance the Boric Acid Corrosion Surveillance program to include all susceptible components (e.g.,

carbon/low alloy steel, copper) potentially exposed to boric acid leaks.

Completed LRA Section B.2.1.6; Letter 7/30/2002 and Letter 7/30/2003 9

Develop a program to periodically assess the condition of non-EQ cables in adverse localized environments.

Completed LRA Section B.2.1.11; Letter 7/30/2002 and Letter 7/30/2003 10 Replace or test a representative sample of fire water system sprinklers that have been in service for up to 50 years.

Prior to 2016 LRA Section B.2.1.14; Letter 7/30/2002 and Letter 7/30/2003 11 Develop a reactor vessel head penetration inspection program, in concert with industry initiatives.

Ongoing initiative with NEI and MRP LRA Section B.2.1.26; Letter 7/30/2002 and Letter 7/30/2003 12 Participate with industry in helping to develop augmented inspection techniques to detect fine cracks and other changes in dimension in non-bolted components of the reactor vessel internals.

Ongoing initiative with NEI and MRP LRA Section B.2.1.27; Letter 7/30/2002 and Letter 7/30/2003 13 Enhance Structural Monitoring Program to include all structures within the scope of license renewal, and provide additional guidance for detecting aging effects.

Completed LRA Section B.2.1.32; Letter 7/30/2002 and Letter 7/30/2003

A-3 14 Enhance Systems Monitoring Program to include all systems within the scope of license renewal, and provide additional guidance for detecting aging effects.

June 2004 LRA Section B.2.1.33; Letter 7/30/2002 and Letter 7/30/2003 15 Add the house heating boiler and associated components in screen house as requiring aging management review.

Prior to September 2009 Response to F-RAI 2.1 -4; Letter 5/13/2003 16 Locations judged to be potentially susceptible to thermal fatigue will be included in the sample population of small bore piping to be examined by appropriate volumetric technique.

Prior to September 2009.

Response to F-RAI 3.2.1 -1.

Letter 5/13/2003 17 The pressurizer manway stainless steel insert will receive a visual and surface examination as part of the applicants ISI program to detect potential stress-corrosion cracking.

Prior to September 2009 Response to F-RAI 3.2.2 -5; Letter 5/13/2003 18 Add System Monitoring as an aging management program applicable to the pipe represented by Table 3.4-2, line number (42)

Prior to September 2009 Response to F-RAI 3.3 -2.

Letter 5/27/2003 19 Develop an engineering guidance document that will direct inspections to evaluate galvanic corrosion at susceptible locations in a raw (service) water environment.

Prior to September 2009 Response to F-RAI 3.5 -8; Letter 5/27/2003 20 Develop an aging management program basis document to periodically measure insulation resistance of nuclear instrumentation system (NIS) and high range radiation monitoring (HRRM) circuits Prior to September 2009 Response to F-RAI 3.7 -3; Letter 6/10/2003

A-4 21 Modify technical specifications to incorporate specific particulate testing requirements for diesel generator fuel oil, and eliminate use of ASTM D4176 Prior to September 2009 Response to C-RAI B2.1.16 -1; Letter 6/10/2003 22 Thermographic inspections of 34.5 kV transformer yard components are to be performed at least once per refueling cycle while the components are energized.

Prior to September 2009 Response to C-RAI 3.7 -6(a);

Letter 7/16/2003 23 Perform visual inspections and UT thickness measurements of the containment liner during 2005 RFO.

2005 RFO Response to C-RAI B2.1.3 -3; Letter 7/16/2003 24 Perform hardness tests, if feasible, on EDG jacket water coolers and lube oil coolers channel heads.

2003 RFO Response to C-RAI B2.1.29; Letter 7/16/2003 25 Perform visual inspections of phase bus.

Prior to 2012 Response to C-RAI 3.7-5; Letter 7/16/2003 26 Revise surveillance capsule withdrawal schedule and implement operating restrictions when capsule is withdrawn.

RFO 2005 RFO 2009 Response to C-RAI 4.2 -1; Letter dated 7/30/2003 27 Perform two SITs at design pressure during period of extended operation.

20092029 Response to C-RAI 3.6-1; Letter dated 7/30/2003 28 Reexamine liner and restore thickness if below acceptance criteria.

2005 Response to C-RAI B2.1.3-3(1);

Letter dated 7/30/2003

A-5 29 Include measurement of voltage between reference cells and rock anchors into PSPM program.

Prior to 2005 Response to C-RAI 3.5-8; Letter dated 7/30/2003 30 Define selection criteria, sample size, and periodicity of inspections for fire system piping Prior to September 2009 Response to AMP audit finding; Letter dated 9/16/03 31 Submit Reactor Vessel Internals Program for review and approval.

Prior to September 2009 Response to RAI B2.1.27-2; Letter dated 9/16/03