JAFP-07-0067, License Renewal Application, Amendment 11

License Renewal Application, Amendment 11

ML071430185
Person / Time
Site:	FitzPatrick
Issue date:	05/17/2007
From:	Peter Dietrich Entergy Nuclear Northeast, Entergy Nuclear Operations
To:	Document Control Desk, NRC/NRR/ADRO
References
JAFP-07-0067
Download: ML071430185 (21)

Text

Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.James A. Fitzpatrick NPP--- EP.O. Box 110 Entergyf Lycoming, NY 13093 Tel 315 349 6024 Fax 315 349 6480 Pete Dietrich Site Vice President

-JAF May 17, 2007 JAFP-07-0067 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

REFERENCES:

1. Letter, Entergy to USNRC, "James A. FitzPatrick Nuclear Power Plant, Docket No. 50-333, License No. DPR-59, License Renewal Application," JAFP-06-0109, dated July 31, 2006 2. Letter, USNRC to JAFNPP, "Requests for Additional Information Regarding the Review of the License Renewal Application for James A. FitzPatrick Nuclear Power Plant (TAC No. MD2666)," dated April 25, 2007

SUBJECT:

Entergy Nuclear Operations, Inc.James A. FitzPatrick Nuclear Power Plant Docket No. 50-333, License No. DPR-59 License Renewal Application, Amendment 11 .

Dear Sir or Madam:

On July 31, 2006, Entergy Nuclear Operations, Inc. submitted the License Renewal Application (LRA) for the James A. FitzPatrick Nuclear Power Plant (JAFNPP) as indicated by Reference 1.Attachment I contains a response to RAls provided in Reference

2. Attachment 2 contains changes to the LRA stemming from NRC Region I inspection of the LRA. Attachment 3 contains the updates to LRA Table 3.1.2-3 requested in a telephone conference call with the NRC license renewal staff on May 15, 2007.Should you have any questions conceming this submittal, please contact Mr. Jim Costedio at (315) 349-6358.I declare under penalty of peijury that the foregoing is true and correct. Executed on the /1'day of May, 2007.SITE VICE PRESIDENT PD/cf May 17, 2007 JAFP-07-0067 Page 2 of 2 Attachment 1, 2, and 3 cc: Mr. N.B. (Tommy) Le, Senior Project Manager License Renewal Branch B Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0-11-FlWashington, DC 20555 Mr. Samuel J. Collins, Administrator Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 NRC Resident Inspector U. S. Nuclear Regulatory Commission James A. FitzPatrick Nuclear Power Plant P.O. Box 136 Lycoming, NY 13093 Mr. John P. Boska, Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8-C2 Washington, DC 20555 Mr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223 Mr. Peter R. Smith, President NYSERDA 17 Columbia Circle Albany, NY 12203-6399 JAFP-07-0067 Docket No. 50-333 Attachment I James A. FitzPatrick Nuclear Power Plant License Renewal Application

-Amendment 11 RAI Responses:

2.3.3 and 2.3.4 JAMES A. FITZPATRICK NUCLEAR POWER PLANT (JAFNPP)LICENSE RENEWAL APPLICATION (LRA)REQUESTS FOR ADDITIONAL INFORMATION (RAI)Sections 2.3.3 and 2.3.4 Section 2.3.3.2 (Service Water)RAI 2.3.3.2-2 The service water system (SW) provides cooling water used to cool various components and equipment at the plant. Because the system contains fluid, and parts of the system are in proximity to safety-related equipment, portions of the system meet the 10 CFR 54.4 (a)(2) scoping criteria.

The information provided in the LRA for this system is not sufficient for us to complete our review. The license renewal drawings do not show SSCs included in scope for 10 CFR 54.4 (a)(2), and no detailed description is given in the LRA of the portions of the system that were included in scope for 10 CFR 54.4 (a)(2). The general statement in the last paragraph of LRA Section 2.1.2.1.3 and the information on LRA page 2.3-95 is not sufficient for us to determine if SSCs were omitted.Please provide a detailed description of what portions of the SW system are included in scope for 10 CFR 54.4 (a)(2) and provide justification for the SSCs or portions of the system that are excluded provide. Also provide, or indicate (if current LR drawings depict the SW system) on which drawings the SSCs in scope of license renewal are shown.Response: The service water system includes components in the normal service water system and the emergency service water system. Components in the emergency service water system are included in scope for 54.4(a)(1) and (a)(3).As described in the JAF LRA in section 2.1.1.2.2, scoping for 54.4(a)(2) fits into the following categories:

• nonsafety-related SSCs directly connected to safety-related SSCs (typically piping and HVAC ductwork);

or* nonsafety-related SSCs with the potential for spatial interaction with safety-related SSCs.A review of components in the service water system included in scope for 54.4(a)(2) for spatial interaction used the site component database to identify components not included in scope for 54.4(a)(1) or (a)(3) and their locations.

The potential 54.4(a)(2) passive mechanical components in this system are located in the auxiliary boiler building, administration building, cable tunnel, EDG building, electrical bay area, MG set room, primary containment, reactor building, Attachment I Page I of 11 JAFP-07-0067 gas treatment building, screenwell house, service water pump house, and turbine building.

Components in the auxiliary boiler building, the turbine building in areas below elevation 260 and on elevation 260 outside grid coordinates 260-8D through 13G, and in the screenwell pumphouse in areas below elevation 255 or areas on elevation 272 outside building grid coordinates SW272-25A, 26A are not in scope for 54.4(a)(2) since there are no safety-related components in these buildings or areas. The major components excluded in these areas include the normal service water pump discharge backwash strainers (46STR-4A/B/C) and the turbine building zebra mussel monitoring tank (46TK-1).

The remaining portion of the system in the administration building, cable tunnel, electrical bay area, EDG building, MG set room, primary containment, reactor building, gas treatment building, screenwell house, service water pump house, and turbine building that requires aging management review due to potential spatial interaction includes orifice, piping, pump casing, strainer housing, tank, tubing, and valve bodies. These components are evaluated as indicated in Tables 2.3.3-14-30 and 3.3.2-14-30.

The majority of the components included in the service water system are shown on LRA drawings LRA-FM-46A, LRA-FM-46B and LRA-FM-46C.The nonsafety-related components that provide structural support for safety-related service water components are included.Attachment 1 Page 2 of 11 JAFP-07-0067 Section 2.3.3.12 (Radwaste and Plant Drains)RAI 2.3.3.12-1 The LRA states the yard storm drain and roof drain systems are within the scope of license renewal based on the need to provide a drainage flow path for fire water in the event of a fire (10 CFR 54.4(a)(3)) (Table 2.3.3.12).

Without a more detailed description of the system, the technical review staff cannot determine if components subject to AMR were omitted (see Table 3.3.2-12).

Please provide more detailed discussion to identify the components required to support the (10 CFR 54.4(a)(3))

function, and discuss the portion of the system, or SSCs were excluded from scope. Justify the exclusions.

Response: The plant drains system provides a network of 4 inch piping to remove approximately 100 gpm of fire fighting water in the following plant areas.* Administration building* Auxiliary boiler room* Emergency generator building* Screenwell building* Heater bay* Radwaste building* Reactor building* Turbine building* Electric & piping tunnels (east and west)In each area, water gravity drains from higher to lower elevations and in some cases discharges to a sump where the water is pumped to other areas of the plant. Floor drains in potentially contaminated areas are piped to the radwaste system for analysis before discharge to the environment.

Floor drains in non-contaminated areas discharge to the yard storm drainage system or the screenwell discharge tunnel.The following passive components of the plant drains system are included in this system review.1. Sump pumps (20P-1A/B, 20P-2A/B, 20P-3A/BICIDIE, 20P-4, 75P-1A/B, 75P-3A/B)2. Floor drain piping and valves 3. Sump pump suction and discharge piping and valves 4. Tanks (sumps) (20TK-25A/B, 20TK-28, 20TK-68A/B, 20TK-103, 20TK-104, 20TK-130A/B/C, 20TK-218)These are the only passive components in the floor drain routes described in LRA Section 2.3.3.12.

The plant drains system number is 020-FEDS although Attachment 1 Page 3 of 11 JAFP-07-0067 some components in system numbers 020, 075 and 077 are included in this system to accomplish its intended function.

Excluded components in this system are not required to remove fire fighting water from the areas mentioned above.The major drainage path components excluded are the following tanks, sumps, sump pumps and associated piping and valves.System 20- Waste sludge tank (20TK-45)System 20-FEDS- Radwaste drywell equipment drain sump (20TK-107), turbine building equipment drain sump (20TK-159), high conductivity drain sump (20TK-233), radwaste building equipment drain sump (20TK-234), concentrated waste tank (20TK-655), reactor building equipment drain sumps (20TK-69A/B)

System 75- Screenwell sump pump (75P-2A/B), reactor building perimeter sump pump (75P-4A/B, condensate storage tank pit sump pump (75P-5A/B)

System 77- None Attachment 1 Page 4 of 11 JAFP-07-0067 Section 2.3.3.14 (Miscellaneous Systems in Scope for (a)(2))RAI 2.3.3.14-1 The turbine building closed loop cooling system is described in LRA Section 2.3.3.14, and UFSAR Section 9.6. In the LRA, this system is included in scope of license renewal per 10 CFR 54.4(a)(2).

Table 2.3.3-14-23 lists the system components subject to AMR. Based on the information provided in the LRA and UFSAR (including the system drawing), it appears that in addition to the component types listed in the table the system also contains pumps and heat exchangers.

Please provide more detailed discussion to identify the portions of the system. Or SSCs excluded from scope. Also provide plant equipment arrangement drawings that show the layout of major plant equipment at various elevations of the Turbine Building and provide justification for the omission of pump casing, and heat exchanger in Table 2.3.3-14-23.

Response: The turbine building closed loop cooling (TBCLC) system has no components with intended functions in scope for 54.4(a)(1) or (a)(3).As described in the JAF LRA in section 2.1.1.2.2, scoping for 54.4(a)(2) fits into the following categories:

• nonsafety-related SSCs directly connected to safety-related SSCs (typically piping and HVAC ductwork);

or* nonsafety-related SSCs with the potential for spatial interaction with safety-related SSCs.A review of components in the turbine building closed loop cooling system included in scope for 54.4(a)(2) for spatial interaction used the site component database to identify the locations of the components.

The potential 54.4(a)(2) passive mechanical components in this system are located in the turbine building, auxiliary boiler room, and radwaste building.

Components in the auxiliary boiler building, the radwaste building and the turbine building in areas below elevation 260 and on elevation 260 outside grid coordinates 260-8D through 13G, are not in scope for 54.4(a)(2) since there are no safety-related components in these buildings or areas. The major components in these areas that are excluded include the TBCLC pumps (37P-2A/B/C), TBCLC heat exchangers (37E-3A/B/C), and TBCLC pump restricting orifices.

The remaining portion of the system in the turbine building that requires aging management review due to potential spatial interaction includes piping, strainer housing, tank, thermowell, tubing, and valve bodies. These components are evaluated as indicated in Tables 2.3.3-14-23 and 3.3.2-14-23.

The components in the TBCLC system are shown on FSAR Figure 9.5-1 sheets 1 and 2.Attachment 1 Page 5 of 11 JAFP-07-0067 There are no nonsafety-related components attached to safety-related components included since none of the components in this system are attached to safety-related components.

RAI 2.3.3.14-2 The LRA states that the following systems are within the scope of license renewal based on the potential for physical interaction with safety components (10CFR54.4(a)(2) (Table 2.3.3-14A).

Circulating Water Contaminated Equipment Drains Main Turbine Generator Sample System Because parts of the system contain fluid and are in proximity of safety-related equipment, some of the non-safety portions of the system meet the IOCFR54.4(a)(2) scoping criteria.

The information provided in your submittal is insufficient for us to complete our review of this since you have not specifically identified the parts of the systems included in scope for 10CFR54.4(a)(2), and have not given a detailed description of the portions of the system that are included in scope. Please provide more detailed discussion to identify what portions of the system, or SSCs were included in scope per 10 CFR 54.4(a)(2).

For the SSCs or portions of the systems that were excluded, please provide justification.

Response: Circulating Water The circulating water system has no components with intended functions in scope for 54.4(a)(1) or (a)(3).As described in the JAF LRA in section 2.1.1.2.2, scoping for 54.4(a)(2) fits into the following categories: " nonsafety-related SSCs directly connected to safety-related SSCs (typically piping and HVAC ductwork);

or* nonsafety-related SSCs with the potential for spatial interaction with safety-related SSCs.A review of components in the circulating water system included in scope for 54.4(a)(2) for spatial interaction used the site component database to identify the locations of the components.

The potential 54.4(a)(2) passive mechanical components in this system are located in the screenwell house and the turbine Attachment I Page 6 of 11 JAFP-07-0067 building.

Components in the turbine building in areas below elevation 260 and on elevation 260 outside grid coordinates 260-8D through 13G, and the screenwell pumphouse in areas below elevation 255 or areas on elevation 272 outside building grid coordinates SW272-25A, 26A are not in scope for 54.4(a)(2) since there are no safety-related components in these buildings or areas. The major components in these areas that are excluded include the circulating water pumps (36P-1A/BIC), the circulating water sump pumps (36P-6A/B/C), and condenser water box expansion joints. The portion of the system in the screenwell house that requires aging management review due to potential spatial interaction includes piping, pump casing, tank, tubing, and valve bodies. These components are evaluated as indicated in Tables 2.3.3-14-22 and 3.3.2-14-22.

The components in the circulating water system are shown on FSAR Figure 10.6-1.There are no nonsafety-related components attached to safety-related components included since none of the components in this system are attached to safety-related components.

Contaminated Equipment Drains The contaminated equipment drains system has sight glass components with intended functions included for 54.4(a)(1) which are reviewed as part of the standby gas treatment system.As described in the JAF LRA in section 2.1.1.2.2, scoping for 54.4(a)(2) fits into the following categories: " nonsafety-related SSCs directly connected to safety-related SSCs (typically piping and HVAC ductwork);

or" nonsafety-related SSCs with the potential for spatial interaction with safety-related SSCs.A review of components in the contaminated equipment drains system included in scope for 54.4(a)(2) for spatial interaction used the site component database to identify the locations of the components.

The potential 54.4(a)(2) passive mechanical components in this system are located in the reactor building.

The portion of the system in the reactor building that requires aging management review due to potential spatial interaction includes piping, sight glass, and valve bodies. These components are evaluated in Tables 2.3.3-14-29 and 3.3.2-14-29.

There were no contaminated equipment drains system components inside the reactor building that were excluded.

All passive fluid-filled components not already in scope for 54.4(a)(1) or 54.4(a)(3) are included for 54.4(a)(2) due to potential for spatial interaction.

The components in this system are shown on LRA drawing LRA-FM-44A.

Attachment 1 Page 7 of 11 JAFP-07-0067 Main Turbine Generator The main turbine generator system has no components with intended functions in scope for 54.4(a)(1) or (a)(3).As described in the JAF LRA in section 2.1.1.2.2, scoping for 54.4(a)(2) fits into the following categories:

• nonsafety-related SSCs directly connected to safety-related SSCs (typically piping and HVAC ductwork);

or* nonsafety-related SSCs with the potential for spatial interaction with safety-related SSCs.A review of components in the main turbine generator system included in scope for 54.4(a)(2) for spatial interaction used the site component database to identify the locations of the components.

The passive mechanical components in this system are located in the turbine building.

The portion of the system in the turbine building that requires aging management review due to potential spatial interaction includes filter housing, heat exchanger shell, piping, pump casing, sight glass, strainer housing, tank, thermowell, tubing, turbine casing, and valve bodies. These components are evaluated as indicated in Tables 2.3.3-14-42 and 3.3.2-14-42.

There were no main turbine generator system components inside the turbine building that were excluded.

All passive fluid-filled components in this system were included for 54.4(a)(2) due to spatial interaction.

There are no nonsafety-related components attached to safety-related components included since none of the components in this system are attached to safety-related components.

Sample System The sample system has no components with intended functions in scope for 54.4(a)(1) or (a)(3).As described in the JAF LRA in section 2.1.1.2.2, scoping for 54.4(a)(2) fits into the following categories: " nonsafety-related SSCs directly connected to safety-related SSCs (typically piping and HVAC ductwork);

or* nonsafety-related SSCs with the potential for spatial interaction with safety-related SSCs.A review of components in the sample system included in scope for 54.4(a)(2) for spatial interaction used the site component database to identify the locations of the components.

The passive mechanical components in this system are in the Attachment 1 Page 8 of 11 JAFP-07-0067 reactor building and radwaste building.

Components in the radwaste building are not in scope for 54.4(a)(2) since there are no safety-related components in this building.

The major components in the radwaste building that are excluded include the chilled water recirculation pump (95P-200), feedwater sample coolers (95SC-101 and 102), condensate sample pump cation columns (95D-23A/B), and the sample system isobath chiller (95-CH-2).

The portion of the system in the reactor building that requires aging management review due to potential spatial interaction includes heat exchanger tubes, piping, pump casing, sight glass, tubing, and valve bodies. These components are evaluated as indicated in Tables 2.3.3-14-43 and 3.3.2-14-43.

There were no components excluded inside the reactor building.

All passive fluid-filled components inside the reactor building are included for 54.4(a)(2) due to spatial interaction.

There are no nonsafety-related components attached to safety-related components included since none of the components in this system are attached to safety-related components.

The majority of components in this system are shown on FSAR figures 9.14-1 and 9.14-2.Attachment 1 Page 9 of 11 JAFP-07-0067 Section 2.3.4 (Steam and Power Conversion Systems)RAI 2.3.4-1 LRA section 2.3.4.2 addresses the Main Steam System, and Section 2.3.4.3 address the Feedwater System. The specific components of these systems that are included in scope for license renewal have not been identified in these sections, nor have the specific drawings used in identifying the in-scope components.

There are no tables in this section identifying the SSCs included in-scope and subject to AMR, and the scoping and screening results as pertaining to system SSCs in scope for 10 CFR 54.4(a)(1), 10 CFR 54.4(a)(2) and 10 CFR 54.4(a)(3) are not apparent.

Please specify what specific Main Steam and Feedwater System components are in scope of license renewal and their associated intended function.

Also identify were in the LRA the components are evaluated along with the LRA result table in which the components are listed.Response: In LRA Sections 2.3.4.2 and 2.3.4.3 under the section titled Components Subject to AMR, the LRA locations of main steam and feedwater system component evaluations are described.

Main Steam The main steam system components that are in scope for 54.4(a)(1) or (a)(3) and subject to AMR are highlighted on LRA drawing LRA-FM-29A.

As shown on this drawing in the notes section, all components are prefixed with 29 or MST unless otherwise noted. System 29 and MST are designations for the main steam system. The components in the main steam system shown on this drawing are evaluated in the following sections and Tables of the LRA.2.3.1 Reactor Coolant system (Includes Class 1 main steam components);

Tables 2.3.1-3 and 3.1.2-3 2.3.3.6 Standby Gas Treatment system (Includes main steam leakage collection system components);

Tables 2.3.2-6 and 3.2.2-6 2.3.3.10 Instrument Air system (Includes MSIV air accumulators);

Tables 2.3.3-10 and 3.3.2-10 A review of components included for 54.4(a)(2) for spatial interaction used the site component database to identify the locations of system components not included in scope for 54.4(a)(1) or (a)(3). The potential 54.4(a)(2) passive mechanical components in this system are located in the primary containment, reactor building, and the turbine building.

Components in the turbine building in areas below elevation 260 and on elevation 260 outside grid coordinates 260-8D through 13G, are not in scope for 54.4(a)(2) since there are no safety-related components in these buildings or areas. The major components in the excluded Attachment 1 Page 10 of 11 JAFP-07-0067 areas include the main steam line drain Y strainers (29Y-05A/B/C/D).

The portion of the system in the primary containment, reactor building, and turbine building that requires aging management review due to potential spatial interaction includes piping, strainer housing, thermowell, tubing, and valve bodies. These components are evaluated as indicated in Tables 2.3.3-14-16 and 3.3.2-14-16.

The nonsafety-related components that provide structural support for safety-related main steam components are included.Feedwater The feedwater system components that are in scope for 54.4(a)(1) or (a)(3) and subject to AMR are highlighted on LRA drawing LRA-FM-34A.

As shown on this drawing in the notes section, all components are prefixed with 34 or FWS unless otherwise noted. System 34 and FWS are designations for the feedwater system. The components highlighted on this drawing are evaluated in Section 2.3.1 reactor coolant system and included in Tables 2.3.1-3 and 3.1.2-3.A review of components included for 54.4(a)(2) for spatial interaction used the site component database to identify the locations of the components included in this system that are not included in scope for 54.4(a)(1) or (a)(3). The potential 54.4(a)(2) passive mechanical components in this system are located in the turbine building.

Components in the turbine building in areas below elevation 260 and on elevation 260 outside grid coordinates 260-8D through 13G, are not in scope for 54.4(a)(2) since there are no safety-related components in these buildings or areas. The major components in the excluded areas include zinc injection skid components, reactor feedwater pump inboard and outboard seal water coolers (34E-5A112), reactor feedwater pumps (34P-1A/B), and the reactor feedwater pump suction flow elements (34FE-135A/B).

The portion of the system in the turbine building that requires aging management review due to potential spatial interaction includes orifice, piping, thermowell, tubing, and valve bodies. These components are evaluated as indicated in Tables 2.3.3-14-20 and 3.3.2-14-20.

The nonsafety-related components that provide structural support for safety-related feedwater components are included.Attachment 1 Page 11 of 11 JAFP-07-0067 JAFP-07-0067 Docket No. 50-333 Attachment 2 James A. FitzPatrick Nuclear Power Plant License Renewal Application

-Amendment 11 NRC Region I Inspection

-LRA Updates The following information supplements the previously submitted License Renewal Application:

Floor and Roof Drainage System Changes LRA Table 2.3.3.14-A, Systems within the Scope of License Renewal based on the Potential for Physical Interaction with Safety-Related Components (10 CFR 50.4(a)(2)), is revised to add the following line for the floor and roof drainage system.System Code System Name Section Describing System 75 Floor and Roof Drainage Section 2.3.3.12, Radwaste and Plant Drains LRA Table 2.3.3.14-B, 10 CFR 50.4(a)(2)

Aging Management Review Tables, is revised to add the following line for the floor and roof drainage system.LRA Section 2.3.3.12, Radwaste and Plant Drains, is revised as follows (strikeouts deleted, underlined text added).The yard storm drains and floor and roof drainage systems have no intended functions for 10 CFR 54.4(a)(1)

F -(a)(2).The yard storm drains and floor and roof drainage systems have the following intended functions for 10 CFR 54.4(a)(2).

Maintain integrity of nonsafety-related components such that no phvsical interaction with safety-related components could Prevent satisfactory accomplishment of a safety function.Attachment 2 Page 1 of 4 JAFP-07-0067 LRA Section 2.3.3 is revised to add a new Table 2.3.3-14-45, Floor and Roof Drainage, Nonsafety-Related Components Affecting Safety-Related Systems-Components Subject to Aging Management Review, as follows.Component Type Intended Function'Bolting Pressure boundary Piping Pressure boundary Valve body Pressure boundary 1. For component types included under 10 CFR 54.4(a)(2), the intended function of pressure boundary includes providing structural/seismic support for components that are included for nonsafety-related SSCs directly connected to safety-related SSCs.LRA Section 3.3.2 is revised to add Table 3.3.2-14-45, Floor and Roof Drainage, Nonsafety-Related Components Affecting Safety-Related Systems-Summary of Aging Management Evaluation, as follows.Component Intended MatealAging Effect Aging NUREG mpoen Fnctind Material Environment Requiring Management

-1801, Table Notes Type Function Maaeet Programs Vol.2 Item Noe Management PItem Pressure Carbon Air- indoor Loss of Bolting VII.I-4 3.3.1-43 A Bolting boundary steel (ext) material integrity (AP-27)External VII.I-8 3.3.1-58 A Pressure Carbon Air -indoor Loss of surfaces (A-77)Piping boundary steel (ext) material monitoring (A-7 Periodic VII.C1- 3.3.1-76 E surveillance 19 Piping boundary steel Raw water (int) Loss of and (A-38)Pressundare Cat material preventive maintenance External VII.I-8 3.3.1-58 A Valve Pressure Carbon Air -indoor Loss of surfaces (A-77)body boundary steel (ext) material monitoring (A-7 Periodic VII.C1- 3.3.1-76 E surveillance 19 Valve Pressure Carbon R Loss of and (A-38)body boundary steel aw water (int) material preventive I_ _ I_ _ _maintenance I_ I LRA Section B.1.22 is revised to add "floor and roof drainage" to the list of nonsafety-related systems affecting safety-related components managed by the Periodic Surveillance and Preventive Maintenance Program.Attachment 2 Page 2 of 4 JAFP-07-0067 Security Generator System Changes LRA Table 2.3.3-13, Security Generator System Components Subject to Aging Management Review, is revised adding the following line item.LRA Table 3.3.2-13, Security Generator System Summary of Aging Management Evaluation, is revised adding the following line items.NUREG Componen Intended MaAal Environment Aging Effect Aging -1801, Table 1 Notes Type Function Requiring Management Vol.2 Item Management Programs Item Sight Pressure Glass Air -indoor None None VII.J-8 3.3.1-93 A glass boundary (ext) (AP-14)Sight Pressure VII.J-10 3.3.1-93 A glass boundary Glass Lube oil (int) None None (AP-15)External VII.I-8 3.3.1-58 A Sight Pressure Carbon Air -indoor Loss of surfaces (A-77)glass boundary steel (ext) material monitorng (A-77 Sight Pressure Carbon Loss of VII.12- 3.3.1-14 E glass boundary steel Lube oil (int) material Oil analysis 20 1 1_ _ _1__1(AP-30)

Fuel Oil System Chanaes LRA Table 3.3.2-4, Fuel Oil System Summary of Aging Management Evaluation, add the following line items.is revised to Attachment 2 Page 3 of 4 JAFP-07-0067 Service, Instrument, and Breathinq Air Chan-oes LRA Table 3.3.2-14-25, Service, Instrument, and Breathing Air Systems Management Evaluation, is revised to add the following line items.Summary of Aging Component Intended MateriAging Effect Aging NUREG mponen Fnctind Matera Environment Requiring Management

-1801, Table I Notes Tye Function Management Programs Vol.2 Item Item Pressure Stainless Air -indoor VII.J-15 3.3.1-94 A Tubing boundary steel (ext) None None (AP-1 7)Pressure Stainless VII.J-19 3.3.1-97 A Tubing boundary steel Gas None None (AP-22)Valve Pressure Stainless Air- indoor VII.J-15 3.3.1-94 A body boundary steel (ext) None None (AP-17)Valve Pressure Stainless VII.J-19 3.3.1-97 A body boundary steel Gas None None (AP-22)Attachment 2 Page 4 of 4 JAFP-07-0067 JAFP-07-0067 Docket No. 50-333 Attachment 3 James A. FitzPatrick Nuclear Power Plant License Renewal Application

-Amendment 11 Table Updates: Table 3.1.2-3 In response to Audit Question 344, JAFNPP agreed to add the Inservice Inspection Program to three line items in Table 3.1.2-3, Reactor Coolant Pressure Boundary of the license renewal application.

JAFNPP hereby modifies the license renewal application to add ISI to the Aging Management Program column for the three line items for Table 1 item 3.1.1-48 (Condensing chambers, Filter housings (CRD), and Orifices (instrumentation).

This will make the entries consistent with NUREG-1801 Item IV.C1-1. These entries will retain Note E because the JAFNPP ISI program is a plant-specific program.Page 3.1-58 Line Item: Condensing chambers, stainless steel, cracking Add Inservice Inspection to Aging Management Program column.Page 3.1-59 Line Item: Filter housing (CRD), stainless steel, cracking Add Inservice Inspection to Aging Management Program column.Page 3.1-61 Line Item: Orifices (instrumentation), stainless steel, cracking Add Inservice Inspection to Aging Management Program column.Although not addressed by Audit Question 344, Inservice Inspection should also be included in the line item in Table 3.1.2-3 for valve bodies <4" NPS, with CASS material, and the aging effect reduction of fracture toughness.

JAFNPP hereby modifies the license renewal application as follows.Page 3.1-71 Line Item: Valve bodies <4" NPS, CASS, reduction of fracture toughness Add Inservice Inspection to Aging Management Program column for Table I item 3.1.1-55.Attachment 3 Page 1 of I JAFP-07-0067