LR-N10-0094, Corrections to License Renewal Application

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Corrections to License Renewal Application
ML100910160
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 03/29/2010
From: Davison P
Public Service Enterprise Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N10-0094
Download: ML100910160 (8)


Text

PSEG Nuclear LLC P.O. Box 236,, Hancocks Bridge, NJ 08038-0236 0 PSEG Nuclear L.L. C.

10 CFR 50 10 CFR 51 10 CFR 54 LR-N10-0094 March 29, 2010 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Hope Creek Generating Station Facility Operating License No. NPF-57 NRC Docket No. 50-354

Subject:

Corrections to the Hope Creek Generating Station License Renewal Application

Reference:

Letter from PSEG Nuclear to USNRC "Application for Renewed Operating License - Hope Creek Generating Station," dated August 18, 2009 PSEG Nuclear LLC has identified corrections to the Hope Creek Generating Station (Hope Creek) License Renewal Application (LRA). As a supplement to the Hope Creek LRA, PSEG Nuclear LLC hereby provides a tabulation of these corrections in the Enclosure to this letter.

The changes are explained, and where appropriate to facilitate understanding, portions of the LRA are repeated with the change highlighted by strikethroughs for deleted text and bolded italics for inserted text.

This submittal has been discussed with the NRC License Renewal Senior Project Manager for the Hope Creek License Renewal project.

There are no new or revised regulatory commitments contained in this letter.

If you have any questions, please contact Mr. Ali Fakhar, PSEG Manager - License Renewal, at 856-339-1646.

LR-N 10-0094 March 29, 2010 Page 2 I declare under penalty of perjury that the foregoing is true and correct.

Executed on 3 -ZI - 10 Sincerely, Paul J. Davison Vice President, Operations Support PSEG Nuclear LLC

Enclosure:

Corrections to the Hope Creek Generating Station License Renewal Application cc:

S. Collins, Regional Administrator-USNRC Region I D. Ashley, Senior Project Manager, License Renewal - USNRC R. Ennis, Project Manager - USNRC NRC Senior Resident Inspector - Hope Creek P. Mulligan, Manager IV, NJBNE L. Marabella, Corporate Commitment Tracking Coordinator T. Devik, Hope Creek Commitment Tracking Coordinator

Enclosure Corrections to the Hope Creek Generating Station License Renewal Application Containment Hvdroqen Recombiner System Affected Section: 3.2.2 LRA Page Number: 3.2-44 Paragraph: Table 3.2.2-1 Change: Subsequent to LRA submittal, it was discovered that the strainer bodies in scope of the Containment Hydrogen Recombiner System are made of carbon steel material. Strainers YS 431A and 431B, shown on Boundary Drawing LR-M-58-1 Sheet 1, were misidentified as stainless steel material during the original scoping process.

Therefore, LRA Table 3.2.2-1 on page 3.2-44 is revised to incorporate a change in material for strainer body as shown below:

Table 3.2.2-1 Containment Hydrogen Recombiner System Component Intended Material Environment Aging Effect Aging NUREG Table 1 Notes Type Function Requiring Management

-1801 Item Management Program Vol. 2 Item Strainer Pressure Stainless Air - Indoor None Nene V.F=F-2 3.2.-_53 A

Body Boundary Steel (External)

Loss of External V.D2-2 3.2.1-31 Carbon Material/General Surfaces Steel Corrosion Monitoring Strainer Pressure Stairi*ees Treated Water Less of Mator4al One-Time V.02 28 3.2.4-A Body Boundary Steel (Internal)

Pi**tig.and Inspection Crevicen Corrosio Carbon Loss of Steel Material/General V.D2-33 3.2.1-14 Pitting and Crevice Corrosion Strainer Pressure Stawn4ess Treated Water Lss of Material!

Water V,02-28 32.A4 B

Body Boundary Stee4 (Internal)

.. #in4*

Chemistry V.D2-33 3.2.1-14 Carbon Loss of Steel Material/General Pitting and Crevice Corrosion Page 1 of 6

Enclosure Corrections to the Hope Creek Generating Station License Renewal Application Filtration, Recirculation, and Ventilation System Affected Section: 3.2.2 LRA Page Number: 3.2-59 Paragraph: Table 3.2.2-3 Change: Subsequent to LRA submittal, it was discovered that there are no stainless steel instrumentation valves in an "Air-Outdoor (External)" environment in the Filtration, Recirculation, and Ventilation System (FRVS). In the Application, stainless steel valves with the environment of "Air-Outdoor (External)" were mistakenly included as one component type line item in the Filtration, Recirculation, and Ventilation System (FRVS)

Aging Management Review Table 3.2.2-3 on page 3.2-59. This error was due to a misinterpretation of a note on the associated P&ID drawing M-84-1, sheet 1 in which all instrument root valves associated with the notated instrumentation line were mistakenly assumed in an outside environment. Follow-up review of Hope Creek P&ID drawings and instrumentation construction drawings show that only a small section of the notated instrumentation lines are located outside but the associated instrumentation root valves are located inside.

Therefore, LRA Table 3.2.2-3 on page 3.2-59 is revised to delete the valve body as shown below:

Table 3.2.2-3 Filtration, Recirculation, and Ventilation System Component Intended Material Environment Aging Effect Aging NUREG-Table 1 Notes Type Function Requiring Managemen 1801 Item Management t Program Vol. 2 Item Valve, Bdy PeeeUe Stainls A Q -.4^^.n 1=966 PeFiedA 1.327 3.6.15

&-6 Beuna.ý,

Seel (Extornal)

Mate~il~i~

lnspeotien And Gewon Page 2 of 6

Enclosure Corrections to the Hope Creek Generating Station License Renewal Application Hvdroqen and Oxvcien Analyzer System Affected Section: 3.2.2 LRA Page Number: 3.2-88 Paragraph: Table 3.2.2-5 Change: Subsequent to LRA submittal, it was discovered that a portion of the outdoor stainless steel piping includes stainless steel valves as well. The stainless steel piping and valves are properly shown in scope on Boundary Drawing LR-M-57-1 Sheet 1.

Stainless steel valve bodies exposed to an outdoor air environment were inadvertently omitted during aging management review of the Hydrogen and Oxygen Analyzer System. Stainless steel pipe with the environment of Air - Outdoor (External) had been included in LRA Table 3.2.2-5.

Therefore, LRA Table 3.2.2-5 on page 3.2-88 is revised to add the valve body as shown below:

Table 3.2.2-5 Hydrogen and Oxygen Analyzer System Component Intended Material Environment Aging Effect Aging NUREG-Table 1 Notes Type Function Requiring Management 1801 Item Management Program Vol. 2 Item Air-Loss of Valve Body Pressure Stainless Material/Pitting Periodic II1.B2-7 3.5.1-50 E, 3 Boundary Steel Outdoor and Crevice Inspection S(External)

Corrosion Page 3 of 6

Enclosure Corrections to the Hope Creek Generating Station License Renewal Application Control Room and Control Area HVAC System Affected Section: 3.3.2 LRA Page Number: 3.3-160 Paragraph: Table 3.3.2-7 Change: Subsequent to LRA submittal, it was discovered that the battery room exhaust portion of the Control Room and Control Area HVAC Systems includes damper housings that are constructed of stainless steel. While these dampers were properly shown as in scope on Boundary Drawing LR-M-89-1, Sheet 1, the stainless steel damper housings were inadvertently omitted from the aging management review for this system.

Therefore, LRA Table 3.3.2-7 on page 3.3-160 is revised to add the damper housing as shown below:

Table 3.3.2-7 Control Room and Control Area HVAC Systems Component Intended Material Environment Aging Effect Aging NUREG-Table 1 Notes Type Function Requiring Management 1801 Item Management Program Vol. 2 Item Damper Pressure Stainless Air-Indoor None None VII.J-15 3.3.1-94 C

Housing Boundary Steel (External)

Damper Pressure Stainless

  • Air/Gas -

Loss of Periodic VII.Fl-1 3.3.1-27 E, 2 Housing Boundary Steel Wetted Material/Pitting Inspection (Internal) and Crevice Corrosion Page 4 of 6

Enclosure Corrections to the Hope Creek Generating Station License Renewal Application Fire Protection System Affected Sections: 2.3.3 LRA Pages Number: 2.3-141 Paragraph: Table 2.3.3-10 Change: Subsequent to LRA submittal, it was discovered that "in scope" portions of the Hope Creek Fire Protection System do not include Fire Pump Suction Strainer Filter Elements. These components are located on the fire pump suction and were credited with the intended function of "Filter". However, review of Hope Creek P&ID drawings M-22-0 sheet 1 and M-00-0 sheets 1 and 2 confirmed that the strainers were removed after initial plant startup. The original purpose of the strainer elements was to protect the fire pumps from internal construction debris after system construction and fabrication during acceptance testing of the system. The internal strainer elements were removed after acceptance testing.

Therefore, LRA Table 2.3.3-10 on page 2.3-141 is revised to delete the Strainer (Fire Pump Suction Strainer) line item as shown below:

Table 2.3.3-10 Fire Protection System Components Subject to Aging Management Review Comronent Type Intended function Stra er 11Pr-P'-mF S'-ctiR S

ýr= rF-lte Affected Sections: 3.3.2 LRA Pages Number: 3.3-189 Paragraph: Table 3.3.2-10 Change: The LRA Table 3.3.2-10 applicable to the Fire Protection System on page 3.3-189 is revised to delete two Strainer (Fire Pump Suction Strainer) line items as shown below:

Table 3.3.2-10 Fire Protection System Component Intended Material Environment Aging Effect Aging NUREG-Table 1 Notes Type Function Requiring Management 1801 Item Management Program Vol. 2 Item Stairner F44ter Rtai"n4ess Raw-Water Loss of Materal!

FirFe-Water

,0 3.2.-38 E-45 (FirePump Steel Extema ft Gre e

System SutetGe apd Strainr)i l

a InfIluenced Qnrrnsiorm-arid Stiae%

Falter Stairn4ess Raw-Water Los o Mteria*;

Ir-ae VG3 3243 (F-Ire Pum Steel Pitig F~GreVOG yse Inlanad CGorree'GnaRd Page 5 of 6

Enclosure Corrections to the Hope Creek Generating Station License Renewal Application TLAA GSI 190 Affected Section: 4.3.5 LRA Page Number: 4-36 Paragraph: Summary Description, First paragraph, first sentence Change: Subsequent to LRA submittal, during the review of other Requests for Additional Information, it was discovered the NRC had requested another utility to change the wording describing GSI 190 in their application. A similar statement exists in the Hope Creek License Renewal Application. Specifically, the first sentence of the Summary Description reads as follows:

Generic Safety Issue (GSI) 166, later renumbered as GSI 190 (Reference 4.8.25), was identified by the NRC because of concerns about the effects of reactor water environment on the fatigue life of components and piping during the period of extended operation.

This statement is incorrect because GSI 166 was not renumbered to GSI 190. GSI 190 was a new issue developed to address concerns remaining from GSI 166 and GSI 78. In order to address this concern the first sentence of the Summary Description is replaced as follows:

GSI 190, "Fatigue Evaluation of Metal Components for 60-year Plant Life" (Reference 4.8.25), was established to address the residual concerns of GSI 78 and GSI 166 regarding the environmental effects on fatigue of pressure boundary components for 60 years of plant operation.

Page 6 of 6