GNRO-2014/00074, License Renewal Application 2014 Annual Update
| ML14301A102 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 10/27/2014 |
| From: | Kevin Mulligan Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GNRO-2014/00074 | |
| Download: ML14301A102 (11) | |
Text
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~Entergy Entergy Operations, Inc.
P. O. Box 756 Port Gibson, MS 39150 Kevin Mulligan Vice President, Operations Grand Gulf Nuclear Station Tel. (601) 437-7500 GNRO-2014/00074 October 27,2014 u.s. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
License Renewal Application 2014 Annual Update Gr~nd Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29
REFERENCE:
Letter to Nuclear Regulatory Commission, "License Renewal Application Grand Gulf Nuclear Station, Unit 1," dated October 28, 2011 (GNRO-2011/00093)
Dear Sir or Madam:
The purpose of this letter is to provide the Nuclear Regulatory Commission (NRC) an annual update to the referenced Grand Gulf Nuclear Station (GGNS) License Renewal Application (LRA), in accordance with 10 CFR 54.21 (b). During NRC review of the GGNS LRA, GGNS is required by 10 CFR 54.21 (b) to provide an annual report of changes to the GGNS current licensing basis (CLB) that materially affects the contents of the GGNS LRA, including the Final Safety Analysis Report supplement. GGNShas completed the annual CLB review and is providing, in the Attachment, the changes to the LRA required by this review.
If you have any questions or require additional information, please contact James Nadeau at 601-437-2103.
I declare under penalty of perjury that the foregoing is true and correct. Executed on th~ 27th day of October, 2014.
Sincerely,
~""~......._---
KJM/ras
GNRO-2014/00074 Page 2 of 2
Attachment:
Current License Basis Changes to the License Renewal Application cc: with Attachment and Enclosures u.s. Nuclear Regulatory Commission ATIN: Mr. John Daily, NRRlDLR Mail Stop OWFN/11 F1 11555 Rockville Pike Rockville, MD 20852-2378 cc: without Attachment and Enclosures u.S. Nuclear Regulatory Commission ATIN:Mr. Mark Dapas Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 1600 East Lamar Boulevard Arlington, TX 76011-4511 U.S. Nuclear Regulatory Commission ATTN: Mr. A. Wang, NRR/DORL Mail Stop OWFN/8 G14 11555 Rockville Pike Rockville, MD 20852-2378 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150
- Attachment to GNRO-2014/00074 Current License Basis Changes to the License Renewal Application
Attachment to GNRO-2014/00074 Page 1 of 8 The following changes are made to the GGNS License Renewal Application. All changes are shown with strikethroughs for deletions and underlines for additions. Affected LRA page numbers are shown in ( ).
2."2 Plant Level Seoping Results (Page 2.2-9)
Table 2.2-1-8 Plant EIC Systems within the Scope of License Renewal System Code System Name UFSAR Reference H22 Local tnstrumentand Racks None (Page 2.2-12)
Table 2.2-2 Mechanical Systems Not within the Scope of License Renewal System Code System Name UFSAR Reference H22
- Localtnstrument and Racks None
- H22 IS mostly an EtC system but has a few mechanical components, none of which have a license renewal intended function.
2.3.2.2 Low Pressure Core Spray The LPCS system has the followingoo intended functions for 10 CFR 54.4(a)(3).
Perform a function (isolates LPCS) that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48).
Components Subject to Aging Management Review ASME Class 1 components with the intended function§. of maintaining the reactor coolant pressure boundary and supporting an intended function for fire protection are reviewed in Section 2.3.1.2, Reactor Coolant Pressure ,Boundary. The spray header internal to the reactor vessel is reviewed in Section 2.3.1.1.2, Reactor Vessel Internals. Nonsafety-related components of the system whose failure could prevent satisfactory accomplishment of safety functions [10 CFR 54.4(a)(2)] not included in other reviews are reviewed in Section 2.3.2.8,
Attachment to GNRO-2014/00074 Page 2 of 8 Miscellaneous ESF Systems in Scope for 10 CFR 54.4(a)(2). Remaining LPCS components are reviewed as listed below.
2.3.2.3 High Pressure Core Spray The HPCS system has the followingAe intended functions for 10 CFR 54.4(a)(3).
Perform a function (isolates HPCS) that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48).
Components Subject to Aging Management Review The spray sparger and piping inside the vessel are reviewed in Section 2.3.1.1.2, Reactor Vessel Internals. Class 1 components with the intended function§ of maintaining the reactor coolant pressure boundary and supporting an intended function for fire protection are reviewed in Section 2.3.1.2, Reactor Coolant Pressure Boundary. A limited number of components supporting condensate storage tank level instruments are reviewed in Section 2.3.4.1, Condensate and Refueling Water Storage and Transfer. Nonsafety-related components of the system whose failure could prevent satisfactory accomplishment of safety functions not reviewed in other sections are reviewed in Section 2.3.2.8, Miscellaneous ESF Systems in Scope for 10 CFR 54.4(a)(2). Remaining HPCS system components are reviewed as listed below.
2.3.3.1 Control Rod Drive The CRD system has the following intended function§ for 10 CFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commission's regulations for anticipated transient without scram (ATWS) (10 CFR 50.62) (ARI function).
Perform a function (assure fail-safe operation of CRD hydraulic system) that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48).
UFSAR References Section 4.6.1.1 Components Subject to Aging Management Review The control rod drive mechanisms (part of system B13) are Class 1 components supporting the reactor coolant pressure boundary and are reviewed in Section 2.3.1.2, Reactor Coolant Pressure Boundary. Nonsafety-related components of the system whose failure could prevent satisfactory accomplishment of safety functions [1 0 CFR 54.4(a)(2)] not included in other reviews are reviewed in Section 2.3.3.19, Miscellaneous Auxiliary,Systems in Scope for 10 CFR 54.4(a)(2). Components that support the intended function for fire protection are reviewed in Section 2.3.3.19.
Attachment to GNRO-2014/00074 Page 3 of 8 2.3.3.2 Standby Liquid Control The SLC system has the following intended function§. for 10 CFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commission's regulations for anticipated transient without scram (ATWS) (10 CFR 50.62).
Perform a function (prevents reverse flow into SLC) that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48).
Components Subject to Aging Management Review ASME Class 1 components with the intended functions of maintaining the reactor coolant pressure boundary and supporting an intended function for fire protection are reviewed in Section 2.3.1.2, Reactor Coolant Pressure Boundary. Nonsafety-related components of the system whose failure could prevent satisfactory accomplishment of safety functions [10 CFR 54.4(a)(2)] not included in other reviews are reviewed in Section 2.3.3.19, Miscellaneous Auxiliary Systems in Scope for 10 CFR 54.4(a)(2).
2.3.3.3 Suppression Pool Makeup The SPMU system has no intended functions for 10 CFR 54.4(a)(2) or (a)(3).
The SPMU system has the followingRG intended functions for 10 CFR 54.4(a)(3).
Perform a function (support pool level instrumentation isolation) that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48).
2.3.3.4 Leakage Detection and Control Main Steam Isolation Valve Leakage Control System The MSIV-LCS system has the followingRG intended functions for 10 CFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48).
Attachment to GNRO-2014/00074 Page 4 of 8 Components Subject to Aging Management Review Class 1 components supporting the reactor coolant pressure boundary and an intended function for fire protection are reviewed in Section 2.3.1.2, Reactor Coolant Pressure Boundary. A small number of leak detection system components are evaluated in Section 2.3.3.6, Fuel Pool Cooling and Cleanup. Nonsafety-related components of the leak detection system and the MSIV-LCS systems whose failure could prevent satisfactory accomplishment of safety functions not reviewed in other sections are reviewed in Section 2.3.3.19, Miscellaneous Auxiliary Systems in Scope for 10 CFR 54.4(a)(2) 2.3.3.8 Component Cooling Water The CCW system has AG-the following intended functions for 10 CFR 54.4(a)(3).
Perform a function (isolation of CCW from SSW) that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48).
2.3.3.9 Plant Service Water The PSW system has AG-the following intended functions for 10 CFR 54.4(a)(3).
Perform a function (isolation of CCW from PSW) that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48).
Components Subject to Aging Management Review Nonsafety-related components of the system whose failure could prevent satisfactory accomplishment of safety functions [10 CFR 54.4(a)(2)] not included in other reviews are reviewed in Section 2.3.3.19, Miscellaneous Auxiliary Systems in Scope for 10 CFR 54.4(a)(2).
Nonsafety-related components that support the intended function (SW to PSW cross-tie isolation) for fire protection are reviewed in Section 2.3.3.19. Remaining PSW components are reviewed as listed below.
2.3.3.17 Control Room Heating, Ventilation and Air Conditioning The CR HVAC system has AG-the following intended functions for 10 CFR 54.4(a)(3).
Perform a function that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48).
Attachment to GNRO-2014/00074 Page 5 of 8 2.3.3.19 Miscellaneous Auxiliary Systems in Scope for 10 CFR 54.4(a)(2)
(Page 2.3-64)
System Description
The following systems within the scope of license renewal based on the criterion of 10 CFR 54.4(a)(2) are not described elsewhere in the application. Each system has the following intended function.
Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function.
The systems described below have components that support this intended function. For systems with intended functions that meet additional scoping criteria, the other intended functions are noted in the descriptions below with a reference to the section where the affected components are evaluated (e.g., Section 2.3.2.7, Containment Penetrations for primary containment penetrations). Of the systems described below, only reactor water cleanup has an intended function for 10 CFR 54.4(a)(3).
(Page 2.3-66 Section 2~3.3.19)
Reactor Water Cleanup The RWCU system has the following intended function for 10 CFR 54.4(a)(3).
- Perform a function (isolate reactor coolant blowdown to the condenser and isolate the RWCU filter/demineralizer from the RCPS) that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48).
2.3.4.2 Miscellaneous Steam and Power Conversion Systems in Scope for 10 CFR 54.4(a)(2)
(Page 2.3-214)
System Description
Attachment to GNRO-2014/00074 Page 6 of 8 The following systems within the scope of license renewal based on the criterion of 10 CFR 54.4(a)(2) are not described elsewhere in the application. Each system has the following intended function.
- Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function.
The systems described below have components that support this intended function. For systems with intended functions that meet additional scoping criteria, the other intended functions are noted in the descriptions below with a reference to the section where the affected components are evaluated (e.g., Section 2.3.2.7, Containment Penetrations for primary containment penetrations). None of these systems has an intended function for 10 CFR 54.4 (a)(3).
(Page 2.3-216)
Condensate and Feedwat(Jr In addition to its intended function for 10 CFR 54.4(a)(2), the condensate and feedwater system has the following intended function for 10 CFR 54.4(a)(3).
- Perform a function (isolate feedwater system) that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48).
Components supporting the intended function for fire protection are reviewed in Section 2.3.4.2.
Condensate Cleanup In addition to its intended function for 10 CFR 54.4(a)(2}, the condensate system has the following intended function for 10 CFR 54.4(a)(3).
- Perform a function (isolates flow to the precoat filters) that demonstrates compliance with the Commission's regulations for fire protection (10CFR 50.48).
Components supporting the intended function for fire protection are reviewed in Section 2.3.4.2.
Attachment to GNRO-2014/00074 Page 7 of 8 Table 3.4.2-2-16 Condenser Air RemovaI System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.4.2-2-16: Condenser Air Removal System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging Component Intended Requiring Management NUREG- Table 1 Type Function Material Environment Management Program 1801 Item Item Notes Valve body Pressure Stainless steel Air - indoor (ext) None None VIII.I.SP-12 3.4.1-58 8-boundary Valve body Pressure Stainless steel Treated water Cracking Water Chemistry VIII.C.SP- 3.4.1-11 C,401 boundary > 140°F (int) Control - BWR 88 Valve body Pressure Stainless steel Treated water Loss of material Water Chemistry VIII.C.SP- 3.4.1-16 C,401 boundary > 140°F (int) Control - BWR 87 Table 2.3.2-8-3 High Pressure Core Spray System Nonsafety-Related Components Affecting Safety-Related Systems Components Subject to Aging Management Review Component Typ~ Intended Function 1 Siaht alass Pressure boundary
Attachment to GNRO-2014/00074 Page 8 of 8 Table 3.2.2-8-3 High Pressure Core Spray System Nonsafety-Related Components Affecting Safety-Related Systems Summary of Aging Management Evaluation Table 3.2.2-8-3: High Pressure Core Spray System, Nonsafety-Related Components Affecting Safety-Related Systems Aging Effect Aging NUREG-Component Intended Requiring Management 1801 Table 1 Type Function Material Environment Management Program Item Item Notes Sight glass Pressure Copper alloy Air - indoor (ext) None None V.F.EP-10 3.2.1-57 8-boundary > 15% Zn or
>8%AI Sight glass Pressure Copper alloy Treated water Loss of material Selective Leaching VII.E3.AP- 3.3.1-72 ~
boundary > 15% Zn or (int) 32
>8%AI Sight glass Pressure Copper alloy Treated water Loss of material Water Chemistry VII.E3.AP- 3.3.1-22 C,201 boundary > 15% Zn or (int) Control - BWR 140
>8%AI Sight glass Pressure Glass Air - indoor (ext) None None V.F.EP-15 3.2.1-60 8-boundary Sight glass Pressure Glass Treated water None None V.F.EP-29 3.2.1-60 8-boundary (int)