ML12339A439

Official Exhibit - NRC000023-00-BD01 - Reply to Request for Additional Information Regarding Offsite Power, Refueling Cavity, and Unit 2 Auxiliary Feedwater Pump Room Fire Event Indian Point Nuclear Generating Unit Nos. 2 & 3

ML12339A439
Person / Time
Site:	Indian Point
Issue date:	06/12/2009
From:	Dacimo F Entergy Nuclear Northeast
To:	Atomic Safety and Licensing Board Panel, Document Control Desk, Office of Nuclear Reactor Regulation
SECY RAS
References
RAS 22139, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01
Download: ML12339A439 (72)

Text

United States Nuclear Regulatory Commission Official Hearing Exhibit Entergy Nuclear Operations, Inc.

In the Matter of:

(Indian Point Nuclear Generating Units 2 and 3) v....t.ft.{\ REGUl..q", ASLBP #: 07-858-03-LR-BD01

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Docket #: 05000247 l 05000286

• 0 Exhibit #: NRC000023-00-BD01 Identified: 10/15/2012

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Admitted: 10/15/2012 Withdrawn:

~4? +O~ Rejected: Stricken: NRC000023

• • • .... Other:

Submitted: March 29, 2012 Q . Entergy Nuclear Northeast Indian Point Energy Center

~Entergx 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel (914) 788-2055 Fred Dacimo Vice President License Renewal NL-09-079 June 12, 2009 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Reply to Request for Additional Information Regarding Offsite Power, Refueling Cavity, and Unit 2 Auxiliary Feedwater Pump Room Fire Event Indian Point Nuclear Generating Unit Nos. 2 & 3 Docket Nos. 50-247 and 50-286 License Nos. DPR-26 and DPR-64

REFERENCES:

1. NRC Letter dated May 20, 2009, "Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application - Offsite Power, Refueling Cavity, and Unit 2 Auxiliary Feedwater Pump Room Fire Event

Dear Sir or Madam:

Entergy Nuclear Operations, Inc is providing, in Attachment I, the additional information requested in the referenced letter pertaining to NRC review of the License Renewal Application for Indian Point 2 and Indian Point 3. The additional information provided in this transmittal addresses staff questions regarding Offsite Power, Refueling Cavity, and Unit 2 Auxiliary Feedwater Pump Room Fire Event. Attachment 2 consists of Revision 9 to the list of regulatory commitments.

If you have any questions, or require additional information, please contact Mr. Robert Walpole at 914-734-6710.

I declare under penalty of perjury that the foregoing is true and correct. Executed on lP/INo9 .

Sincerely,

--W. ~. ~CW" f. \h~

NL-09-079 Page 2 of 2 FRD/dmt

Attachment:

1. Reply to R~quest for Additional Information Regarding Offsite Power, Refueling Cavity, and Unit 2 Auxiliary Feedwater Pump Room Fire Event

2. List of Regulatory Commitments, Revision 9 cc: Mr. Samuel J. Collins, Regional Administrator, NRC Region I .

Mr. Sherwin E. Turk, NRC Office of General Counsel, Special Counsel Ms. Kimberly Green, NRC Safety Project Manager Mr. Kenneth Chang, NRC Branch Chief, Engineering Review Branch I Mr. John Boska, NRR Senior Project Manager Mr. Paul Eddy, New York State Department of Public Service NRC Resident Inspector's Office Mr. Francis J. Murray, President and CEO, NYSERDA

ATTACHMENT 1 TO NL-09-079 Reply to Request for Additional Information Regarding Offsite Power, Refueling Cavity, and Unit 2 Auxiliary Feedwater Pump Room Fire Event ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 & 3 DOCKET NOS. 50-247 AND 50-286

Attachment 1 NL-09-079 Page 1 of 51 INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION OFFSITE POWER, REFUELING CAVITY, AND UNIT 2 AUXILIARY FEEDWATER PUMP ROOM FIRE EVENT RAI2.5-4 In license renewal application (LRA) Section 2.5, as clarified in LRA Amendment 3, dated March 24, 2008, the applicant included in the scope of license renewal the structures and components for one offsite circuit path (138 kV/Station Auxiliary Transformer circuit, the immediate access circuit) . The applicant is requested to explain why the second offsite circuit (the delayed access circuit) path, from .the first inter-tie with the offsite distribution systems at the Buchanan substations to the safety buses, was not included in the scope of license renewal.

Specifically, the applicant is requested to explain why the components up to and including either 138 kV circuit breaker F1 or 345 kV circuit breaker F7 for IP2 and either 138 kV circuit breaker F3 or 345 kV circuit breaker F7 for IP3 were not included in the scope of license renewal.

Response for RAI 2.5-4 The components up to and including either 138 kV circuit breaker F1 or 345 kV circuit breaker F7 for IP2 and either 138 kV circuit breaker F3 or 345 kV circuit breaker F7 for IP3 were not included in the scope of license renewal because they do not meet the scoping criteria of 10 CFR 54.4. The scoping for offsite power recovery was in accordance with the guidance provided in a staff letter dated April 1, 2002. That letter states, "For purposes of the license renewal rule, the staff has determined that the plant system portion of the offsite power system that is used to connect the plant to the offsite power source should be included within the scope of the rule." The breakers identified in this RAI are part of the offsite power source; and not plant system components that are used to *connect the plant to the offsite power source.

Discussion The second offsite circuit path was explicitly added in response to RAI 2.5-1 .

RAI 2.5-1 (Dated 10/24/07; ML0729200270) asked the following question.

According to the above, both paths from the safety-related 480 Volt (V) buses to the first circuit breaker from the offsite line, used to control the offsite circuits to the plant, should be age managed. The guidance does not specify that the switchyard is not part of the plant system nor that the switchyard does not need to be included in the scope of license renewal. Explain in detail which high voltage breakers and other components in the switchyard will be connected from the startup transformers up to the offsite power system for the purpose of SBO recovery.

Attachment 1 NL-09-079 Page 2 of 51 RAI 2.5-1 Response Excerpt (Dated 11/16/2007)

General Design Criterion 17 of 10 CFR Part 50, Appendix A, specifies that electric power from the transmission network to the onsite electric distribution system be supplied by two physically independent circuits to minimize the likelihood of their simultaneous failure. As discussed in IP2 UFSAR Section 8.1.2.1, "10 CFR 50 Appendix A General Design Criterion 17 - Electric Power Systems," the two physically independent circuits supplying offsite power to IP2 are the Buchanan Substation via the Con Edison 138 kV system feeder and the Buchanan 13.8 kV system feeder. The 138 kV system feeder is the primary offsite power source connected to the 6.9 kV buses through the station auxiliary transformer. The 13.8 kV system feeder is the secondary offsite power source connected to the 6.9 kV buses through the GT autotransformer. The station auxiliary transformer and the GT autotransformer perform the functions assigned to the typical startup transformers referred to in the April 1, 2002 letter.

LRA Figure 2.5-2 showed only the primary offsite power source or the 6.9kV source from the 138kV/6.9kV station auxiliary transformer, which is connected to the Buchanan substation through the Con Edison 138kV feeder. Figure 2.5-2 is revised as shown in this response to add the secondary offsite power feeder from the 13.8 kV Buchanan substation via the GT autotransformer.

As shown in the revised LRA Figure 2.5-2, the 6.9 kV buses receive power from the two independent sources of offsite power via the 138 kV 16.9 kV station auxiliary transformer or the 13.8 kV 16.9 kV GT autotransformer. The station auxiliary transformer is connected to the 138 kV Buchanan substation, the primary offsite power source, via switchyard bus,overhead transmission conductors, and underground transmission conductors through motor-operated disconnect F3A, which is located at the Buchanan substation. The GT autotransformer is connected to the 13.8 kV Buchanan substation, the secondary offsite power source, via underground medium voltage cable through breaker F2-3, which is located at the Buchanan substation.

General Design Criterion 17 of 10 CFR Part 50, Appendix A, specifies that electric power from the transmission network to the onsite electric distribution system be supplied by two physically independent circuits to minimize the likelihood of their simultaneous failure. As discussed in IP3 UFSAR Section 8.2.1, "Network Interconnection", and 8.2.3, "Emergency Power - Sources Description," the two physically independent circuits supplying offsite power to IP3 are the Buchanan Substation via the Con Edison 138 kV system feeder and the Buchanan 13.8 kV system feeder. The 138 kV system feeder is the primary offsite power source connected to the 6.9 kV buses through the station auxiliary transformer. The 13.8 kV system feeder is the secondary offsite power source connected to the 6.9 kV buses through the GT autotransformer. The station auxiliary transformer and the GT autotransformer perform the functions assigned to the typical startup transformers referred to in the April 1, 2002 letter.

Attachment 1 NL-09-079 Page 3 of 51 LRA Figure 2.5-3 showed only the primary offsite power source or the 6.9kV source from the 138kV/6.9kV station auxiliary transformer, which is connected to the Buchanan substation through the Con Edison 138kV feeder .. Figure 2.5-3 is revised as shown in this response to add the secondary offsite power feeder from the .13.8 kV Buchanan substation via the GT autotransformer.

As shown in the revised LRA Figure 2.5-3, the 6.9 kV buses receive power from the two independent sources of offsite power via the 138 kV 16.9 kV station auxiliary transformer or the 13.8 kV 16.9 kV GT autotransformer. The station auxiliary transformer is connected to the 138 kV Buchanan substation, the primary offsite power source, via switchyard bus and overhead transmission conductors through breaker BT2-6, which is located at the Buchanan substation.

The GT autotransformer is connected to the 13.8 kV Buchanan substation, the secondary offsite power source, via underground medium voltage cable through breaker F3-1, which is located at the Buchanan substation.

(Revised LRA Figures 2.5-2 and 2.5-3 were also provided with this RAI response.)

Based on discussions with the NRC staff on 12112/07 and 1/30108 this.RAI response was revised for the IP2 138 kV connection point.

RAI 2.5-1 Response Clarification Excerpt (Dated 3/24/2008)

As shown in the revised LRA Figure 2.5-2. the 6.9 kV buses receive offsite power from either the 138 kV / 6.9 kV station auxiliary transformer or the 13.8 kV / 6.9 kV GT autotransformer. The station auxiliary transformer is connected to the 138 kV Buchanan substation, the primary offsite power source, via switchyard bus, overhead transmission conductors, and underground transmission conductors through meter eperatee diS60nne6t ~aA switchyard breakers F2 and BT 3-4 which is are located at the Buchanan substation. The GT autotransformer is connected to the 13.8 kV Buchanan substation, the secondary offsite power source, via underground medium voltage cable through breaker F2-3, which is located at the Buchanan substation.

(A revised LRA Figure 2.5-2 was also provided with this RAI clarification.)

The boundaries described in the RAI 2.5-1 response were determined in accordance with the guidance provided in a staff letter dated April 1, 2002. The following excerpt from the RAI 2.5-1 response discusses this determination.

RAI 2.5-1 Response Excerpt (Dated 11/16/2007)

The staff position in the letter dated April 1, 2002, "Staff Guidance on Scoping of Equipment Relied on to Meet the Requirements of the Station Blackout (SBO)

Rule (10 CFR 50.63) for License Renewal (10 CFR 54.4(a)(3))" is that the plant system portion of the offsite power system should be included within the scope of license renewal. Specifically, the letter states,

Attachment 1 NL-09-079 Page 4 of 51 "For purposes of the license renewal rule, the staff has determined that the plant system portion of the offsite power system that is used to connect the plant to the offsite power source should be included within the scope of the rule."

Implementation of the staff position requires definition of the offsite power source. The April 1, 2002 letter states:

"The offsite power systems of U.S. nuclear power plants consist of a transmission system (grid) component that provides a source of power and a plant system component that connects that power source to a plant's onsite electrical distribution system which powers safety equipment. The staff has historically relied upon the well-distributed, redundant, and interconnected nature of the grid to provide the necessary level of reliability to support nuclear power plant operations."

In this discussion, the staff defines the offsite power source as the transmission system or the grid. The staff refers to the well-distributed, redundant, and interconnected nature of the grid. The Buchanan substation, which includes the 345 kV, the 138 kV, and the 13.8 kV sections, is a key element of the well-distributed, redundant and interconnected grid or transmission system that constitutes the offsite power source for IP2 and IP3.

The Buchanan substation provides for the interconnection of multiple sources of power and provides dispatch control for a multiple county transmission network. The multiple power sources are interconnected through switchyard bus, transmission conductors, and breakers within the substation. In keeping with the guidance in the letter dated April 1, 2002, the SBa recovery paths from the plant systems to the offsite power system or grid connection are included in scope for license renewal.

The 138 kV circuit breaker F1, the 345 kV circuit breaker F7, and the 138 kV circuit breaker F3 are part of the Buchanan Substation, which is part of the well-distributed, redundant and interconnected grid or transmission system that constitutes the offsite power source for IP2 and IP3 .. In other words, these breakers are part of the transmission system (grid) ,component that provides a source of power; and not plant system components that connect that power source to the plant's onsite electrical distribution system which powers safety equipment. The Buchanan Substation is not the IP2 or IP3 switchyard. The Buchanan Substation is part of the Con Edison transmission and distribution system, and it provides distribution to Westchester County and the New York City area with 345 kV, 138 kV, and 13.8 kV transmission lines. The Con Edison transmission system does not perform a function that meets the license renewal scoping criteria of 10 CFR 54.4.

The breakers conservatively included in scope for the offsite power recovery path are the interface points added to the Buchanan Substation during the construction of IP2 and IP3. As stated in LRA Section 2.5:

Attachment 1 NL-09-079 Page 5 of 51 In addition to the plant electrical systems, certain switchyard components required to restore offsite power following a station blackout were conservatively included within the scope of license renewal even though those components are not relied on in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commission's regulations for station blackout (SBO) (10 CFR 50.63).

The breakers are shown on LRA Figure 2.5-2 (Amended by letter dated 3/24/2008), and LRA Figure 2.5-3 (Amended by letter dated 11/16/2007).

Follow-up RAI 2: Open Item 3.0.3.2.15-1 The purpose of this follow-up request for additional information (RAI) is to request additional information and clarification to help the staff to understand the applicant's May 1, 2009 response to Follow-up RAI 1 for Open Item 3.0.3.2.15-1. Specifically, the staff requests the following:

(a) In part (a) of the applicant's response, Figures 1 through 4 do not clearly identify the flow path from the refueling cavity liner to the A, B, and C water exit locations.

Therefore, please provide the following additional descriptive information. In an elevation view (similar to Figure 2), cut through each of the exit locations A, B, and C, showing the horizontal and vertical dimension between the entry point through the liner and the exit location. To the extent possible, describe the possible circumferential traverse of the leakage, from the entry point through the liner to the exit location.

(b) The staff requests the applicant to provide the following additional information/clarification regarding the revised license renewal commitments in part (b) of the applicant's response:

(1) The current remediation plan has targeted the 2014 outage for completion.

Please identify actions that will be taken if the remediation plan is unsuccessful.

(2) Identify the specific location and number of the concrete core samples (e.g., the three water exit locations) that will be removed and tested (i) during the upcoming, 2010 refueling outage, and (ii) at 10 years into the extended period of operation (if

• a permanent solution for the leakage has not been achieved, in accordance with Entergy's current remediation plan). Define the tests that will be performed, and the objective of each test.

(3) Please advise if the revised commitments in the applicant's May 1, 2009 response include chemical analysis of the leaking water (i) during the upcoming 2010 refueling outage, and (ii) at 10 years into the extended period of operation.

Please identify the ana'lyses that will be performed, and the objective of each analysis.

Attachment 1 NL-09-079 Page 6 of 51 Response for Follow-up RAI 2: Open Item 3.0.3.2.15-1

a. Based on leakage investigations, the reactor refueling cavity begins to leak when the water in the cavity reaches an approximate elevation between 80'- 85'. As can be seen on the attached elevation views of the cavity (Figures 1 thru 4), horizontal weld seams exist between these elevations, but the exact liner leakage points are unknown. We can, however, make the following observations regarding the relationship between the leakage areas in the concrete structure denoted as points A, Band C, and conditions of the cavity liner:

1. Above point A, defects in the CeramAlloy patch along a horizontal weld seam located on the south wall at an elevation between 80'- 85' has been observed. The CeramAlloy patch material that covers several weld seams was a previous attempt to mitigate the cavity leakage. This is a potential cavity liner leak point for the observed leakage on the concrete structure at point A.

2. Above the exit point denoted as B, defects in a CeramAlloy patch along a horizontal weld seam located at an elevation between 80'- 85' on the south wall has been observed. This patch area is an extension from the area discussed in item 1 above. In addition, the upper internals stand support base is attached to the cavity floor above the vicinity of the observed leakage in the concrete structure at point B. Both these areas in the cavity liner are potential leak point sources for the observed leakage at point B.

3. Above the observed leakage area in the concrete structure denoted as point C, defects in both the CeramAlloy patches along weld seams and potential defects in the weld seams themselves at the north cavity wall have been observed. These defects are located approximately 10-15' above the cavity floor and are potential leak points for the leakage observed at point C.

b. The following provides Entergy's response to part (b) of the staff's request.

1. Should the remediation plan for the cavity liner targeted for completion during the 2014 outage be unsuccessful, Entergy will perform additional monitoring to assess the condition of potentially affected structures. To assure continued structural integrity of the reactor refueling cavity reinforced concrete walls, Entergy will perform further core sampling and inspect reinforcing steel at suspect locations as described in item 3.

2. (i) During the upcoming 2010 outage, a total of 3 core bore samples will be taken from the reinforced concrete walls that form the outer shell of the reactor refueling cavity steel liner. The locations of these core bores will be chosen based on the following.

~ Locations in the vicinity of observed linerlliner patch degradation in relative proximity to the observed leak points A, Band C on the concrete structure.

~ Accessibility of suspect areas based on the principle of As Low As Reasonably Achievable (ALARA) and physical interferences.

Attachment 1 NL-09-079 Page 70f 51 The core samples will be tested and chemically analyzed to determine the effect, if any, past leakage has had on the concrete properties. The objectives of the physical and chemical tests of the concrete core samples are as follows ..

~ Determine the compressive strength of concrete.

~ Determine boron and chloride concentration in concrete.

~ Determine pH of concrete.

In addition, a petrographic examination will be performed on the core samples to evaluate the cementitious matrix, and, to the extent possible, determine the durability of the concrete.

In addition, reinforcing steel in the core sample areas will be exposed and inspected. Visual inspections of the reinforcing steel will be performed to determine the extent of material loss, if any, from the steel as a result of the borated water leakage.

2. (ii) -If a solution to the leakage has not been achieved, Entergy will perform core samples and reinforcing steel inspections prior to 10 years into the period of extended operation. Locations of the core samples will be chosen based on the extent and location of the leakage remaining following previous repair efforts. Core samples will be tested and chemically analyzed as discussed under part 2 above. Visual inspections of the reinforcing steel will be performed to determine the extent of material loss, if any, from the steel as a result of the borated water leakage.

3. (I and ii) Revised Commitment 36 includes chemical analysis of water leakage from the refueling cavity. During the upcoming 2010 outage, Entergy will collect water samples from the cavity leak and perform chemical analysis.

If the leakage has not been stopped, Entergy will collect additional water samples of the leak during the same outage as the core samples are taken no later than 10 years into the period of extended operation. The water that is collected will be analyzed for the following.

~ Boron concentration

~ pH

~ Iron

~ Calcium Results of the analysis will be evaluated to assess the aggressiveness of the leaking fluid to reinforced concrete structures.

Attachment 1 NL-09-079 Page 8 of 51 FIGURE 1 VIEW FROM NORTHWEST rI LEAKAGE BEGINS _ PLATE TO PLATE WELDS (TYPICAL)

AT 80-85 FT. ELEV.

POINT "e" 69FT. ELEV.

REACTOR ____ POINT "B" VESSEL 64 FT. ELEV.

BIOLOGICAL SHIELD WALL

Attachment 1 NL-09-079 Page 9 of 51 VIEW FROM SOUTHWEST FIGURE 2 AREA OF SUSPECTED AREA OF FAILED CERAMALLOY SUSPECTED PATCH FAILED CERAMALLOY PATCH LEAKAGE BEGINS AT XSO-S5FT.

ELEV.

r BOTTOM SLAB 5 FT THICK

."",.. PLATE TO PLATE WELDS POINT "A" 69 FT. ELEV.

POINT "B" 64 FT. ELEV. " REACTOR VESSEL BIOLOGICAL SHIELD WALL

Attachment 1 NL-09-079 Page 10 of 51 FIGURE 3 REFUELING CAVITY CONCRETE~

- jUNER PLATES~ ~

95 FT EL

~ LEAKAGE BEGINS AT 80-85 FT. ELEV.

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(Y) (Y)

..-t I 3,9 ..-t I 3 ,9

.. -I ..-

I 69 FT EL,

~.) ~ '---J \iJ, POINT A" POINT IIC II ) II

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REACTOR VESSEL 0J BIOLOGICAL SHIELD WALL 46 FT EL, VIEW' LOO k ING EA ST DIMENSIONS IN FEET

Attachment 1 NL-09-079 Page 11 of 51 95 FT, EL, FIGURE 4 CAVITY CAVITY EXTERIOR INTERIOR LINER PLATE LEAKAGE BEGINS AT ~

80-85 FT. ELEV. ~

~==:::c tr

....../ UPPER INTERNALS SUPPORT STAND 69 FT, EL,

(\J 64 FT, EL, If)

POINT "B" OPEN PASSAGE 46 FT , EL, VIE w LOOKING NORTH DIMENSIONS IN FEET

Attachment 1 NL-09-079 Page 12 of 51 RAJ 3.4.2-2 By letter dated January 27, 2009, Entergy responded to RAI 3.4.2-1, and provided clarifying details regarding the passive, long-lived component types, materials, environments, aging effects and aging management programs for systems, structures and components that support the auxiliary feedwater (AFW) pump room fire event at Indian Point Nuclear Generating Unit No.2 (IP2) that were not already within the scope of license renewal for 10 CFR 54.4(a)(1) or (a)(2).

The staff reviewed the response and determined that the systems contain passive, long-lived components made of materials that when exposed to the stated environments may experience aging effects as described in the GALL Report, which must be managed during the period of extended operation in accordance with 10 CFR 54.21 (a)(3).

By letter dated May 1, 2009, Entergy submitted a revised commitment list which included a new commitment (Commitment 39) to install a fixed automatic fire suppression system for IP2 in the AFW pump room which would make the suppression configuration of the room similar to that of the AFW pump room at Unit 3.

Because the planned installation is not yet part of the current licensing basis, the staff cannot make a finding consistent with the requirement in 10 CFR 54.29(a). Therefore, the staff requests that the applicant provide information to demonstrate that the effects of aging will be adequately managed so that the intended function(s) will maintained consistent with the current licensing basis for the period of extended operation as required by 10 CFR 54.21 (a)(3). Specifically, the staff requests that the applicant list all aging effects and the aging management programs needed to manage the aging effects for the component types provided in the January 27, 2009 letter.

Response for RAJ 3.4.2-2 As stated in the initial response*to RAI 3.4.2-1 in the January 27, 2009 letter, the function of supporting safe shutdown in the event of a fire in the auxiliary feed pump room is confirmed on an ongoing basis since the required SSCs are performing their intended functions under design basis conditions during normal operation. Performance of intended functions during normal plant operation demonstrates that the systems and components can perform those functions for one hour in the event of a fire in the auxiliary feedwater pump room. Nevertheless, the additional information requested by the staff is provided below in the form of revised tables from the response to RAI 3.4.2-1 provided in the January 27, 2009 letter. This additional information includes aging effects and aging management programs to manage the aging effects for the component types that support the AFW pump room fire event that were not already included in scope and subject to aging management review for 10CFR54.4(a)(1) or (a)(2).

These tab.les identify changes as strikethroughs for deletions and underlines for additions. During the revision of these tables, the following changes to line items in the tables were identified outside of the addition of aging effects and programs.

~ new line items identifying cracking as an aging effect for tubing in the condensate system and loss of material due to selective leaching in heat exchanger tubes for the instrument air system.

Attachment 1 NL-09-079 Page 13 of 51

~ new line items for component type "strainers" in the city water system and the IP1 station air system

~ new line items for component type "strainer housings" made of copper alloy

>15% zn in the city water system

~ deleted line items for component type "expansion joint" made of elastomer in the condensate system since elastomer expansion joints are replaced on a specified time period

~ new line items for pump casings made of gray cast iron and stainless steel in the circulating water system

~ revised line items in the service water system to change environment from "air-outdoor (ext)" to "condensation (ext)" for consistency with other LRA tables

~ revised line items for environment of "treated water (int)" to include "> 140°F" for high temperature aging effects

~ revised line item for pump casings in the wash water system to change material to "stainless steel" from "carbon steel"

~ revised line item for pump casings for the river water system to change material to "gray cast iron" from "carbon steel"

~ revised line item for pump casings for the fresh water cooling system to change material to "titanium" from "copper alloy"

~ Replaced Note 408 with the following:

408 The "air - treated" environment is the equivalent of dried air and for the purposes of evaluating aluminum components, the "air - treated" environment is drier than the NUREG-1801 defined "air - indoor uncontrolled" .

The addition of aging management programs to these tables also resulted in necessary revisions for Appendix A, UFSAR Supplement and Appendix B, Aging Management Programs and Activities which are also provided with this response.

The following revised tables are provided in response toRAI 3.4.2-2.

Attachment 1 NL-09-079 Page 14 of 51 Table 3.4.2-5-1-IP2 Conventional Closed Cooling System Components Required to Support AFW Pump Room Fire Event Summary of Aging Management Review

~able 3.4.2-5-1-IP2: Conventional Closed Cooling System (CCC)

Aging Effect NUREG- Table 1 Intended Aging Management Notes Component Type Material Environment Requiring 1801 Vol. 2 Item Function Programs

- Management Item Pressure NGRe VII.E1-2 3.3.1-51 400 Heat exchanger Cogger alloll NGRe boundary aM Treated water (ext) Water Chemistry Control (AP-34) Q (tubes) >15% zn Loss of material Reat traAsfer - Closed Cooling Water Heat exchanger Cogger alloll Water Chemist[.ll Control VII.C2-2 3.3.1-52 400 Heat transfer Treated water (ext) Fouling (tubes) >15% zn - Closed Cooling Water (AP-80) B Heat exchanger Pressure Cogger alloll VII.C2-6 3.3.1-84 400 Treated water (ext) Loss of material Selective Leaching (tubes) bounda[.ll >15% zn (AP-43) C Pressure VII.C1-3 3.3.1-82 400 Heat exchanger Cogger alloll Treated water Raw NGRe NGRe (A-65) .Q boundary aM (tubes) >15% zn water (int) Loss of material Service Water Integritll Reat traAsfer .

Heat exchanger Heat transfer Cogger alloll Raw water (int) Fouling Service Water Integritll VII.C1-6 3.3.1-83 .Q (tubes). >15% zn (A-72)

Heat exchanger Pressure Cogger alloll Raw water (int) Loss of material Selective Leaching VII.C1-4 3.3.1-84 .Q (tubes) bounda[.ll >15% zn (A-66)

Attachment 1 NL-09-079 Page 15 of 51 Table 3.4.2-5-2-IP2 Condensate System Components Required to Support AFW Pump Room Fire Event Summary of Aging Management Review trable 3.4.2-5-2-IP2 Condensate System (CONO)

Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Pressure NGRe NeRe VIII.H-4 3.4.1-22 400 Bolting Carbon steel Air - indoor (ext) (S-34) A boundary Loss of material Bolting Integrit~

Pressure Stainless VII 1.1-1 0 3.4.1-41 400 Bolting Air - indoor (ext) None None boundary steel (SP-12) C Expansion joint Pressure Elastomer ,A',Ir indoor (ext) NGRe NeRe --- --- 400 eoundary --

Expansion joint Pressure Elastomer Steam (int) NGRe NeRe --- --- 400 eoundary --

Expansion joint Pressure Elastomer Treated water (int) NGRe NeRe --- --- 400 eoundary --

NeRe VIII.E-34 3.4.1-4 400 Heat exchanger Pressure NGRe A. 404 Carbon steel Treated water (int) Water Chemistry Control (S-10)

(shell) boundary Loss of material

- Primary & Secondary NeRe VIII.H-7 3.4.1-28 400 Heat exchanger Pressure NGRe (shell) boundary Carbon steel Air - indoor (ext)

Loss of material External Surfaces (S-29) 6 Monitoring NeRe VIII.A-16 3.4.1-2 400 Heat exchanger Pressure NGRe

- - C,404 Carbon steel Steam (ext) Water Chemistry Control (S-06)

(shell) boundary Loss of material

- Primary & Secondar~

Attachment 1 NL-09-079 Page 16 of 51 Irable 3.4.2-5-2-IP2 Condensate System (COND)

Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Heat exchanger Pressure Nooe Nooe --- --- 400 (tubes) boundary aM Titanium Steam (ext)

Loss of material Water Chemistry Control E Reat tFaAsfeF - Primary & Secondary Heat exchanger Heat transfer Titanium Steam (ext) Fouling Water Chemistry Control --- --- 400 (tubes) - Primary & Secondar~ F Pressure Nooe --- -- 400 Heat exchanger boundary aM Titanium Raw water (int)

Nooe Periodic Surveillance E (tubes) Loss of material and Preventive Reat tFaAsfeF Maintenance Heat exchanger Periodic Surveillance --- --- 400 (tubes)

Heat transfer Titanium Raw water (int) Fouling and Preventive E Maintenance Pressure Nooe VIII,A-5 3.4.1-15 400 Heat exchanger Nooe 0,404 boundary aM Copper alloy Treated water (int) Water Chemistry Control (SP-61)

(tubes) Loss of material Reat tFaAsfeF - Primary & Secondary Heat exchanger Water Chemistry Control VIII,E-10 3.4.1-9 400 Heat transfer C01212er allo~ Treated water (int) Fouling (SP-58) A, 404 (tubes) - Primary & Secondar~

Pressure VIII,G-8 3.4.1-10 400 Heat exchanger Nooe Nooe (SP-53) 0,405 boundary aM Copper alloy Lube oil (ext)

(tubes) Loss of material Oil Anal~sis Reat tFaAsfeF Heat exchanger VIII,G-8 3.4.1-10 400 Heat transfer C01212er allo~ Lube oil (ext) Fouling Oil Ana/~sis (SP-53) 0,405 (tubes)

Nooe VIII,B1-3 3.4.1-37 400 Heat exchanger Pressure* Stainless Nooe Q Steam (ext) Water Chemistry Control (SP-43)

(tubes) boundary steel Loss of material

- Primary & Secondar~

Attachment 1 NL-09-079 Page 17 of 51 Table 3.4.2-5-2-IP2 Condensate System (CON D)

Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Heat exchanger Pressure Stainless Water Chemistry Control VIII.B1-2 3.4.1-39 408 i Steam (ext) Cracking I (tubes) boundary steel - Primary & Secondary (SP-44) C Heat exchanger Heat transfer Stainless Steam (ext) Fouling Water Chemistry Control -- --- 408 (tubes) steel - Primary & Secondary G Nooe VIII.E-36 3.4.1-16 408 Heat exchanger Pressure Stainless Treated water Nooe Water Chemistry Control (S-22) A, 404 (tubes) boundary steel > 140°F (int) Loss of material

- Primary & Secondary Heat exchanger Pressure Stainless Treated water Water Chemistry Control VIII.E-30 3.4.1-14 408 Cracking (tubes) boundary steel > 140°F (int) - Primary & Secondar~ (SP-17) C,404 Heat exchanger Stainless Treated water Water Chemistry Control VIII.E-13 3.4.1-9 408 Heat transfer Fouling (tubes) steel > 140°F (int) - Primary & Secondary (SP-40) A, 404 Heat exchanger Pressure Nooe Nooe --- --- 408 (tubes) boundary Titanium Treated water (int)

Loss of material Water Chemistry Control E

- Primary & Secondary Heat exchanger Heat transfer Titanium Treated water (int) Fouling Water Chemistry Control --- --- 408 (tubes) - Primary & Secondary F Heat exchanger Pressure Nooe Nooe --- --- 408 (tubes) boundary Titanium Steam (ext)

Loss of material Water Chemistry Control E

- Primary & Secondar~

Heat exchanger Heat transfer Titanium Steam (ext) Fouling Water Chemistry Control --- --- 408 (tubes) - Primary & Secondary F Nooe VII I. E-34 3.4.1-4 400 Pressure Nooe Piping Carbon steel Treated water (int) Water Chemistry Control (S-10) A, 404 boundary Loss of material

- Primary & Secondary

Attachment 1 NL-09-079 Page 18 of 51 Table 3.4.2-5-2-IP2 Condensate System (CON D)

Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Pressure Cracking - VIlI.B1-10 3.4.1-1 400 ElQlng Carbon steel Treated water {int} Metal Fatigue - TLAA boundar~ fatigue {S-08} C NeAe VIlI.H-7 3.4.1-28 400 Pressure NeAe Piping boundary Carbon steel Air - indoor (ext)

Loss of material External Surfaces {S-29} ~

Monitoring NeAe VIII.H-7 3.4.1-28 400 Pressure NeAe Sight glass boundary Carbon steel Air - indoor (ext)

Loss of material External Surfaces {S-29} ~

Monitoring NeAe VIII.E-34 3.4.1-4 400 Pressure NeAe Sight glass Carbon steel Treated water (int) Water ChemistQi Control {S-10} A. 404 boundary Loss of material

- PrimaQi & Secondar~

Pressure VII 1.1-5 3.4.1-40 400 Sight glass Glass Air - indoor (ext) None None boundary {SP-9} ~

Pressure VII 1.1-8 3.4.1-40 400 Sight glass Glass Treated water (int) None None boundary {SP-35} A NeAe VIII.H-7 3.4.1-28 400 Pressure NeAe Thermowell boundary Carbon steel Air - indoor (ext) External Surfaces {S-29} ~

Loss of material Monitoring NeAe VIlI.E-34 3.4.1-4 400 Pressure NeAe Thermowell Carbon steel Treated water (int) Water ChemistQi Control {S-10} A. 404 Boundary Loss of material

- PrimaQi & SecondaQi Pressure Cracking - VIlI.B1-10 3.4.1-1 400 Thermowell Carbon steel Treated water {inn Metal Fatigue - TLAA Boundar~ fatigue {S-08} Q

Attachment 1 NL-09-079 Page 19 of 51

~able 3.4.2-5-2-IP2 Condensate System (CON D)

Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Pressure Stainless VII 1.1-1 0 3.4.1-41 400 Thermowell Air - indoor (ext) None None boundary steel (SP-12) A Nooe VIII.E-29 3.4.1-16 400 Pressure Stainless Treated water Nooe A. 404 Thermowell Water Chemistry Control (SP-16) boundary steel > 140°F (int) Loss of material

- Primary & Secondar~

Pressure Stainless Treated water Water Chemistry Control VII I. E-30 3.4.1-14 A. 404 Thermowell Cracking boundary steel > 140°F (int) - Primary & Secondary (SP-17)

Pressure Stainless Treated water Cracking - VII.E1-16 3.3.1-2 C,406 Thermowell Metal Fatigue - TLAA (A-57) boundary steel > 140°F (int) fatigue Nooe VIII.E-29 3.4.1-16 400 Pressure Stainless Treated water Nooe A. 404 Tubing Water Chemistry Control (SP-16) boundary steel > 140°F (int) Loss of material

- Primary & Secondary Pressure Stainless Treated water Water Chemistry Control VIII.E-30 3.4.1-14 400 i Tubing Cracking boundary steel > 140°F (int) - Primary & Secondary (SP-17) A. 404 Pressure Stainless Treated water Cracking - VII.E1-16 3.3.1-2 400 Tubing Metal Fatigue - TLAA boundary steel > 140°F (int) fatigue (A-57) C,406 Pressure Stainless Air - indoor (ext) None None VIII.I-10 3.4.1-41 ~

Tubing (SP-12) boundary steel Nooe VIII.E-34 3.4.1-4 400 Pressure Nooe A. 404 Valve body Carbon steel Treated water (int) Water Chemistry Control (S-10) i boundary Loss of material

- Primary & Seconda!y Valve bod~

Pressure Carbon steel Treated water (int) ~~~Cking- Metal Fatigue - TLAA VIII.B1-10 3.4.1-1 400 boundary ---'- --.J_ _ ~ (S-08)

Q

Attachment 1 NL-09-079 Page 20 of 51

!fable 3.4.2-5-2-IP2' Condensate System (CONO)

Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Nooe VIILH-7 3.4 .1-28 4G8 Pressure Nooe (S-29)

Valve body boundary Carbon steel Air - indoor (ext)

Loss of material External Surfaces 8 Monitoring Nooe VIILE-29 3.4.1-16 4G8 Pressure Stainless Treated water Nooe Valve body Water Chemistry Control (SP-16) A, 404 boundary steel > 140°F (int) Loss of material

- Primary & Secondary Pressure Stainless Treated water Water Chemistry Control VIILE-30 3.4.1-14 4G8 Valve bod~ Cracking boundary steel > 140°F (int) - Primary & Secondary (SP-17) A. 404 Pressure Stainless Treated water Cracking - VILE1-16 3.3.1-2 4G8 Valve bod~ Metal Fatigue - TLAA boundary steel > 140°F (int) fatigue (A-57) C,406 Pressure Stainless VII 1.1-1 0 3.4.1-41 4G8 Valve body Air - indoor (ext) None None boundary steel (SP-12) 8

Attachment 1 NL-09-079 Page 21 of 51 Table 3.4.2-5-3-IP2 Circulating Water System Components Required to Support AFW Pump Room Fire Event Summary of Aging Management Review Table 3.4.2-5-3-IP2 Circulating Water System (CIRC)

Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Pressure NeRe NeRe VII.I-1 3.3.1-43 4Qi Bolting Carbon steel Air - outdoor (ext) boundary Loss of material Bolting IntegrirL (AP-28) C NeRe VIII.E-1 3.4.1-11 4Qi Pressure NeRe .Q Bolting Carbon steel Soil (ext) Buried Piging And Tanks (S-01) boundary Loss of material Insgection Periodic Surveillance VIII.G-36 3.4.1-8 I; Pressure Bolting Carbon steel Raw water (ext) Loss of material and Preventive (S-12) boundarY Maintenance NeRe VII.C1-1 3.3.1-75 4Qi Pressure NeRe Periodic Surveillance (AP-75) I; Expansion joint Elastomer Raw water (int) boundary Cracking and Preventive Maintenance Change of Periodic Surveillance VII.C1-1 3.3.1-75 4Qi Pressure Exgansion joint Elastomer Raw water (int) material and Preventive (AP-75) I; boundarY grogerties Maintenance NeRe -- --- 4Qi Pressure NeRe Periodic Surveillance G Expansion joint Elastomer Air -outdoor (ext) boundary Cracking and Preventive Maintenance

Attachment 1 NL-09-079 Page 22 of 51 Table 3.4.2-5-3-IP2 Circulating Water System (CIRC)

Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Pressure Change of Periodic Surveillance -- --- 400 EXQansion joint bounda!:y Elastomer Air -outdoor (ext) material and Preventive 2 QroQerties Maintenance NGAe VIII.E-1 3.4.1-11 400 Pressure NGAe Piping Carbon steel Soil (ext) Buried PiQing And Tanks (S-01 ) Q boundary Loss of material InsQection NGAe VIII.H-8 3.4.1-28 400 Pressure NGAe Piping Carbon steel Air outdoor (ext) External Surfaces (S-41 ) ~

boundary Loss of material Monitoring NGAe VIII.G-36 3.4.1-8 400 Pressure NGAe Periodic Surveillance (S-12) ~

Piping Carbon steel Raw water (int) boundary Loss of material and Preventive Maintenance NGAe VIII.H-8 3.4.1-28 400 Pressure NGRe Pump casing Carbon steel Air-outdoor (ext) External Surfaces (S-41 ) ~

boundary Loss of material Monitoring NGAe VIII.G-36 3.4.1-8 400 Pressure NGAe Periodic Surveillance (S-12) ~

Pump casing Carbon steel Raw water (int) boundary Loss of material and Preventive Maintenance Periodic Surveillance VIII.G-36 3.4.1-8 400 Pressure PumQ casing Carbon steel Raw water (ext) Loss of material and Preventive (S-12) ~

bounda!:y Maintenance

Attachment 1 NL-09-079 Page 23 of 51 lTable 3.4.2-5-3-IP2 Circulating Water System (CIRC)

Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Periodic Surveillance VIII.E-27 3.4.1-32 g Pressure (SP-36)

Pump casing Stainless steel Raw water (int) Loss of material and Preventive bounda[Y Maintenance Periodic Surveillance VIII.E-27 3.4.1-32 g Pressure (SP-36)

Pump casing Stainless steel Raw water (ext) Loss of material and Preventive bounda[y Maintenance Pressure External Surfaces VIII.H-8 3.4.1-28 8 Pump casing Gra~ cast iron Air-outdoor (ext} Loss of material bounda[y Monitoring (S-41 }

Periodic Surveillance VIII.G-36 3.4.1-8 g Pressure (S-12)

Pump casing Gra~ cast iron Raw water (int) Loss of material and Preventive bounda[y Maintenance Pressure VIII.A-7 3.4.1-36 Q Pump casing Gra~ cast iron Raw water (int} Loss of material Selective Leaching bounda[y (SP-28}

Periodic Surveillance VIII.G-36 3.4.1-8 g Pressure (S-12}

Pump casing Gra~ cast iron Raw water (ext} Loss of material and Preventive bounda[y Maintenance Pressure VIII.A-7 3.4.1-36 Q Pump casing Gra~ cast iron Raw water (ext) Loss of material Selective Leaching boundar~ (SP-28}

Attachment 1 NL-09-079 Page 24 of 51 Table 3.4.2-S-4-IP2 City Water System Components Required to Support AFW Pump Room Fire Event Summary of Aging Management Review Table 3.4.2-S4-IP2 City Water System (CYW)

Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Pressure Nooe Nooe VILI-4 3.3.1-43 4G8 Bolting Carbon steel Air - indoor (ext) boundary Loss of material Bolting Integrit~ (AP-27) A Pressure Stainless VII.J-15 3.3.1-94 4G8 Bolting Air - indoor (ext) None None boundary steel (AP-17) C Pressure Nooe Nooe VILI-1 3.3.1-43 4G8 Bolting Carbon steel Air - outdoor (ext) boundary Loss of material Bolting Integriti (AP-28) A Bolting Pressure Stainless Air - outdoor (ext)

Nooe Nooe --- --- 4G8 boundary steel Loss of material Bolting Integriti G Pressure Stainless VII.J-15 3.3.1-94 4G8 Flex hose Air-indoor (ext) None None boundary steel (AP-17) A Flex hose Pressure Stainless Treated water (int)

Nooe Nooe -- --- 4G8 boundary steel Loss of material One-Time Ins(2ection G,407 Nooe VII.I-9 3.3.1-58 4G8 Pressure Nooe Piping boundary Carbon steel Air-outdoor (ext)

Loss of material External Surfaces (A-78) 8 Monitoring Nooe VILI-8 3.3.1-58 4G8 Pressure Nooe Piping boundary Carbon steel Air-indoor (ext)

Loss of material External Surfaces (A-77l 8 Monitoring

Attachment 1 NL-09-079 Page 25 of 51 Table 3.4.2-S-4-IP2 City Water System (CYW)

Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Nooe -- --- 400 Pressure Nooe Periodic Surveillance G.407 Piping Carbon steel Treated water (int) boundary* Loss of material and Preventive Maintenance Pressure Stainless VILJ-15 -3.3.1-94 400 Piping Air-indoor (ext) None None boundary steel (AP-17) A Pressure Stainless *Nooe Nooe -- --- 400 Piping Air-outdoor (ext) External Surfaces G boundary steel Loss of material Monitoring Piping Pressure Stainless Treated water (int)

Nooe Nooe -- --- 400 boundary steel Loss of material One-Time Insgection G.407 Nooe VI 1.1-9 3.3.1-58 400 Pressure Nooe (A-78)

Sight glass boundary Carbon steel Air-outdoor (ext)

Loss of material External Surfaces 8 Monitoring Nooe -- --- 400 Pressure Nooe Periodic Surveillance G.407 Sight glass Carbon steel Treated water (int) boundary Loss of material and Preventive Maintenance Sight glass Pressure Glass Air-outdoor (ext) None None -- --- 400 boundary G Sight glass Pressure Glass Treated water (int) None None -- --- 400 boundary G.407 c

Strainer Filtration Stainless Treated water {int} Loss of material One-Time Insgection --- --- G.407 Steel

Attachment 1 NL-09-079 Page 26 of 51 lTable 3.4.2-S-4-IP2 City Water System (CYW)

Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Strainer Filtration Stainless Treated water (ext) Loss of material One-Time Insl'2ection -- --- G, 407 Steel Nooe VI 1.1-8 3.3.1-58 400 Pressure Nooe Strainer housing boundary Carbon steel Air-indoor (ext)

Loss of material External Surfaces (A-77) 8 Monitoring Pressure Nooe Periodic Surveillance --- --- 400 Strainer housing Carbon steel Treated water (int) and Preventive G,407 boundary Loss of material Maintenance Pressure COl'21'2er alloy V.F-3 3.2.1-53 .Q Strainer housing Air-indoor (ext) None None boundary >15% zn (EP-10)

Pressure COl'21'2er alloy Periodic Surveillance -- -- G,407 i Strainer housing Treated water (inn Loss of material and Preventive boundary >15% zn Maintenance Strainer housing Pressure COl'21'2er alloy Treated water (int) Loss of material Selective Leaching --- - G,407 boundary >15% zn II Pressure Stainless VII.J-15 3.3.1-94 400 Strainer housing Air-indoor (ext) None None boundary steel (AP-17) A Strainer housing Pressure boundary Stainless steel Treated water (int)

Nooe Loss of material Nooe One-Time Insl'2ection

~071 Tubing Pressure Stainless Treated water (int)

Nooe Nooe -- --- 400 boundary steel Loss of material One-Time Insl'2ection G,407 Tubing Pressure Stainless Air - outdoor (ext)

Nooe Nooe External Surfaces

--- --- 400 G

boundary steel Loss of material Monitoring

- - ----....J ~-~~-~

-~

Attachment 1 NL-09-079 Page 27 of 51 Table 3.4.2-S-4-IP2 City Water System (CYW)

Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Pressure Stainless VII.J-15 3.3.1-94 400 I Tubing Air - indoor (ext) None None boundary steel (AP-17) A I

Nooe 400 Pressure Nooe Periodic Surveillance Go 407 Valve body Carbon steel Treated water (int) boundary Loss of material and Preventive Maintenance Nooe VII .I-9 3.3.1-58 400 Pressure Nooe Valve body boundary Carbon steel Air - outdoor (ext)

Loss of material External Surfaces (A-78l 8 Monitoring Nooe VI 1.1-8 3.3.1-58 400 Pressure Nooe Valve body boundary Carbon steel Air - indoor (ext)

Loss of material External Surfaces (A-77l 8 Monitoring Valve body Pressure Stainless Treated water (int)

Nooe Nooe --- --- 400 boundary steel Loss of material One-Time Insl2ection Go 407 Pressure Stainless Nooe Nooe -- --- 400 Valve body Air - outdoor (ext) External Surfaces G boundary steel Loss of material Monitoring Pressure Stainless VII.J-15 3.3.1-94 400 Valve body Air - indoor (ext) None None

• boundary steel (AP-17) 8

Attachment 1 NL-09-079 Page 28 of 51 Table 3.4.2-5-5-IP2 Wash Water System Components Required to Support AFW Pump Room Fire Event Summary of Aging Management Review Table 3.4.2-5-5-IP2 Wash Water System (WW) Components Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Pressure Nooe Nooe VILI-1 3.3.1-43 400 Bolting Carbon steel Air-outdoor (ext) boundary Loss of material Bolting Integrit~ (AP-28) A Bolting Pressure Stainless Air-outdoor (ext)

Nooe Nooe --- --- 400 boundary steel Loss of material Bolting Integrit~ G Bolting Pressure Stainless Raw water (ext) Loss of material Bolting Integrit~

VII.C1-15 3.3.1-79 Q boundar~ steel (A-54)

Nooe --- --- 400 Pressure Nooe Periodic Surveillance G Expansion joint Elastomer Air-outdoor (ext) boundary Cracking and Preventive Maintenance Pressure Change of Periodic Surveillance --- --- 400 EXl2ansion joint Elastomer Air-outdoor (ext) material and Preventive G bounda!y groQerties Maintenance Nooe VII.C1-1 3.3.1-75 400 Expansion joint Pressure Elastomer Raw water (int)

Nooe Periodic Surveillance (AP-75) £ boundary Cracking and Preventive Maintenance Change of Periodic Surveillance VII.C1-1 3.3.1-75 400 Pressure EXl2ansion joint bounda!y Elastomer Raw water (int) material and Preventive (AP-75) £ I2 ro l2erties Maintenance

Attachment 1 NL-09-079 Page 29 of 51 Irable 3.4.2-5-5-IP2 Wash Water System (WW) Components Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Pressure Stainless NGAe NGAe --- --- 400 Flex hose Air-outdoor (ext) External Surfaces G boundary steel Loss of material Monitoring NGAe VII.C1-15 3.3.1-79 400 Pressure Stainless NGAe Periodic Surveillance (A-54) ,!;

Flex hose Raw water (int) boundary steel Loss of material and Preventive Maintenance NGAe VII.I-9 3.3.1-58 400 Pressure NGAe (A-78)

Nozzles boundary Carbon steel Air-outdoor (ext)

Loss of material External Surfaces 8.

Monitoring NGAe VII.C1-19 3.3.1-76 400 Pressure NGAe Periodic Surveillance (A-38) ,!;

Nozzles Carbon steel Raw water (int) boundary Loss of material and Preventive Maintenance I

NGAe VII.I-9 3.3.1-58 400 Pressure NGAe (A-78)

Piping boundary Carbon steel Air-outdoor (ext)

Loss of material External Surfaces 8.

Monitoring NGAe VII.C1-19 3.3.1-76 400 Pressure NGAe Periodic Surveillance (A-38) ,!;

Piping Carbon steel Raw water (int) boundary Loss of material and Preventive Maintenance I Pressure Stainless NGAe NGAe --- --- 400 Piping Air-outdoor (ext) External Surfaces G boundary steel Loss of material Monitoring

- ----- - ----- ~ -

Attachment 1 NL-09-079 Page 30 of 51 rrable 3.4.2-5-5-IP2 Wash Water System (WW) Components Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item NeRe VII.C1-15 3.3.1-79 400 Pressure Stainless NeRe Periodic Surveillance (A-54) £ Piping Raw water (int) boundary steel Loss of material and Preventive Maintenance Pressure Carbon steel NeRe NeRe --- --- 400 Pump casing Stainless Air-outdoor (ext) External Surfaces G boundary Loss of material steel Monitoring NeRe VII.C1-15 *3.3.1-79 400 Carbon steel (A-54)

Pump casing Pressure Stainless Raw water (int)

NeRe Periodic Surveillance £ boundary Loss of material and Preventive steel Maintenance Periodic Surveillance VII.C1-15 3.3.1-79 400 Pressure Stainless PumQ casing Raw water (ext) Loss of material and Preventive (A-54) £ boundar~ steel Maintenance Pressure Stainless NeRe NeRe* --- --- 400 Tubing Air-outdoor (ext) External Surfaces G boundary steel Loss of material Monitoring NeRe VII.C1-15 3.3.1-79 400 Pressure Stainless NeRe Periodic Surveillance (A-54) £ Tubing Raw water (int) boundary steel Loss of material and Preventive Maintenance NeRe VI 1.1-9 3.3.1-58 400 Pressure NeRe Valve body Carbon steel Air-outdoor (ext) External Surfaces (A-78) 8 boundary Loss of material Monitoring

Attachment 1 Nl-09-079 Page 31 of 51

~able 3.4.2-5-5-IP2 Wash Water System (WW) Components Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Nooe VII.C1-19 3.3.1-76 400 ,

Pressure Nooe Periodic Surveillance (A-38) g Valve body Carbon steel Raw water (int) boundary Loss of material and Preventive Maintenance I Pressure Stainless Nooe Nooe --- --- 400 Valve body Air-outdoor (ext) External Surfaces G boundary steel

• Loss of material Monitoring Nooe VII.C1-15 3.3.1-79 400 Pressure Stainless Nooe Periodic Surveillance (A-54) g Valve body Raw water (int) I boundary steel Loss of material and Preventive Maintenance

- -~--

'-- -.L--- -

Attachment 1 NL-09-079 Page 32 of 51 Table 3.4.2-5-6-IP2 Feedwater System Components Required to Support AFW Pump Room Fire Event Summary of Aging Management Review

~able 3.4.2-5-6-IP2 Feedwater System (FW)

Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management . Item Nooe VIII.B1-3 3.4.1-37 408 Heat exchanger Pressure Stainless Nooe Steam (ext) Water Chemistry Control (SP-43) Q (tubes) boundary steel Loss of material

- Primary & Secondar~  !

Heat exchanger Pressure Stainless Water Chemistry Control VIII.B1-2 3.4.1-39 408 Steam (ext} Cracking I (tubes} boundary steel - Primary & Secondar~ (SP-44} C Nooe VIII.D1-4 3.4.1-16 408 Heat exchanger . Pressure Stainless Treated water Nooe Water Chemistry Control (SP-16} A. 404 (tubes) boundary steel > 140°F (int} Loss of material

- Primary & Secondary Heat exchanger Pressure Stainless Treated water Water Chemistry Control VIII.D1-5 3.4.1-14 408 Cracking (tubes} boundary steel > 140°F (int} - Primary & Sec6ndar~ (SP-17} C,404

Attachment 1 NL-09-079 Page 33 of 51 Table 3.4.2-5-7-IP2 Instrument Air System Components Required to Support AFW Pump Room Fire Event Summary of Aging Management Review Table 3.4.2-5-7-IP2 Instrument Air System (IA)

Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Pressure NeAe NeAe VI 1.1-1 3.3.1-43 400 Bolting Carbon steel Air-outdoor (ext) boundary Loss of material Bolting Integrit~ (AP-28) A Bolting Pressure Stainless Air-outdoor (ext)

NeAe NeAe --- --- 400 boundary steel Loss of material Bolting Integrit~ G NeAe VII.G-9 3.3.1-28 400 Pressure Heat exchanger boundary aM Copper alloy Condensation (int)

NeAe Periodic Surveillance (AP-78) ~

(tubes) >15% zn Loss of material and Preventive Reat tFaAsfeF Maintenance Heat exchanger Copper alloy Periodic Surveillance

-- --- 400 Heat transfer Condensation (int) Fouling and Preventive G (tubes) >15% zn Maintenance Pressure NeAe VII.C2-4 3.3.1-51 400 Heat exchanger Copper alloy Treated Water NeAe boundary aM Water Chemist!Y Control (AP-12) Q (tubes) >15% zn (ext) Loss of material Reat tFaAsfeF - Closed Cooling Water Heat exchanger Pressure Copper alloy Treated Water NeAe NeAe VII.C2-6 3.3.1-84 400 (tubes~ boundary >15% zn (ext) Loss of material Selective Leaching (AP-43) C Heat exchanger Copper alloy Treated Water Water Chemist!Y Control VII.C2-2 3.3.1-52 400 I Heat transfer Fouling (tubes) >15% zn (ext) - Closed Cooling Water (AP-80) Q I

Attachment 1 NL-09-079 Page 34 of 51

~able 3.4.2-5-7-IP2 Instrument Air System (IA)

Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Pressure V.F-3 3.2.1-53 4G8 Tubing Copper alloy Air - indoor (ext) None None boundary (EP-10) C Pressure VII.J-3 3.3.1-98 A. 408 Tubing Copper alloy Air - treated (int) None None boundary (AP-8)

Pressure Stainless VII.J-15 3.3.1-94 4G8 Tubing Air - indoor (ext) None None boundary steel (AP-17) A Pressure Stainless VILJ-18 3.3.1-98 A. 408 Tubing Air - treated (int) None None boundary steel (AP-20)

NeRe VII.D-3 3.3.1-57 4G8 Pressure NeRe Piping Carbon steel Air-indoor (ext) External Surfaces (A-80) 8 boundary Loss of material Monitoring Pressure VII.J-22 3.3.1-98 A. 408 Piping Carbon steel Air-treated (int) None None boundary (AP-4)

Pressure Stainless VILJ-15 3.3.1-94 4G8 Piping Air-indoor (ext) None None boundary steel (AP-17) A Pressure Stainless Air-treated (int)

VII.J-18 3.3.1-98 A. 408 Piping None None boundary steel (AP-20)

Pressure V.F-3 3.2.1-53 4G8 Valve body Copper alloy Air - indoor (ext) None None boundary (EP-10) C Pressure VII.J-3 3.3.1-98 A. 408 Valve body Copper alloy Air - treated (int) None None boundary (AP-8)

Pressure Copper alloy V.F-3 3.2.1-53 4G8 Valve body Air - indoor (ext) None None boundary >15% zn (EP-10) C Pressure Copper alloy VILJ-3 3.3.1-98 A. 408 Valve body Air - treated (int) None None boundary >15% zn (AP-8)

Attachment 1 NL-09-079 Page 35 of 51 Table 3.4.2-5-7-IP2 Instrument Air System (IA)

Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Nooe VILO-3 3.3.1-57 400 Pressure NGRe (A-80)

Valve body boundary Carbon steel Air - indoor (ext)

Loss of material External Surfaces 8 Monitoring Valve body Pressure Carbon steel Air - treated (int) None None VII.J-22 3.3.1-98 A. 408 boundary (AP-4)

Pressure Stainless VILJ-15 3.3.1-94 400 Valve body Air - indoor (ext) None None boundary steel (AP-17) A Pressure Stainless VILJ-18 3.3.1-98 A, 408 Valve body Air - treated (int) None None boundary steel (AP-20)

Attachment 1 NL-09-079 Page 36 of 51 Table 3.4.2-5-8-IP2 Instrument Air Closed Cooling System Components Required to Support AFW Pump Room Fire Event Summary of Aging Management Review Table 3.4.2-5-8-IP2 Instrument Air Closed Cooling System (IACC)

Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Co!;mer > VII.C1-3 3.3.1-82 Heat exchanger Pressure A-65) 4G8 15%Zn Raw water (int) Loss of material Service Water Integrity (tubes) boundarY (inhibited)

Q Copper> VII.C1-6 3.3.1-83 4G8 Heat exchanger Nooe Nooe (A-72)

Heat transfer 15%Zn Raw water (int)

Fouling Service Water Integrity Q

(tubes)

(inhibited)

Co~~er> VII.E1-2 3.3.1-51 4G8 Heat exchanger Pressure Water ChemistrY Control (AP-34) Q 15% Zn Treated water (ext) Loss of material (tubes) boundary - Closed Cooling Water (inhibited)

Copper> Nooe VII.C2-2 3.3.1-52 4G8 Heat exchanger Nooe Heat transfer 15% Zn Treated water (ext) Water ChemistrY Control (AP-80) Q (tubes) Fouling (inhibited) - Closed Cooling Water

-- ~--

Attachment 1 NL-09-079 Page 37 of 51 Table 3.4.2-5-9-IP2 Service Water System Components Required to Support AFW Pump Room Fire Event Summary of Aging Management Review lTable 3.4.2-5-9-IP2 Service Water System (SW)

Aging Effect NUREG-Intended Aging Management TaIJle 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Pressure Air outdoor (ext) Nooe Nooe VILO-1 3.3.1-44 400 Bolting Carbon steel (A-103) C boundary Condensation (ext) Loss of material Bolting Integrit~

Pressure Stainless Air outdoor (ext) Nooe Nooe VILF1-1 3.3.1-27 400 Bolting (A-09) E boundary steel Condensation (ext) Loss of material Bolting Integrit~

Nooe VILI-11 3.3.1-58 400 Pressure Air outdoor (ext) Nooe Nozzles Carbon steel External Surfaces (A-81) 6 boun 9ary Condensation (ext) Loss of material Monitoring Pressure Nooe Nooe VII.C1-19 3.3.1-76 400 Nozzles Carbon steel Raw water (int) (A-38) A boundary Loss of material Service Water Integrit~

Nooe VILI-11 3.3.1-58 400 Pressure Air outdoor (ext) Nooe Piping Carbon steel External Surfaces (A-81) 6 boundary Condensation (ext) Loss of material Monitoring Pressure Nooe Nooe VILC1-19 3.3.1-76 400 Piping Carbon steel Raw water (int) (A-38) A boundary Loss of material Service Water Integrit~

Nooe VILF1-1 3.3.1-27 400 Pressure Stainless Air outdoor (ext) Nooe Piping External Surfaces (A-09) £ boundary steel Condensation (ext) Loss of material Monitoring

Attachment 1 NL-09-079 Page 38 of 51 lTable 3.4.2-5-9-IP2 Service Water System (SW)

Aging Effect NUREG-

• Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Pressure Stainless Nooe Nooe VII.C1-15 3.3.1-79 400 Piping Raw water (int) (A-54) boundary steel Loss of material Service Water Integrit~ A Nooe VII.F1-16 3.3.1-25 400 Pressure Air ol:ltaoor (ext) Nooe Tubing Copper alloy External Surfaces (A-46) £ boundary Condensation (ext) Loss of material Monitoring Pressure None Nooe VII.C1-9 3.3.1-81 400 Tubing Copper alloy Raw water (int) (A-44) boundary Loss of material Service Water Integrit~ A Nooe VII.F1-1 3.3.1-27 400 Pressure Stainless Air ol:ltaoor (ext) Nooe Tubing External Surfaces (A-09) £ boundary steel Condensation (ext) Loss of material Monitoring Pressure Stainless Nooe Nooe VII.C1-15 3.3.1-79 400 Tubing Raw water (int) boundary steel Loss of material Service ~ater Integrit~ (A-54) A Nooe VILI-11 3.3.1-58 400 Pressure Air ol:ltaoor (ext) Nooe (A-81) 8.

Valve body Carbon steel External Surfaces boundary Condensation (ext) Loss of material Monitoring Pressure Nooe Nooe VII.C1-19 3.3.1-76 400 Valve body Carbon steel Raw water (int) (A-38) ,

boundary Loss of material Service Water Integrit~ A Nooe VII.F1-1 3.3.1-27 400 Pressure Stainless Air ol:ltaoor (ext) Nooe Valve body External Surfaces (A-09) £ boundary steel Condensation (ext) Loss of material Monitoring Pressure Stainless Nooe Nooe VII.C1-15 3.3.1-79 400 Valve body Raw water (int) (A-54) boundary steel Loss of material Service Water Integrit~ 8.

Attachment 1 NL-09-079 Page 39 of 51 Table 3.4.2-5-10-IP2 Lube Oil System Components Required to Support AFW Pump Room Fire Event Summary of Aging Management Review

Table 3.4.2-5-10-IP2 Lube Oil System (LO)

Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Heat exchanger Pressure Nooe Nooe --- --- 400 tubes boundary aM Titanium Lube oil (int)

Loss of material Oil Anal~sis E

Reat tFaASfeF Heat exchanger Heat transfer Titanium Lube oil {int} Fouling Oil Anal~sis --- --- 400 tubes E Pressure 400 Heat exchanger Nooe Nooe tubes boundary aM Titanium Raw water (ext)

Loss of material Service Water Integrit~

E Reat tFaAsfeF Heat exchanger Heat transfer Titanium - Raw water {ext} Fouling Service Water Integrit~ --- --- 400 tubes -

E

Attachment 1 NL-09-079 Page 40 of 51 Table 3.4.2-5-11-IP2 River Water Service System Components Required to Support AFW Pump Room Fire Event Summary of Aging Management Review Table 3.4.2-5-11-IP2 River Water Service System (RW)

Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management ~

Item Pressure Nooe NeR& VII.I-1 3.3.1-43 400 Bolting Carbon steel Air-outdoor (ext) (AP-28) boundary Loss of material Bolting Integrit~ A Bolting Pressure Stainless Air-outdoor (ext)

Nooe NeR& --- --- 400 boundary steel Loss of material Bolting Integri~ G NeR& VI 1.1-9 3.3.1-58 400 Pressure Nooe (A-78)

Piping boundary Carbon steel Air-outdoor (ext) .

Loss of material External Surfaces 8 Monitoring None VII.C1-19 3.3.1-76 400 Pressure Nooe Periodic Surveillance (A-38) £ Piping Carbon steel Raw water (int) boundary Loss of material and Preventive Maintenance Ga~bon steel NeR& VI 1.1-9 3.3.1-58 400 Pressure Nooe (A-78)

Pump casing boundary Gra~ cast Air-outdoor (ext)

Loss of material External Surfaces 8 iron Monitoring NeR& VII.C1-19 3.3.1-76 400 Ga~bon steel Pressure Nooe Periodic Surveillance (A-38) £ Pump casing Gra~ cast Raw water (int) boundary Loss of material and Preventive iron Maintenance

Attachment 1 NL-09-079 Page 41 of 51 Table 3.4.2-5-11-IP2 River Water Service System (RW)

Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Carbon steel VII.C1-11 3.3.1-85 6 Pressure (A-51 )

Pump casing Gra~ cast Raw water (int) Loss of material Selective Leaching boundar~

iron Pressure Stainless Nooe Nooe --- --- 400 Tubing Air-outdoor (ext) External Surfaces G boundary steel Loss of material Monitoring Nooe VII.C1-15 3.3.1-79 400 Pressure Stainless Nooe Periodic Surveillance (A-54) 1; Tubing Raw water (int) boundary steel . Loss of material and Preventive Maintenance Nooe VILI-9 3.3.1-58 400 Pressure Nooe (A-78)

Valve body boundary Carbon steel Air-outdoor (ext)

Loss of material External Surfaces 6 Monitoring Nooe VII.C1-19 3.3.1-76 400 Pressure None Periodic Surveillance (A-38) 1; Valve body Carbon steel Raw water (int) boundary Loss of material and Preventive Maintenance Pressure Stainless Nooe Nooe --- --- 400 I Valve body Air-outdoor (ext) External Surfaces G boundary steel Loss of material Monitoring Nooe VII.C1-15 3.3.1-79 400 Pressure Stainless Nooe Periodic Surveillance (A-54) 1; Valve body Raw water (int) boundary steel Loss of material and Preventive Maintenance

Attachment 1 NL-09-079 Page 42 of 51 Table 3.4.2-5-12-IP2 Fresh Water Cooling System Components Required to Support AFW Pump Room Fire Event Summary of Aging Management Review Table 3.4.2-5-12-IP2 Fresh Water Cooling (FWC) System Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Heat transfer Nooe --- --- 400 Heat exchanger aAG--pPressure Copper alloy Raw water (int)

Nooe Periodic Surveillance E (tubes) Titanium Loss of material and Preventive , I boundary Maintenance Heat exchanger Periodic Surveillance --- --- E Heat transfer Titanium Raw water (int) Fouling and Preventive (tubes)

Maintenance Heat transfer Nooe --- --- 400 Heat exchanger aAG--pPressure Copper alloy Treated Water Nooe Periodic Surveillance E (tubes) Titanium (ext) Loss of material and Preventive boundary Maintenance Heat exchanger Treated Water Periodic Surveillance --- --- E Heat transfer Titanium Fouling and Preventive (tubes) (ext)

Maintenance

Attachment 1 NL-09-079 Page 43 of 51 Table 3.4.2-5-13-IP2 IP1 Station Air System Components Required to Support AFW Pump Room Fire Event Summary of Aging Management Review Table 3.4.2-5-13-IP2 IP1 Station Air (SA) System )

i Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item Pressure Nooe Nooe VI 1.1-4 3.3.1-43 400 Bolting Carbon steel Air-indoor (ext) boundary Loss of material Bolting Integrit~ (AP-27} A Pressure Stainless VILJ-15 3.3.1-94 400 Bolting Air-indoor (ext) None None boundary steel (AP-17} A Nooe V11.0-3 3.3.1-57 400 Pressure Nooe (A-BO}

Filter housing boundary Carbon steel Air-indoor (ext)

Loss of material External Surfaces 6 Monitoring Nooe VII. 0-2 3.3.1-53 400 Pressure Nooe Periodic Surveillance (A-26} £ Filter Housing Carbon steel Condensation (int) boundary Loss of material and Preventive Maintenance Nooe V11.0-3 3.3.1-57 400 Pressure Nooe Piping Carbon steel Air-indoor (ext) External Surfaces (A-BO} 6 boundary Loss of material Monitoring Nooe VII. 0-2 3.3.1-53 400 Pressure Nooe Periodic Surveillance (A-26} £ Piping Carbon steel Condensation (int) boundary Loss of material and Preventive Maintenance Pressure Stainless VII.J-15 3.3.1-94 400 Piping Air-indoor (ext) None None boundary steel (AP-17} 6

Attachment 1 NL-09-079 Page 44 of 51 Table 3.4.2-5-13-IP2 IP1 Station Air (SA) System ,

Aging Effect NUREG-Intended Aging Management Table 1 Component Type Function Material Environment Requiring Management Programs 1801 Vol. 2 Item Item Notes I Pressure Stainless Nooe NGAe VII.0-4 3.3.1-54 400 Piping Condensation (int) boundary steel Loss of material One-Time Ins~ection (AP-81) E Stainless NGAe NGAe VII.D-4 3.3.1-54 400 Strainer Filtration Condensation (int) steel Loss of material One-Time Ins~ection (AP-81 ) E Stainless NGAe NGAe VII.D-4 3.3.1-54 400 Strainer Filtration Condensation (ext) steel Loss of material One-Time Ins~ection (AP-81 ) E NGAe VII.D-3 3.3.1-57 400 Pressure NGAe Strainer housing Carbon steel Air-indoor (ext) External Surfaces (A-80) ~

boundary Loss of material Monitoring NGAe VII .D-2 3.3.1-53 400 Strainer housing Pressure Carbon steel Condensation (int)

NGAe Periodic Surveillance (A-26) E i

.*. boundary Loss of material and Preventive I Maintenance NGAe VII.D-3 3.3.1-57 400 Pressure NGAe Tank Carbon steel Air-indoor (ext) External Surfaces (A-80) ~

boundary Loss of material Monitoring NGAe VII.D-2 3.3.1-53 400 Tank .

Pressure Carbon steel Condensation (int)

NGAe Periodic Surveillance (A-26) E boundary Loss of material and Preventive Maintenance NGAe VII.D-3 3.3.1-57 400 Pressure NGAe (A-80)

Tubing Carbon steel Air-indoor (ext) External Surfaces ~

boundary Loss of material Monitoring

Attachment 1 NL-09-079 Page 45 of 51 Table 3.4.2-5-13-IP2 IP1 Station Air (SA) System Aging Effect NUREG-Component Type Intended Function Material Environment Requiring Management Aging Management Programs 1801 Vol. 2 Item Table 1 Item Notes I Nooe VILO-2 3.3.1-53 4Q3 Pressure Nooe Periodic Surveillance (A-26) £ Tubing Carbon steel Condensation (int) boundary Loss of material and Preventive Maintenance Pressure Stainless VILJ-15 3.3.1-94 4Q3 Tubing Air-indoor (ext) None None boundary steel (AP-17) A Pressure Stainless Nooe Nooe VILO-4 3.3.1-54 4Q3 Tubing Condensation (int) boundary steel Loss of material One-Time Ins(2ection (AP-S1 ) E Pressure V.F-3 3.2.1-53 4Q3 Tubing Copper alloy Air-indoor (ext) None None boundary (EP-1O) C Nooe VILG-9 3.3.1-2S 4Q3 Pressure NGAe Periodic Surveillance (AP-78) £ i Tubing Copper alloy Condensation (int) boundary Loss of material and Preventive Maintenance NeRe VILO-3 3.3.1-57 4Q3 Pressure NGAe Trap Carbon steel Air-indoor (ext) External Surfaces (A-SO) 6 boundary Loss of material Monitoring NeRe VILO-2 3.3.1-53 4Q3 Pressure NGAe Periodic Surveillance (A-26) £ Trap Carbon steel Condensation (int) boundary Loss of material and Preventive Maintenance Nooe VILO-3 3.3.1-57 4Q3 Pressure NGAe (A-SO)

Valve body boundary Carbon steel Air-indoor(ext)

Loss of material External Surfaces 6 Monitoring

Attachment 1 NL-09-079 Page 46 of 51 Table 3.4.2-5-13-IP2 IP1 Station Air (SA) System Aging Effect NUREG-Intended Aging Management Table 1 Component Type Material Environment Requiring 1801 Vol. 2 Notes Function Programs Item Management Item NGAe VII. 0-2 3.3.1-53 4Q8 Pressure NGAe Periodic Surveillance (A-26) £ Valve body Carbon steel Condensation (int) boundary loss of material and Preventive Maintenance Pressure Stainless VILJ-15 3.3.1-94 4Q8 Valve body Air-indoor (ext) None None (AP-17} A boundary steel Pressure Stainless NGAe NGAe VILo-4 3.3.1-54 4Q8 Valve body Condensation (int) (AP-81 ) E boundary steel Loss of material One-Time Insl2ection Pressure V.F-3 3.2.1-53 4Q8 Valve body Copper alloy Air-indoor (ext) None None (EP-10) C boundary NGAe VILG-9 3.3.1-28 4Q8 Valve body Pressure Copper alloy Condensation (int)

NGAe Periodic Surveillance (AP-78) £ boundary loss of material and Preventive Maintenance

./

Attachment 1 NL-09-079 Page 47 of 51 As a result of the previous table changes, the following changes are required to Appendix A (Changes are shown as strikethroughs for deletions and underlines for additions).

A.2.1.26 One-Time Inspection Program One-time inspection activities on the following confirm that loss of material is not occurring or is so insignificant that an aging management program is not warranted.

• internal surfaces of stainless steel drain piping,.piping elements and components containing raw water (drain water)

• internal surfaces of stainless steel piping, piping elements and components in the station air containment penetration exposed to condensation

• Internal surfaces of stainless steel piping. tubing. strainers and valve bodies in the IP1 station air system exposed to condensation

• internal surfaces of stainless steel EDG starting air tanks, piping, piping elements and components exposed to condensation

• internal surfaces of carbon steel and stainless steel tanks, piping, piping elements and components in ,

the RCP oil collection system exposed to lube oil

• internal surfaces of auxiliary feedwater system stainless steel piping, piping elements and components exposed to treated water from the city water system A.2.1.28 Periodic Surveillance and Preventive Maintenance Program The Periodic Surveillance and Preventive Maintenance Program is an existing program that includes periodic inspections and tests that manage aging effects not managed by other aging management programs. In addition to specific activities in the plant's preventive maintenance program and surveillance program, the Periodic Surveillance and Preventive Maintenance Program includes enhancements to add new activities. The preventive maintenance and surveillance testing activities are generally implemented through repetitive tasks or routine monitoring of plant operations.

Surveillance testing and periodic inspections using visual or other non-destructive examination techniques verify that the following components are capable of performing their intended function.

• reactor building cranes (polar and manipulator), crane rails, and girders, and refueling platform

• recirculation pump motor cooling coils :and housing

• city water system components

• charging pump casings

• plant drain components and backwater valves

• station air containment penetration piping

• HVAC duct flexible connections

• HVAC stored portable blowers and flexible trunks

• EDG exhaust components

Attachment 1 NL-09-079 Page 48 of 51

• EDG duct flexible connections

• EDG air intake and aftercooler components

• EDG air start components

• EDG cooling water makeup supply valves

• security generator exhaust components

• security generator radiator tubes

• SSC/Appendix R diesel exhaust components

• SSC/Appendix R diesel turbochargers and aftercoolers

• SSC/Appendix R diesel cooling water heat exchangers

• SSC/Appendix R diesel fuel oil cooler

• diesel fuel oil trailer transfer tank and associated valves

• auxiliary feedwater components

• containment cooling duct flexible connections

• containment cooling fan units internals

• control room HVAC condensers and evaporators

• control room HVAC ducts and drip pans

• control room HVAC duct flexible connections

• circulating water, city water, intake structure system, emergency diesel generator, fresh water cooling, instrument air, integrated liquid waste handling, lube oil, miscellaneous, radiation monitoring, river water, station air, waste disposal, wash water, and water treatment plant system piping, piping components, and piping elements

• pressurizer relief tank

• main steam safety valve tailpipes .

• atmospheric dump valve silencers

• feedwater system sight glass,housings

• off-site power feeder, 138 kV underground transmission cable

• main condenser tube internal surfaces

• instrument air aftercooler tube internal surfaces

• fresh water/river water heat exchanger internal and external surfaces A.2.1.39 Water Chemistry Control - Closed Cooling w.ater Program The Water Chemistry Control - Closed Cooling Water Program is an existing program that includes preventive measures that manage loss of material, cracking, or fouling for components in closed cooling water systems (component cooling water (CCW), instrument air (IP2 only), conventional closed cooling (CCC), instrument air closed cooling (IACC), emergency diesel generator cooling, security generator cooling, and SSC/Appendix R diesel generator cooling). These chemistry activities provide for monitoring and controlling closed cooling water chemistry using procedures and processes based on EPRI guidance for closed cooling water chemistry.

Attachment 1 NL-09-079 Page 49 of 51 As a result of the previous table changes, the following changes are required to Appendix B (Changes are shown as strikethroughs for deletions and underlines for additions).

8.1.27 One-Time Inspection Program pescription One-time inspection activities on the following confirm that loss of material is not occurring or is so insignificant that an aging management program is not warranted.

• Internal surfaces of drain system stainless steel piping, tubing, and valve bodies exposed to raw water (drain water) in EDG buildings, primary auxiliary buildings, and electrical tunnels. Also included are drains in the IP3 auxiliary feed pump building

• Internal surfaces of stainless steel valve bodies in the station air containment penetration exposed to condensation

• Internal surfaces of stainless steel piping, tubing. strainers and valve bodies in the IP1 station air system exposed to condensation

• Internal surfaces of stainless steel piping, strainers, strainer housings, tanks, tubing and valve bodies exposed to condensation in the emergency diesel generator (EDG) starting air subsystem 8.1.29 Periodic Surveillance and Preventive Maintenance program pescription The Periodic Surveillance and Preventive Maintenance Program is an existing program that includes periodic inspections and tests.that manage aging effects not managed by other aging management programs. In addition to specific activities in the plant's preventive maintenance program and surveillance program, the Periodic Surveillance and Preventive Maintenance Program includes enhancements to add new activities. The preventive maintenance and .

surveillance testing activities are generally implemented through repetitive tasks or routine monitoring of plant operations. Credit for program activities has been taken in the aging management review of the following systems and structures. All activities are new unless otherwise noted.

Reactor building Use visual or other NDE techniques to inspect the surface condition of carbon steel components of the reactor building cranes (polar and manipulator), crane rails, and girders, and refueling platform to manage loss of material. [existing]

Containment spray system IP3: Perform wall thickness measurements of the NaOH tank to manage loss of material. [existing}

IP3: Perform visual or other NDE inspections on the inside

Attachment 1 NL-09-079 Page 50 of 51 surfaces of a representative sample of stainless steel components exposed to sodium hydroxide to manage loss of material and cracking.

Safety injection system Perform operability testing to manage fouling for recirculation pump motor cooling coils.

Use visual or other NDE techniques to internally inspect the recirculation pump cooler housing to manage loss of material.

Main steam system Use visual or other NDE techniques to inspect a representative sample of the internal surfaces of the carbon steel main steam safety valve tailpipes and atmospheric dump valve silencers to manage loss of material.

Circulating water system Use visual or other NDE techniques to inspect a representative sample of the internals of circulating water piping. piping elements and components exposed to raw water to manage loss of material, cracking and change in material properties.

City water system Use visual or other NDE techniques to inspect a representative sample of the internals of city water piping, piping elements, and components exposed to treated water (city water) to manage loss of material.

Condensate system Use visual or other NDE techniques to inspect a representative sample of the internal surfaces of the main condenser tubes exposed to raw water to manage loss of material and fouling.

River water system Use visual or other NDE techniques to inspect a representative sample of the internals of river water piping.

piping elements and components exposed to raw water to manage loss of material and cracking.

Fresh water cooling system Use visual or other NDE techniques to inspect a representative sample of the internal and external surfaces of the fresh water/river water heat exchanger tubes exposed to raw water to manage loss of material and fouling.

Attachment 1 NL-09-079 Page 51 of 51 Wash water system Use visual or other NDE techniques to inspect a representative sample of the internals of wash water piping.

piping elements and components exposed to raw water to manage loss of material. cracking and change in material properties.

Chemical and volume During quarterly surveillances perform visual inspection of control system the external surface of charging pump casings to manage cracking. [existing]

Plant drains Use visual or other NDE techniques to inspect a representative sample of the internals of carbon steel plant drain piping, piping elements, and components to manage loss of material.

IP2: Use visual or other NDE techniques to inspect the internals of backwater valves to manage loss of material.

[existing]

Station air system Use visual or other NDE techniques to inspect a representative sample of containment penetration piping and the internals and externals of station air piping. piping elements and components to manage loss of material.

Use visual or other NDE techniques to inspect a representative sample of the internals of station air piping.

piping elements and components exposed to raw water to manage loss of material and cracking.

Instrument air system Use visual or other NDE techniques to internally inspect the heat exchanger tubes on the instrument air aftercoolers to manage loss of material and fouling.

ATTACHMENT 2 TO NL-09-079 List of Regulatory Commitments, Revision 9 ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 & 3 DOCKET NOS. 50-247 AND 50-286

Attachment 2 NL-09'-079 Page 1 of 17 List of Regulatory Commitments Rev. 9 The following table identifies those actions committed to by Entergy in this document.

Changes are shown as strikethroughs for deletions and underlines for additions.

1. COMMITMENT IMPLEMENTATION SOURCE RELATED SCHEDULE LRASECTION I AUDIT ITEM IP2: NL-07-039 A.2.1.1 1 Enhance the Aboveground Steel Tanks Program for

~eptember 28, A.3.1.1 IP2 and IP3 to perform thickness measurements of 12013 B.1.1 the bottom surfaces of the condensate storage tanks, city water tank, and fire water tanks once during the IP3:

first ten years of the period of extended operation.

December 12, Enhance the Aboveground Steel Tanks Program for 2015 IP2 and IP3 to require trending of thickness measurements when material loss is detected.

IP2: NL-07-039 A.2.1.2 2 Enhance the Bolting Integrity Program for IP2 and IP3

~eptember 28, A.3.1.2 to clarify that actual yield strength is used in selecting 12013 B.1.2 materials for low susceptibility to SCC and clarify the prohibition on use of lubricants containing MoS 2 for IP3: NL-07-153 Audit Items bolting.

December 12, 201,241, The Bolting Integrity Program manages loss of 12015 270 preload and loss of material for all external bolting.

IP2: NL-07-039 A.2.1.5 3 Implement the Buried Piping and Tanks Inspection

~eptember 28, A.3.1.5 Program for IP2 and IP3 as described in LRA Section 12013 B.1.6 B.1.6.

NL-07-153 Audit Item This new program will be implemented consistent with IP3: 173 the corresponding program described in NUREG- December 12, 1801 Section XI.M34, Buried Piping and Tanks 12015 Inspection.

Attachment 2 NL-09-079 Page 2 of 17

1. COMMITMENT IMPLEMENTATION SOURCE RELATED SCHEDULE LRASECTION I AUDIT ITEM IP2: NL-07-039 A.2.1.B 4 Enhance the Diesel Fuel Monitoring Program to September 2B, A.3.1.B include cleaning and inspection of the IP2 GT-1 gas

~013 S.1.9 turbine fuel oil storage tanks, IP2 and IP3 EDG fuel oil NL-07-153 Audit items day tanks, IP2 SSO/Appendix R diesel generator fuel IP3: 12B, 129, oil day tank, and IP3 Appendix R fuel oil storage tank December 12, 132, and day tank once every ten years.

~015 NL-OB-057 491,492, Enhance the Diesel Fuel Monitoring Program to 510 include qu~rterly sampling and analysis of the IP2 SSO/Appendix R diesel generator fuel oil day tank, IP2 security diesel fuel oil storage tank, IP2 security diesel fuel oil day tank, and IP3 Appendix R fuel oil storage tank. Particulates, water and sediment checks will be performed on the samples. Filterable solids acceptance criterion will be less than or equal to 10mg/1. Water and sediment acceptance criterion will be less than or equal to 0.05%.

Enhance the Diesel Fuel Monitoring Program to include thickness measurement of the bottom of the following tanks once every ten years. IP2: EDG fuel oil storage tanks, EDG fuel oil day tanks, SSO/Appendix R diesel generator fuel oil day tank, GT-1 gas turbine fuel oil storage tanks, and diesel fire pump fuel oil storage tank; IP3: EDG fuel oil day tanks, EDG fuel oil storage tanks, Appendix R fuel oil storage tank, and diesel fire pump fuel oil storage tank.

Enhance the Diesel Fuel Monitoring Program to change the analysis for water and particulates to a quarterly frequency for the following tanks. IP2: GT-1 gas turbine fuel oil storage tanks and diesel fire pump fuel oil storage tank; IP3: Appendix R fuel oil day tank and diesel fire pump fuel oil storage tank.

Enhance the Diesel Fuel Monitoring Program to specify acceptance criteria for thickness measurements of the fuel oil storage tanks within the scope of the program.

Enhance the Diesel Fuel Monitoring Program to direct samples be taken and include direction to remove water when detected.

Revise applicable procedures to direct sampling of the onsite portable fuel oil contents prior to transferring the contents to the storage tanks.

Attachment 2 NL-09-079 Page 3 of 17

1. COMMITMENT IMPLEMENTATION SOURCE RELATED SCHEDULE LRASECTION I AUDIT ITEM Enhance the Diesel Fuel Monitoring Program to direct the addition of chemicals including biocide when the presence of biological activity is confirmed.

IP2: NL-07-039 A.2.1.10 5 Enhance the External Surfaces Monitoring Program September 28, A.3.1.10 for IP2 and IP3 to include periodic inspections of 2013 8.1.11 systems in scope and subject to aging management review for license renewal in accordance with 10 CFR IP3:

54.4(a)(1) and (a)(3). Inspections shall include areas December 12, surrounding the subject systems to identify hazards to 2015 those systems. Inspections of nearby systems that could impact the subject systems will include SSCs that are in scope and subject to aging management review for license renewal in accordance with 10 CFR 54.4(a)(2).

IP2: NL-07-039 A.2.1.11 6 Enhance the Fatigue Monitoring Program for IP2 to September 28, A.3.1.11 monitor steady state cycles and feedwater cycles or

~013 8.1.12, perform an evaluation to determine monitoring is not NL-07-153 Audit Item required. Review the number of allowed events and 164 resolve discrepancies between reference documents and monitoring procedures.

Enhance the Fatigue Monitoring Program for IP3 to IP3:

include all the transients identified. Assure all fatigue December 12, analysis transients are included with the lowest ~015 limiting numbers. Update the number of design transients accumulated to date.

Attachment 2 NL-09-079 Page 4 of 17

1. COMMITMENT IMPLEMENTATION SOURCE RELATED SCHEDULE LRASECTION I AUDIT ITEM IP2: NL-07-039 A.2.1.12 7 Enhance the Fire Protection Program to inspect September 28, A.3.1.12 external surfaces of the IP3 RCP oil collection 2013 8.1.13 systems for loss of material each refueling cycle.

Enhance the Fire Protection Program to explicitly IP3:

state that the IP2 and IP3 diesel fire pump engine December 12, sub-systems (including the fuel supply line) shall be [2015 observed while the pump is running. Acceptance criteria will be revised to verify that the diesel engine does not exhibit signs of degradation while running; such as fuel oil, lube oil, coolant, or exhaust gas leakage.

Enhance the Fire Protection Program to specify that the IP2 and IP3 diesel fire pump engine carbon steel exhaust components are inspected for evidence of corrosion and cracking at least once each operating cycle.

Enhance the Fire Protection Program for IP3 to visually inspect the cable.spreading room, 480V switchgear room, and EDG room CO2 fire suppression system for signs of degradation, such as corrosion and mechanical damage at least once every six months.

Attachment 2 NL-09-079 Page 5 of 17

1. . COMMITMENT IMPLEMENTATION SOURCE RELATED SCHEDULE LRASECTION I AUDIT ITEM IP2: NL-07-039 A.2.1.13 8 Enhance the Fire Water Program to include inspection lSeptember 28, A.3.1.13 of IP2 and IP3 hose reels for evidence of corrosion.

~013 8.1.14 Acceptance criteria will be revised to verify no NL-07-153 Audit Items unacceptable signs of degradation.

IP3: 105, 106 Enhance the Fire Water Program to replace all or test December 12, NL-08-014 a sample of IP2 and IP3 sprinkler heads required for ~015 10 CFR 50.48 using guidance of NFPA 25 (2002 edition), Section 5.3.1.1.1 before the end of the 50-year sprinkler head service life and at 10-year intervals thereafter during the extended period of operation to ensure that signs of degradation, such as corrosion, are detected in a timely manner.

Enhance the Fire Water Program to perform wall thickness evaluations of IP2 and IP3 fire protection piping on system components using non-intrusive techniques (e.g., volumetric testing) to identify evidence of loss of material due to corrosion. These inspections will be performed before the end of the current operating term and at intervals thereafter during the period of extended operation. Results of the initial evaluations will be used to determine the appropriate inspection interval to ensure aging effects are identified prior to loss of intended function.

Enhance the Fire Water Program to inspect the internal surface of foam based fire suppression tanks.

Acceptance criteria will be enhanced to verify no significant corrosion.

Attachment 2 NL-09-079 Page 6 of 17

1. COMMITMENT IMPLEMENTATION SOURCE RELATED SCHEDULE LRASECTION I AUDIT ITEM IP2: NL-07-039 A.2.1.15 9 Enhance the Flux Thimble Tube Inspection Program iSeptember 28, A.3.1.15 for IP2 and IP3 to implement comparisons to wear

~O13 8.1.16 rates identified in WCAP-12866. Include provisions to compare data to the previous performances and IP3:

perform evaluations regarding change to test December 12, frequency and scope.

~O15 Enhance the Flux Thimble Tube Inspection Program for IP2 and IP3 to specify the acceptance criteria as outlined in WCAP-12866 or other plant-specific values based on evaluation of previous test results.

Enhance the Flux Thimble Tube Inspection Program for IP2 and IP3 to direct evaluation and performance of corrective actions based on tubes that exceed or are projected to exceed the acceptance criteria. Also

. stipulate that flux thimble tubes that cannot be inspected over the tube length and cannot be shown by analysis to be satisfactory for continued service, must be removed from service to ensure the integrity of the reactor coolant system pressure boundary.

Attachment 2 NL-09-079 Page 7 of 17

1. COMMITMENT IMPLEMENTATION SOURCE RELATED SCHEDULE LRASECTION I AUDIT ITEM IP2: NL-07-039 A.2.1.16 10 Enhance the Heat Exchanger Monitoring Program for September 28, A.3.1.1.6 IP2 and IP3 to include the following heat exchangers 2013 8.1.17, in the scope of the program.

NL-07-153 Audit Item

• Safety injection pump lube oil heat exchangers IP3: 52 December 12,

• RHR heat exchangers 2015

• RHR pump seal coolers

• Non-regenerative heat exchangers

• Charging pump seal water heat exchangers

• Charging pump fluid drive coolers

• Charging pump crankcase oil coolers

• Spent fuel pit heat exchangers

• Secondary system steam generator sample coolers

• Waste gas compressor heat exchangers

• SSO/Appendix R diesel jacket water heat exchanger (IP2 only)

Enhance the Heat Exchanger Monitoring Program for IP2 and IP3 to perform visual inspection on heat exchangers where non-destructive examination, such as eddy current inspection, is not possible due to heat exchanger design limitations.

Enhance the Heat Exchanger Monitoring Program for IP2 and IP3 to include consideration of material-environment combinations when determining sample population of heat exchangers.

Enhance the Heat Exchanger Monitoring Program for IP2 and IP3 to establish minimum tube wall thickness for the new heat exchangers identified in the scope of the program. Establish acceptance criteria for heat exchangers visually inspected to include no indication of tube erosion, vibration wear, corrosion, pitting, NL-09-018 fouling, or scaling.

Attachment 2 NL-09-079 Page 8 of 17

1. COMMITMENT IMPLEMENTATION SOURCE RELATED SCHEDULE LRASECTION I AUDIT ITEM 11 Delete commitment. ~ Nb Q1 Q39 A.2.~.H I..... ..... ')0

, A.3.~.H ERRaRse tRe lSI PFe)Fam feF IP2 aRe IP3 te I3Fe\liee ~ 8.~.HJ l3eFieeis I.lisl:jal iRsl3estieRs te seRfiFm tRe aBseRse ef Nb Q1 ~53 Al:jeit item a)iR) effeGts feF Il:jBFite slieiR) Sl:jl3l3erts l:jsee iR tRe ~ as steam )eRemteF aRe FeasteF ceelaRt l3l:jml3 Sl:jl3l3ert In"" .L. 'I')

, NL-09-056 systems. ~

IP2: NL-07-039 A.2.1.18 12 Enhance the Masonry Wall Program for IP2 and IP3 September 28, A.3.1.18 to specify that the IP1 intake structure is included in 2013 B.1.19 the program.

IP3:

December 12,

~015 Enhance the Metal-Enclosed Bus Inspection Program IP2: NL-07-039 A.2.1.19 13 to add IP2 480V bus associated with substation A to September 28, A.3.1.19 the scope of bus inspected. ~013 B.1.20 NL-07-153 Audit Items Enhance the Metal-Enclosed Bus Inspection Program IP3: 124, for IP2 and IP3 to visually inspect the external surface December 12, NL-08-057 133,519 of MEB enclosure assemblies for loss of material at ~015 least once every 10 years. The first inspection will occur prior to the period of extended operation and the acceptance criterion will be no significant loss of material.

Enhance the Metal-Enclosed Bus Inspection Program to add acceptance criteria for MEB internal visual inspections to include the absence of indications of dust accumulation on the bus bar, on the insulators, and in the duct, in addition to the absence of indications of moisture intrusion into the duct.

Enhance the Metal-Enclosed Bus Inspection Program for IP2 and IP3 to inspect bolted connections at least once every five years if performed visually or at least once every ten years using quantitative measurements such as thermography or contact resistance measurements. The first inspection will

\

. occur prior to the period of extended operation.

The plant will process a change to applicable site procedure to remove the reference to lire-torquing" connections for phase bus maintenance and bolted connection maintenance.

Attachment 2 NL-09-079 Page 9 of 17

1. COMMITMENT IMPLEMENTATION SOURCE RELATED SCHEDULE LRASECTION I AUDIT ITEM IP2: NL-07-039 A.2.1.21 14 Implement the Non-EQ Bolted Cable Connections September 28, A.3.1.21 Program for IP2 and IP3 as described in LRA Section 2013 B.1.22 B.1.22.

IP3:

December 12, 2015 IP2: NL-07-039 A.2.1.22 15 Implement the Non-EQ Inaccessible Medium-Voltage September 28, A.3.1.22 Cable Program for IP2 and IP3 as described in LRA 2013 B.1.23 Section B.1.23.

NL-07-153 Audit item This new program will be implemented consistent with IP3: 173 the corresponding program described in NUREG- December 12, 1801 Section XLE3, Inaccessible Medium-Voltage 2015 Cables Not Subject To 10 CFR 50.49 Environmental Qualification Requirements.

IP2: NL-07-039 A.2.1.23 16 Implement the Non-EQ Instrumentation Circuits Test September 28, A.3.1.23 Review Program for IP2 and IP3 as described in LRA 2013 B.1.24 Section B.1.24.

NL-07-153 Audit item This new program will be implemented consistent with IP3: 173 the corresponding program described in NUREG- December 12, 1801 Section XLE2, Electrical Cables and 2015 Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits.

IP2: NL-07-039 A.2.1.24 17 Implement the Non-EQ Insulated Cables and September 28, A.3.1.24 Connections Program for IP2 and IP3 as described in 2013 B.1.25 LRA Section B.1.25.

NL-07-153 Audit item This new program will be implemented consistent with IP3: 173 the corresponding program described in NUREG- December 12, 1801 Section XLE1, Electrical Cables and ~015 Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements.

Attachment 2 NL-09-079 Page 10 of 17

1. COMMITMENT IMPLEMENTATION SOURCE RELATED SCHEDULE LRASECTION I AUDIT ITEM IP2: NL-07-039 A.2.1.25 18 Enhance the Oil Analysis Program for IP2 to sample September 28, A.3.1.25 and analyze lubricating oil used in the SBO/Appendix 2013 B.1.26 R diesel generator consistent with oil analysis for other site diesel generators.

IP3:

Enhance the Oil Analysis Program for IP2 and IP3 to December 12, sample and analyze generator seal oil and turbine 2015 hydraulic control oil.

Enhance the Oil Analysis Program for IP2 and IP3 to formalize preliminary oil screening for water and particulates and laboratory analyses including defined acceptance criteria for all components included in the scope of this program. The program will specify corrective actions in the event acceptance criteria are not met.

Enhance the Oil Analysis Program for IP2 and IP3 to formalize trending of preliminary oil screening results as well as data provided from independent .

laboratories.

IP2: NL-07-039 A.2.1.26 19 Implement the One-Time Inspection Program for IP2 September 28, A.3.1.26 and IP3 as described in LRA Section 8.1.27.

~013 B.1.27 This new program will be implemented consistent with NL-07-153 Audit item the corresponding program described in NUREG- IP3: 173 1801,Section XI.M32, One-Time Inspection. December 12,

~015 IP2: NL-07-039 A.2.1.27 20 Implement the One-Time Inspection - Small Bore September 28, A.3.1.27 Piping Program for.IP2 and IP3 as described in LRA

~013 B.1.28 Section B.1.28.

NL-07-153 Audit item This new program will be implemented consistent with IP3: 173 the corresponding program described in NUREG- December 12, 1801,Section XI.M35, One-Time Inspection of ASME ~015 Code Class I Small-Bore Piping___

IP2: NL-07-039 A.2.1.28 21 Enhance the Periodic Surveillance and Preventive September 28, A.3.1.28 Maintenance Program for IP2 and IP3 as necessary

~013 B.1.29 to assure that the effects of aging will be managed such that applicable components will continue to IP3:

perform their intended functions consistent with the December 12, current licensing basis through the period of extended

~015 operation.

Attachment 2 NL-09-079 Page 11 of 17

1. COMMITMENT IMPLEMENTATION SOURCE RELATED SCHEDULE . LRA SECTION I AUDIT ITEM IP2: NL-07-039 A.2.1.31 22 Enhance the Reactor Vessel Surveillance Program for September 28, A.3.1.31 IP2 and IP3 revising the specimen capsule withdrawal 2013 8.1.32 schedules to draw and test a standby capsule to cover the peak reactor vessel fluence expected IP3:

through the end of the period of extended operation.

December 12, Enhance the Reactor Vessel Surveillance Program for ~015 IP2 and IP3 to require that tested and untested specimens from all capsules pulled from the reactor vessel are maintained in storage.

IP2: NL-07-039 A.2.1.32 23 Implement the Selective Leaching Program for IP2

~eptember 28, A.3.1.32 and IP3 as described in LRA Section 8.1.33.

~013 8.1.33 This new program will be implemented consistent with NL-07-153 Audit item the corresponding program described in NUREG- IP3: 173 1801, SectionXI.M33 Selective Leaching of Materials. December 12, 2015 IP2: NL-07-039 A.2.1.34 24 Enhance the Steam Generator Integrity Program for

~eptember 28, A.3.1.34 IP2 and IP3 to require that the results of the condition

~013 8.1.35 monitoring assessment are compared to the operational assessment performed for the prior IP3:

operating cycle with differences evaluated.

December 12,

~015 Enhance the Structures Monitoring Program to IP2: NL-07-039 A.2.1.35 25 explicitly specify that the following structures are September 28, A.3.1.35 included in the program. ~013 8.1.36

• Appendix R diesel generator foundation (IP3) NL-07-153 v

• Appendix R diesel generator fuel oil tank vault IP3: Audit items (IP3) December 12, 86,87,88,

• Appendix R diesel generator switchgear and ~015 NL-08-057 417 enclosure (IP3)

• city water storage tank foundation

• condensate storage tanks foundation (lP3)

• containment access facility and annex (IP3)

• discharge canal (IP2/3)

• emergency lighting poles and foundations (IP2/3)

• fire pumphouse (IP2)

• fire protection pumphouse (IP3)

• fire water storage tank foundations (IP2/3)

• gas turbine 1 fuel storage tank foundation

• maintenance and outage building-elevated passageway (IP2) \

Attachment 2 NL-09-079 Page 12 of 17

1. COMMITMENT IMPLEMENTATION SOURCE RELATED SCHEDULE LRASECTION I AUDIT ITEM

• new station security building (IP2)

• nuclear service building (IP1)

• primary water storage tank foundation (IP3)

• refueling water storage tank foundation (IP3)

• security access and office building (IP3)

• service water pipe chase (IP2/3)

• service water valve pit (IP3)

• superheater stack

• transformerlswitchyard support structures (IP2)

• waste holdup tank pits (IP2/3)

Enhance the Structures Monitoring Program for IP2 and IP3 to clarify that in addition to structural steel and concrete, the following commodities (including their anchorages) are inspected for each structure as applicable.

• cable trays and supports

• concrete portion of reactor vessel supports

• conduits and supports

• cranes, rails and girders

• equipment pads and foundations

• fire proofing (pyrocrete)

• HVAC duct supports

• jib cranes

• manholes and duct banks

• manways, hatches and hatch covers

• monorails

• new fuel storage racks

• sumps, sump screens, strainers and flow barriers Enhance the Structures Monitoring Program for IP2 and IP3 to inspect inaccessible concrete areas that are exposed by excavation for any reason. IP2 and IP3 will also inspect inaccessible concrete areas in environments where observed conditions in accessible areas exposed to the same environment indicate that significant concrete degradation is occurring.

Enhance the Structures Monitoring Program for IP2 and IP3 to perform inspections of elastomers (seals, gaskets, seismic joint filler, and roof elastomers) to

Attachment 2 NL-09-079 Page 13 of 17

1. COMMITMENT IMPLEMENTATION SOURCE RELATED SCHEDULE LRASECTION I AUDIT ITEM identify cracking and change in material properties and for inspection of aluminum vents and louvers to identify loss of material.

Enhance the Structures Monitoring Program for IP2 NL-08-127 Audit Item and IP3 to perform an engineering evaluation of 360 groundwater samples to assess aggressiveness of groundwater to concrete on a periodic basis (at least once every five years). IPEC will obtain samples from at least 5 wells that are representative of the ground water surrounding below-grade site structures and perform an engineering evaluation of the results from those samples for sulfates, pH and chlorides.

Additionally, to assess potential indications of spent fuel pool leakage, IPEC will sample for tritium in groundwater wells in close proximity to the IP2 spent fuel pool at least once every 3 months.

Enhance the Structures Monitoring Program for IP2 and IP3 to perform inspection of normally submerged concrete portions of the intake structures at least once every 5 years. Inspect the baffling/grating partition and support platform of the IP3 intake structure at least once every 5 years.

Enhance the Structures Monitoring Program for IP2 Audit Item and IP3 to perform inspection of the degraded areas 358 of the water control structure once per 3 years rather than the normal frequency of once per 5 years during the PE~. I IP2: NL-07-039 A.2.1.36 26 Implement the Thermal Aging Embrittlement of Cast September 28, A.3.1.36 Austenitic Stainless Steel (CASS) Program for IP2 and IP3 as described in LRA Section 8.1.37. ~013 8.1.37 NL-07-153 Audit item This new program will be implemented consistent with IP3: 173 the corresponding program described in NUREG- December 12, 1801,Section XI.M12, Thermal Aging Embrittlement 12015 of Cast Austenitic Stainless Steel (CASS) Program.

Attachment 2 NL-Q9-Q79

• . Page 14 of 17

1. COMMITMENT IMPLEMENTATION SOURCE . RELATED SCHEDULE '. LRA SECTION

- I AUDIT ITEM IP2: NL-Q7-Q39 A2.1.37 27 Implement the Thermal Aging and Neutron Irradiation S~ptember 28, A.3.1.37 Embrittlement of Cast Austenitic Stainless Steel 2Q13 . . B.1.38 (CASS) Program for IP2 and IP3 as described in LRA NL-Q7-153 Audit item Section B.1.38.

IP3: 173 This new program will be implemented consistent with December 12, the corresponding program described in NUREG- 2015 180.1 Section XI.M13, Thermal Aging and Neutron Embrittlement of Cast Austenitic Stainless Steel (CASS) Program. .

IP2: NL-Q7-Q39 A.2.1.39 28 Enhance the Water Chemistry Control - Closed September 28, A.3.1.39 Cooling Water Program to maintain water chemistry of 20.13 . B.1.4Q ttie IP2 SBO/Appendix R diesel generator cooling ' .

NL-Q8-Q57 Audit item system per EPRI guidelines.

IP.3: 50.9 Enhance the Water ChemistrY Control - Closed . December 12, .'

. Cooling Water Program to maintain the IP2 and IP3 20.15 ,

security generator and fire protection diesel cooling water pH and glycol within limits specified by EPRI .

guidelines.

IP2: NL-Q7-Q39 A.2 .1.4Q 29 Enhance the Water Chemistry Control - Primary and September 28, B.1.41 Secondary Program for IP2 to test sulfates monthly in 20.13 the RWST with a limit of <150. ppb.

IP2: NL-Q7-Q39 . A.2 .1.41

30. For aging management of the reactor vessel internals, S~ptember 28, A.3.1.41 IPEC will (1) participate in the industry programs for 20.11 investigating and managing aging effects on reactor internals; (2) evaluate and implement the results of IP3:

the industry programs .as applicable to the reactor December 12, .

internals; and (3) upon completion of these programs, . 20.13 '

but not less than 24 months before entering the .period of extended operation, submit an inspection plan for reactor internals to the NRC for review and apprqval.

' IP2:

• NL-Q7-Q39 A:2.2,1 ,2 31 Additional P-T curves*will be submitted as required September 28, A.3.2.1.2 per 10. CFR 50., Appendix G prior to the period of 20.13 4.2.3 extended operation as part ofthe Reactor Vessel Surveillance Program.

IP3:

December 12, 20.15 As required by 10. CFR 50..61 (b)(4) , IP3 will submit a IP3: NL-Q7-Q39 A.3.2.1.4 32 plant-specific safety analysis for plate B28Q3-3 to the ' De.cember 12, 4.2.5 NRC three years prior to reaching the RTPTS , 20.'15 . NL:'Q8-127

.screening criterion. Alternatively, the site may choose to implement the revised PTS rule when approved . .

Attachment 2 NL-09-079 Page 15 of 17

1. COMMITMENT IMPLEMENTATION SOURCE RELATED SCHEDULE LRASECTION I AUDIT ITEM IP2: NL-07-039 A.2.2.2.3 33 At least 2 years prior to entering the period of September 28, A.3.2.2.3 extended operation, for the locations identified in LRA

~011 4.3.3 Table 4.3-13 (IP2) and LRA Table 4.3-14 (IP3), under NL-07-153 Audit item the Fatigue Monitoring Program, IP2 and IP3 will IP3: 146 implement one or more of the following:

December 12, NL-08-021 (1) Consistent with the Fatigue Monitoring Program, ~013 Detection of Aging Effects, update the fatigue usage calculations using refined fatigue analyses to determine valid CUFs less than 1.0 when accounting for the effects of reactor water environment. This includes applying the appropriate Fen factors to valid CUFs determined in accordance with one of the following:

1. For locations in LRA Table 4.3-13 (IP2) and LRA Table 4.3-14 (IP3), with existing fatigue analysis valid for the period of extended operation, use the existing CUF.

2. Additional plant-specific locations with a valid CUF may be evaluated. In particular, the pressurizer lower shell will be reviewed to ensure the surge nozzle remains the limiting component.

3. Representative CUF values from other plants, adjListed to or enveloping the IPEC plant specific external loads may be used if demonstrated applicable to IPEC.

4. An analysis using an NRC-approved version of theASME code or NRC-approved alternative (e.g., NRC-approved code case) lJ1ay be performed to determine a valid CUF.

(2) Consistent with the Fatigue Monitoring Program, Corrective Actions, repair or replace the affected locations before exceeding a CUF of 1.0.

April 30, 2008 NL-07-078 2.1.1.3.5 34 IP2 SSO I Appendix R diesel generator will be installed and operational by April 30, 2008. This Complete NL-08-074 committed change to the facility meets the requirements of 10 CFR 50.59(c)(1) and, therefore, a license amendment pursuant to 10 CFR 50.90 is not  :

required.  !

Attachment 2 NL-09-079 Page 16 of 17

1. COMMITMENT IMPLEMENTATION SOURCE RELATED SCHEDULE LRASECTION I AUDIT ITEM IP2: NL-08-127 Audit Item 35 Perform a one-time inspection of representative September 28, 27 sample area of IP2 containment liner affected by the 1973 event behind the insulation, prior to entering the 12013 extended period of operation, to assure liner degradation is not occurring in this area.

Perform a one-time inspection of representative IP3:

sample area of the IP3 containment steel liner at the December 12,

. juncture with the concrete floor slab, prior to entering 12015 the extended period of operation, to assure liner degradation is not occurring in this area.

Any degradation will be evaluated for updating of the NL-09-018 containment liner analyses as needed.

IP2: NL-08-127 Audit Item 36 Perform a one-time Inspection and evaluation of a September 28, 359 sample of potentially affected IP2 refueling cavity 12013 concrete prior to the period of extended operation.

The sample will be obtained by core boring the refueling cavity wall in an area that is susceptible to exposure to borated water leakage. The inspection will include an assessment of embedded reinforcing steel.

Additional core bore samples will be taken, if the NL-09-056 leakage is not stopped, prior to the end of the first ten years of the period of extended operation.

A samQle of leakage fluid will be anal~zed to NL-09-079 determine the comQosition of the fluid. If additional core samQles are taken Qrior to the end of the first ten

~ears of the Qeriod of extended ol2eration, a saml2le of leakaae fluid will be analvzed.

IP2: NL-08-127 Audit Item 37 Enhance the Containment Inservice Inspection (CII-September 28, 361 IWL) Program to include inspections of the 2013 containment using enhanced characterization of degradation (i.e., quantifying the dimensions of noted IP3:

indications through the use of optical aids) during the December 12, period of extended operation. The enhancement

~015 includes obtaining critical dimensional data of degradation where possible through direct measurement or the use of scaling technologies for photographs, and the use of consistent vantage points for visual inspections.

Attachment 2 NL-09-079 Page 17 of 17

1. COMMITMENT IMPLEMENTATION SOURCE RELATED SCHEDULE LRASECTION I AUDIT ITEM IP2: NL-08-143 4.2.1 38 For Reactor Vessel Fluence, should future core September 28, loading patterns invalidate the basis for the projected 2013 values of RTpts or CvUSE, updated calculations will .

be provided to the NRC.

IP3:

. December 12, 2015 J.P2:. NL-09-056 2.3.4.5 39 Install a fixed automatic fire suppression system for C'~~~ .* ~ .....

~

')0 IP2 in the Auxiliary Feedwater Pump Room.

~ NL-09-079