05000317/FIN-2014003-01: Difference between revisions
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| identified by = NRC | | identified by = NRC | ||
| Inspection procedure = IP 71111.04 | | Inspection procedure = IP 71111.04 | ||
| Inspector = S Kennedy, T O,' | | Inspector = S Kennedy, T O, 'Haraa Rosebrook, D Orr, D Schroeder, E Torres, H. Anagnostopoulus, R Clagg, S Barra, Rosebrookb Fuller, D Schroeder, E Burket, E Torres, G Callaway, J Nicholson, P Presby, R Clagg, S Stewart | ||
| CCA = N/A for ROP | | CCA = N/A for ROP | ||
| INPO aspect = | | INPO aspect = | ||
| description = An unresolved item (URI) was identified by the inspectors relating to an issue regarding the failure of Exelon to scope main steam line drains (MSLDs) and CIVs motor operated valves (MOVs) (6611, 6612, 6613, 6615, 6620, and 6621) into their inservice testing (IST) program. Description: The inspectors identified an issue of concern involving Exelons scoping of MSLD MOVs into the IST program. The MSLD MOVs are normally open valves with the ability to be remotely-operated from the main control room. The MSLD MOVs are classified as CIVs per UFSAR, Figure 5-10, Containment Structure Isolation Valve Arrangement, Sheet 24 and 25. This figure classifies the main steam penetrations as Type III, and requires the valves to be closed to perform their CIV function. UFSAR, Section 5.2, Isolation System, Subsection 5.2.2, System Design, defines a Type III penetration as a line not directly connected to the reactor coolant system (RCS) or the containment structure atmosphere that has at least one valve, either a check valve or a remotely-operated valve, outside of the containment structure. These valves are classified as American Society of Mechanical Engineers (ASME) Code, Class 2, per drawing 60740, Sheet 0001, Steam Line Drainage System, Revision 39, and M-601, Piping Class Summary Sheets, Revision 49. The ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) 2004, Subsection ISTA, General Requirements, Section ISTA-1100, Scope, states in part, Section IST establishes the requirements for pre-service and IST and examination of certain components to assess their operational readiness in light-water reactor nuclear power plants. These requirements apply to: a) pumps and valves that are required to perform a specific function in shutting down the reactor to the safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the consequences of an accident. 10 CFR 50.55a(f)(1), Codes and Standards, requires the establishment of OM Code IST test requirements to components which are classified ASME Code Class 1, 2 and 3. The inspectors require additional information from Exelon to determine if there is a performance deficiency which is more than minor. Specifically, the revision to calculation CA06453, Steam Generator Tube Rupture Accident Using Source Terms; calculation referenced in April 6, 1988, memo from D. S. Elkins to B. B. Mrowca, Impact of the Main Steam Drain Line on the 10CFR100 Limits of the Steam Generator Event; and for CCNPP to research which standard for the design of CIVs the plant was licensed to (equivalent to ANSI N271-1976, Containment Isolation Provisions for Fluid Systems.) The issue is identified as (URI 05000317/318/2014003-01, Main Steam Line Drain Containment Isolation Valves not Scoped in In-Service Testing Program.) | | description = An unresolved item (URI) was identified by the inspectors relating to an issue regarding the failure of Exelon to scope main steam line drains (MSLDs) and CIVs motor operated valves (MOVs) (6611, 6612, 6613, 6615, 6620, and 6621) into their inservice testing (IST) program. Description: The inspectors identified an issue of concern involving Exelons scoping of MSLD MOVs into the IST program. The MSLD MOVs are normally open valves with the ability to be remotely-operated from the main control room. The MSLD MOVs are classified as CIVs per UFSAR, Figure 5-10, Containment Structure Isolation Valve Arrangement, Sheet 24 and 25. This figure classifies the main steam penetrations as Type III, and requires the valves to be closed to perform their CIV function. UFSAR, Section 5.2, Isolation System, Subsection 5.2.2, System Design, defines a Type III penetration as a line not directly connected to the reactor coolant system (RCS) or the containment structure atmosphere that has at least one valve, either a check valve or a remotely-operated valve, outside of the containment structure. These valves are classified as American Society of Mechanical Engineers (ASME) Code, Class 2, per drawing 60740, Sheet 0001, Steam Line Drainage System, Revision 39, and M-601, Piping Class Summary Sheets, Revision 49. The ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) 2004, Subsection ISTA, General Requirements, Section ISTA-1100, Scope, states in part, Section IST establishes the requirements for pre-service and IST and examination of certain components to assess their operational readiness in light-water reactor nuclear power plants. These requirements apply to: a) pumps and valves that are required to perform a specific function in shutting down the reactor to the safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the consequences of an accident. 10 CFR 50.55a(f)(1), Codes and Standards, requires the establishment of OM Code IST test requirements to components which are classified ASME Code Class 1, 2 and 3. The inspectors require additional information from Exelon to determine if there is a performance deficiency which is more than minor. Specifically, the revision to calculation CA06453, Steam Generator Tube Rupture Accident Using Source Terms; calculation referenced in April 6, 1988, memo from D. S. Elkins to B. B. Mrowca, Impact of the Main Steam Drain Line on the 10CFR100 Limits of the Steam Generator Event; and for CCNPP to research which standard for the design of CIVs the plant was licensed to (equivalent to ANSI N271-1976, Containment Isolation Provisions for Fluid Systems.) The issue is identified as (URI 05000317/318/2014003-01, Main Steam Line Drain Containment Isolation Valves not Scoped in In-Service Testing Program.) | ||
}} | }} | ||
Revision as of 20:50, 20 February 2018
| Site: | Calvert Cliffs  |
|---|---|
| Report | IR 05000317/2014003 Section 1R04 |
| Date counted | Jun 30, 2014 (2014Q2) |
| Type: | URI: |
| cornerstone | Mitigating Systems |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 71111.04 |
| Inspectors (proximate) | S Kennedy T O 'Haraa Rosebrook D Orr D Schroeder E Torres H. Anagnostopoulus R Clagg S Barra Rosebrookb Fuller D Schroeder E Burket E Torres G Callaway J Nicholson P Presby R Clagg S Stewart |
| INPO aspect | |
| ' | |