ML050330463

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License Renewal Application - Responses to NRC Requests for Additional Information Regarding Aging Management of Bolting
ML050330463
Person / Time
Site: Nine Mile Point  Constellation icon.png
Issue date: 01/20/2005
From: Spina J
Constellation Energy Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NMP1L 1919, TAC MC3272, TAC MC3273
Download: ML050330463 (48)
v • d • e


Text

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Constellation Energy

  • Nine Mile Point Nuclear Station RO. Box 63 Lycoming, New York 13093 January 20, 2005 NMP1L 1919 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Nine Mile Point Units 1 and 2 Docket Nos. 50-220 and 50-410 Facility Operating License Nos. DPR-63 and NPF-69 License Renewal Application - Responses to NRC Requests for Additional Information Regarding Aging Management of Bolting (TAC Nos. MC3272 and MC3273)

Gentlemen:

By letter dated May 26, 2004, Nine Mile Point Nuclear Station, LLC (NMPNS) submitted an application to renew the operating licenses for Nine Mile Point Units 1 and 2. The aging management review results for the Reactor Vessel, Internals, and Reactor Coolant Systems (Section 3.1 of the License Renewal Application) were subsequently revised in NMPNS supplemental letter NMPIL 1892 dated December 6, 2004.

In a letter dated December 21, 2004, the NRC requested additional information regarding the aging management review of bolting associated with the Reactor Vessel, Internals, and Reactor Coolant Systems, as well as other plant systems addressed in Sections 3.2, 3.3, 3.4, and 3.5 of the License Renewal Application. The NMPNS responses to these requests for additional information are provided in Attachments I through 4. Attachment 5 provides a list of the regulatory commitments associated with this submittal.

If you have any questions about this submittal, please contact Peter Mazzaferro, NMPNS License Renewal Project Manager, at (315) 349-1019.

Very tal yours, Ja s A. Spina ice President Nine Mile Point JAS/DEV/jm, Ai 61

Page 2 NMP1L 1919 STATE OF NEW YORK

TO WIT:

COUNTY OF OSWEGO I, James A. Spina, being duly sworn, state that I am Vice President Nine Mile Point, and that I am duly authorized to execute and file this supplemental information on behalf of Nine Mile Point Nuclear Station, LLC. To the best of my knowledge and belief, the statements contained in this submittal are true and correct. To the extent that these statements are not based on my personal knowledge, they are based upon information provided by other Nine Mile Point employees and/or consultants. Such information has been reviewed in accordance with company practice and I believe it to be reliable.

Subscribed and sworn before me, a Notary Public in and frthe State of New York and County of Oswego, this AC day of I

2005.

WITNESS my Hand and Notarial Seal:

SANDRIA OSA L NotarY Pubic0 S OSWork Notary Public No. OlOS6032276W Ouaflied in Oswego Qountv/5 My Commission Expires:

i

/

O/o b~ate Attachments:

1. Responses to NRC Requests for Additional Information (RAI) Regarding Aging Management of Bolting
2. Revisions to LRA Section 3 Tables Regarding Aging Management of Bolting
3. New LRA Sections A1.1.38 and A2.1.37, Bolting Integrity Program
4. New LRA Section B2. 1.36, Bolting Integrity Program
5. List of Regulatory Commitments cc:

Mr. S. J. Collins, NRC Regional Administrator, Region I Mr. G. K. Hunegs, NRC Senior Resident Inspector Mr. P. S. Tam, Senior Project Manager, NRR Mr. N. B. Le, License Renewal Project Manager, NRR Mr. J. P. Spath, NYSERDA

ATTACHMENT 1 Nine Mile Point Nuclear Station Responses to NRC Requests for Additional Information (RAI)

Regarding Aging Management of Bolting This attachment provides the Nine Mile Point Nuclear Station, LLC (NMPNS) responses to the requests for additional information contained in the NRC letter dated December 21, 2004, regarding aging management of bolting. Each NRC RAI is repeated, followed by the NMPNS response for Nine Mile Point Unit 1 (NMP1) and/or Nine Mile Point Unit 2 (NMP2), as applicable. Revisions to the License Renewal Application (LRA) are described where appropriate. The revisions are highlighted by shading unless otherwise noted.

Note: Section, table, and page numbers cited for LRA Section 3.1 refer to the revised version of LRA Section 3.1 that was submitted by NMPNS letter NMPIL 1892, dated December 6, 2004.

RAI T3. 1-1 In LRA Tables 3.1.]A&B, items 3. 1.LA &B-26, the applicant credited the Inservice Inspection (ISI) IJWB/I/D Program for bolting management. The GALL recommended the uise of X.M18,

'Bolting Integrity Program, "for managing of aging effects for safety-related bolts. The bolting integrity program described in XLM18 relies on the NRC recommendations and guidelines for comprehensive bolting integrity programs that are delineated in NUREG-1339. The XL.M18 program also relies on the industry s technical basis for the program and guidelines for material selection and testing, bolting preload control, inservice inspection (ISI), use of lubricant and sealant, plant operation and maintenance and evaluation of stnrctural integrity of bolted joints, as outlined in EPRINP-5679, with exception noted in NUREG-1339. The ISIprogramn only addressed one task described in the Bolting Integrity program. Please provide infornmation to explain how the remaining of all other tasks of the XI.Ml8prograrn are addressed by NMP arid NMP2.

Response

NMPNS has reevaluated its position regarding the treatment of closure bolting for NMP1 and NMP2 and is revising the credited aging management program from the ASME Section XI Inservice Inspection (Subsections IWB, IWC, IWD) Program to the Bolting Integrity Program.

The Bolting Integrity Program is being added to the LRA in the applicable sections and tables in Section 3 as well as Appendices A and B.

The Bolting Integrity Program is consistent with NUREG-1801,Section XI.M18, with exceptions and enhancements. One exception is that the NMPNS program does not include Page 1 of8

structural bolting within its scope since aging of this bolting will be managed under the Structures Monitoring Program (LRA Section B2.1.28) and the ASME Section XI Inservice Inspection (Subsection IWF) Program (LRA Section B2.1.25). The other exception is that monitoring of identified leakage from pressure retaining components (not covered by ASME Section XI) will be performed on a frequency considering the safety significance of the leaking component and the radiological conditions in the vicinity of the component. The enhancements to the Bolting Integrity Program include revisions to the implementing procedures to: (1) more clearly restrict the use of lubricants containing molybdenum disulfide; (2) clearly restrict the use of high-strength (>

250 ksi yield strength) bolts to only those applications that require it; (3) reference the evaluation method in Electric Power Research Institute (EPRI) NP-5769, Volume 2, as an acceptable method for assuring integrity of bolting material in component support applications; and (4) reference the EPRI reports (NP-5769 and TR-104213) and NLTREG-1339 as source documents for the implementing procedures, as appropriate. More information on the Bolting Integrity Program is being added to the LRA in new Sections Al.1.38, A2.1.37, and B2.1.36.

LRA Revisions Applicable sections in LRA Section 3 are revised to add the Bolting Integrity Program as an aging management program, as identified in the response to RAIs T3.1-2 and T3.1-3 below.

Applicable tables in LRA Section 3 are revised to identify the Bolting Integrity Program as the aging management program for bolting, as shown in Attachment 2.

New LRA Sections A1.1.38 and A2.1.37, and new Section B2.1.36, are added to describe the Bolting Integrity Program. These new LRA sections are shown in Attachments 3 and 4.

RAI T3.1-2 In Tables 3.1.1.A&B, 3.1.2.A&B of the LRA supplemiental letter dated Decenmber 6,2004, the applicant did not address aging effect of crack initiation and growtlhfor closure bolting (see pages 3.1-26, -36, -54, -57, -88, and -94) due to cyclic loading and/or stress corrosion cracking (SCC), which is identified in GALL. Please provide infornation to explain why the aging effect ofcracking was not addressed for the above item.

Response

This question refers to closure bolting in the Reactor Vessel Instrumentation System (LRA Table 3.1.2.A-3 (page 3.1-54) for NMP1 and Table 3.1.2.B-3 (page 3.1-88) for NMP2) and the Reactor Recirculation System (Table 3.1.2.A-4 (page 3.1-57) for NMPI and Table 3.1.2.B-4 (page 3.1-

94) for NMP2). These items are aligned with NUREG-1 801 Items IV.Cl.3-e, IV.C1.3-f, and IV.C1.3-g, corresponding to the aging effects/mechanisms of loss of material, loss of preload/stress relaxation, and cumulative fatigue damage, respectively, for reactor coolant pressure boundary valve closure bolting. Additionally, for the NMPI and NMP2 Reactor Recirculation Systems, these items are aligned with NUTREG-1801 Items IV.Cl.2-d, IV.Cl.2-e, and IV.Cl.2-f, corresponding to the aging effects/mechanisms of loss of material, loss of Page 2 of 8

preload/stress relaxation, and cumulative fatigue damage, respectively, for recirculation pump closure bolting. NUREG-1 801 does not identify crack initiation and growth due to cyclic loading or stress corrosion cracking for boiling water reactor (BWR) reactor coolant pressure boundary valve or recirculation pump closure bolting. The NMPNS results are, therefore, consistent with NUREG-1801.

The Aging Effect/Mechanism description provided for Item 3.1.1.A-26 in LRA Table 3.1.1.A (page 3.1-26), and for Item 3.1.1.B-26 in LRA Table 3.1.l.B (page 3.1-36), is generic wording taken from NUREG-1801, Volume 1, Table 1, line 26 (hence the -26 item number in LRA Tables 3.1.1.A and 3.1.1.B). The NUREG-1801, Volume 1, Table I line item associated with the Bolting Integrity Program (first line item on page 10 of NUREG-1801, Volume 1) captures both BWR and pressurized water reactor (PWR) aging mechanisms to be managed by this program, but not all of the aging effects listed are applicable to BWRs. Specifically, the aging effect of crack initiation and growth is applicable to PWRs because the materials listed for the applicable PWR item numbers (i.e., IV.C2.3-e, IV.C2.4-e, and IV.C2.5-n) apply to high strength steel bolting materials specific to PWRs. These NUREG-1 801 item numbers do not apply to BWRs.

The aging management program for the subject closure bolting, for the aging effects of loss of material and loss of preload, is changed from the currently identified aging management program to the Bolting Integrity Program. The Bolting Integrity Program is consistent with NUREG-1801, Volume 2, Section XL.M18, with respect to closure bolting, with exceptions and enhancements (see the response to RAI T3.1-1 above).

LRA Revisions The Bolting Integrity Program is added under the "Aging Management Programs" heading for the systems addressed in the following sections of LRA Section 3.1, "Aging Management of Reactor Vessel, Internals, and Reactor Coolant Systems:"

  • 3.1.2.A.4 Reactor Recirculation System (page 3.1-9)
  • 3.1.2.B.4 Reactor Recirculation System (page 3.1-16)

Corresponding changes are incorporated for LRA Tables 3.1. LA (page 3.1-26), 3.1.1.B (page 3.1-36), 3.1.2.A-3 (page 3.1-54), 3.1.2.A-4 (page 3.1-57), 3.1.2.B-3 (page 3.1-88), and 3.1.2.B-4 (page 3.1-94), as shown in Attachment 2.

RAI T3.1-3 In Tables 3.2.1.A&B of the LRA supplemental letter dated December 6, 2004, the applicant stated that loss of material (due to general corrosion, crack initiation and growth, and cyclic loading and/or stress corrosion cracking (SCG)) is not applicablefor closure bolting items 3.2.1.A&B-18. Tle applicantfiurther stated that the above loss of material aging effect is not applicable to closure bolting in high-pressure or high temperature systems because NUREG-Page 3 of 8

1801, Volumne 2, stated that the causal mechanisms for loss of material include leakingfluid; whereas, the NMP environmentfor bolting does not assume leakage. The staff disagrees with NMP i assessment because operating experiencefrom the industry indicated that leakage occurs. Please provide aging management for potential loss ofmaterial due to general corrosion, crack initiation and growth, and cyclic loading and/or stress corrosion cracking (SCC) for these closure bolting items.

This RAI also applies to closure bolting items identified in Sections 3.3, 3.4, and 3.5 of the LRA.

Please provide the applicable aging management accordingly.

Response

NMPNS has reevaluated its position regarding the treatment of closure bolting at NMPI and NMP2 and is revising the applicable environments, aging effects requiring management (AERM) and associated aging management programs (AMP). The revisions make the NMPNS position consistent with the guidance provided in NUREG-1801. Specifically, the environment for high-pressure or high-temperature systems will include leaking fluid. The AERMs will include loss of material due to general corrosion, and crack initiation and growth due to cyclic loading and/or stress corrosion cracking, and the credited AMP will be the Bolting Integrity Program.

The revisions to the original LRA, dated May 26, 2004, for each of the applicable sections are described below. Associated revisions to the tables in LRA Sections 3.2, 3.3, 3.4, and 3.5 are shown in Attachment 2.

LRA Section 3.2.2 and Associated Tables For LRA Table 3.2.1LA (page 3.2-27), Item 3.2.1.A-18, and Table 3.2.1.B (page 3.2-35), Item 3.2.1.B-1 8, the Discussion column is revised to state that the AMP will be consistent with NUREG-1801, with exceptions. These line items correspond to NUREG-1801, Volume 2, Item Numbers V.E.2-a and V.E.2-b, for the AERMs of loss of material and crack initiation and growth of closure bolting in high-pressure or high-temperature systems.

For high-pressure or high-temperature systems (or portions of systems thereof), the bolting environment described as "Closure Bolting for Non-Borated Water Systems with Operating Temperatures >212'F," is changed to "Closure Bolting for Non-Borated Water Systems with Operating Temperatures Z2 120F, EeakiigFluid." This change is incorporated under the "Environments" heading in the following sections of LRA Section 3.2, "Aging Management of Engineered Safety Features:"

  • 3.2.2.A.3 Emergency Cooling System (page 3.2-7)
  • 3.2.2.B.3 Low Pressure Core Spray System (page 3.2-11)

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New items corresponding to NUREG-1801, Volume 2, Item V.E.2-b, "Crack initiation and growth/Cyclic loading, stress corrosion cracking," for carbon or low alloy steel closure bolting in high-pressure or high-temperature systems are added for each closure bolting item in Section 3.2 "Table 2s," with the environment as described above. For closure bolting in low-pressure and low-temperature systems (or portions of systems thereof), the environment will remain "Air" or "Air With Moisture or Wetting, Temperature <140'F."

The Bolting Integrity Program is assigned as the aging management program for the aging effect of crack initiation and growth due to cyclic loading or stress corrosion cracking. Additionally, the Bolting Integrity Program replaces the Systems Walkdown Program as the assigned aging management program for loss of material for bolts with an environment description of "Air" or "Air With Moisture or Wetting, Temperature <140'F," in LRA Tables 3.2.2.A and 3.2.2.B. The Bolting Integrity Program is consistent with NUREG-1 801, Volume 2, Section XL.M18, with exceptions (not related to pressure retaining bolting) and enhancements (see the response to RAI T3.1-1 above). Thus, the Bolting Integrity Program is added under the "Aging Management Programs" heading for the systems addressed in the following sections of LRA Section 3.2:

  • 3.2.2.A.3 Emergency Cooling System (page 3.2-8)
  • 3.2.2.B.1 Hydrogen Recombiner System (page 3.2-9)
  • 3.2.2.B.3 Low Pressure Core Spray System (page 3.2-12)

LRA Section 3.3 and Associated Tables Bolting components in Section 3.3 are in auxiliary systems. The majority of these bolting components are in "Air", or "Air, Moisture or Wetting, Temperature <1400F." These are low-pressure and low-temperature environments. The NUREG-1 801, Volume 2, items for auxiliary systems closure bolting are VII.I.2-a and VII.I.2-b, which have the component description "Closure Bolting in High Pressure or High Temperature Systems" and have an environment described as "Air, Moisture, Humidity, and Leaking Fluid." The auxiliary systems at NMP 1 and NMP2 are typically low-pressure, low temperature systems and do not exactly fit the description ofNUREG-1801, Volume 2, Items VII.I.2-a and VII.I.2-b. However, portions ofthe Reactor Water Cleanup Systems, the Liquid Poison System (NMP I) and the Standby Liquid Control System (NMP2) have a high-pressure or high-temperature environment; therefore, a new bolting component is added for closure bolting in the high temperature portions of these systems. These bolting components have the aging effect of crack initiation and growth (due to cyclic loading or stress corrosion cracking). The assigned aging management program for all bolting components in LRA Section 3.3 is changed to the Bolting Integrity Program. Thus, the Bolting Integrity Program is added under the "Aging Management Programs" heading for the systems addressed in the following sections of LRA Section 3.3:

Page 5 of 8

3.3.2.A.3 Compressed Air Systems (page 3.3-14)

  • 3.3.2.A.4 Containment Systems (page 3.3-15)
  • 3.3.2.A.5 Control Room HVAC System (page 3.3-17)
  • 3.3.2.A.8 Fire Detection and Protection System (page 3.3-21)
  • 3.3.2.A.10 Liquid Poison System (page 3.3-23) 33.2.A.14 Radioactive Waste System (page 3.3-27)
  • 3.3.2.A.16 Reactor Building HVAC System (page 3.3-30)
  • 3.3.2.A.23 Turbine Building HVAC System (page 3.3-39) 3.3.2.B.1 Air Startup Standby Diesel Generator System (page 3.3-41)
  • 3.3.2.B.5 Compressed Air Systems (page 3.3-46)
  • 3.3.2.B.6 Containment Atmosphere Monitoring System (page 3.3-47)
  • 3.3.2.B.13 Fire Detection and Protection System (page 3.3-54)
  • 3.3.2.B.14 Floor and Equipment Drains System (page 3.3-56)
  • 3.3.2.B.23 Reactor Building HVAC System (page 3.3-64)
  • 3.3.2.B.26 Service Water System (page 3.3-68) 3.3.2.B.28 Standby Diesel Generator Fuel Oil System (page 3.3-70)
  • 3.3.2.B.29 Standby Diesel Generator Protection (Generator) System (page 3.3-71)

LRA Sections 3.3.2.A.l0 (pages 3.3-22 and 23) and 3.3.2.B.30 (page 3.3-73) are revised as follows:

(1) Under the "Materials" header, "Carbon or Low Alloy Steel (Yield Strength 2100 ksi)" is added.

(2) Under the "Environments" header, "Air" and "Closure Bolting for Non-Borated Water Systems with Operating Temperatures 2212'F, Leaking Fluid" are added.

(3) Under the "Aging Effects Requiring Management" header, "Cumulative Fatigue Damage" is added.

LRA Sections 3.3.2.A.17 and 3.3.2.B.24 are revised as follows:

(1) Under the "Environments" header, "Closure Bolting for Non-Borated Water Systems with Operating Temperatures

.2212°F, Leaking Fluid" is added.

(2) Under the "Aging Effects Requiring Management" header, "Cumulative Fatigue Damage" is added.

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LRA Section 3.4 and Associated Tables Bolting components in LRA Section 3.4 are in steam and power conversion systems. The corresponding NUREG-1801, Volume 2, items are VIII.H.2-a and VIII.H.2-b, for the aging effects of loss of material and crack initiation and growth (due to cyclic loading or stress corrosion cracking), with the component description "Closure Bolting in High Pressure or High Temperature Systems," and the environment description "Air, Moisture, Humidity, and Leaking Fluid." NMP1 and NMP2 bolting components in steam and power conversion systems were assigned to the environments "Closure Bolting for Non-Borated Water Systems with Operating Temperatures 2212 0F," with the exception of bolting for the Main Generator and Auxiliaries System in which the bolting was assigned to an environment of "Air." LRA Section 3.4 is revised to change the environment description of bolting components from "Closure Bolting for Non-Borated Water Systems with Operating Temperatures 2212 F," to "Closure Bolting for Non-Borated Water Systems with Operating Temperatures 2212 F, Leaking Fluid." This change is incorporated under the "Environments" heading in the following sections of LRA Section 3.4:

  • 3.4.2.A.2 Feedwater/High Pressure Coolant Injection System (page 3.4-6)

The additional aging effect of crack initiation and growth (due to cyclic loading or stress corrosion cracking) corresponding to NUREG-1801, Volume 2, Item VIII.H.2-b, is identified, and the loss of material aging effect is aligned to NUREG-1801, Volume 2, Item VIII.H.2-a.

The Bolting Integrity Program is the aging management program for both aging mechanisms.

The bolting in the Main Generator and Auxiliaries System in which the environment is "Air,"

does not have the aging effect of crack initiation and growth assigned; however, the currently assigned aging management program is replaced with the Bolting Integrity Program. Thus, the Bolting Integrity Program is added under the "Aging Management Programs" heading for the systems addressed in the following sections of LRA Section 3.4:

  • 3.4.2.A.2 Feedwater/High Pressure Coolant Injection System (page 3.4-7)
  • 3.4.2.A.3 Main Generator and Auxiliary System (page 3.4-8)

LRA Section 3.5 and Associated Tables LRA Section 3.5 pertains to structures and component supports. NUREG-1801, Volume 2, Item III.B.1.1.2-a, for "High strength bolting for NSSS component supports," is the only structural or component support bolting item in NUREG-1 801 with an aging effect of cracking caused solely by the mechanism of stress corrosion cracking (SCC). The environment for this component is described as "inside containment" and the material is low alloy steel, yield strength >150 ksi.

NUREG-1 801 recommends the Bolting Integrity Program be assigned as the aging management Page 7 of 8

program for this item. The corresponding item in NUREG -1801, Volume 1, Table 5, "Summary of Aging Management Programs for the Structures and Component Supports Evaluated in Chapters II and III of the GALL Report," is crack initiation and growth due to SCC of Group B1.1, high strength low-alloy bolts in component supports. For those situations, a separate line item in LRA Tables 3.5.2.A and 3.5.2.B is added for high-strength bolting (yield strength 2150 ksi) in component supports, and the Bolting Integrity Program is added under the "Aging Management Programs" heading for LRA Section 3.5.2.C.1, "Component Supports" (page 3.5-38).

Note that the NMPNS Bolting Integrity Program will not include structural bolting (other than high-strength nuclear steam supply system (NSSS) component support bolting) within the program scope. Aging of these bolts will be managed under the ASME Section XI Inservice Inspection (Subsection IWF) and Structures Monitoring Programs described in LRA Sections B2.1.25 and B2.1.28, respectively.

Other Associated LRA Revisions In LRA Table 2.3.3.A.1 1-1 (page 2.3-84) for the NMPl Liquid Poison System, and in Table 2.3.3.B.31-1 (page 2.3-183) for the NMP2 Standby Liquid Control System, the Component Type "Bolting," with an Intended Function of "Pressure Boundary" is added.

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ATTACHMENT 2 Nine Mile Point Nuclear Station Revisions to LRA Section 3 Tables Regarding Aging Management of Bolting LRA Table Number LRA Page Number 3.1.1.A 3.1-26 3.1.1.B 3.1-36 3.1.2.A-3 3.1-54 3.1.2.A-4 3.1-57 3.1.2.B-3 3.1-88 3.1.2.B-4 3.1-94 3.2.1.A 3.2-27 3.2.1.13 3.2-35 3.2.2.A-1 3.2-36 3.2.2.A-2 3.2-44 3.2.2.A-3 3.2-52 3.2.2.B-1 3.2-67 3.2.2.B-2 3.2-70, 71 3.2.2.B-3 3.2-77 3.2.2.B-4 3.2-85, 86 3.2.2.B-5 3.2-98, 99 3.2.2.13-6 3.2-107 3.3.1.A 3.3-85 3.3.1.B 3.3-99 3.3.2.A-3 3.3-104 3.3.2.A-4 3.3-113 3.3.2.A-5 3.3-118 3.3.2.A-7 3.3-124 3.3.2.A-8 3.3-134 3.3.2.A-10 3.3-141 3.3.2.A-14 3.3-147 3.3.2.A-16 3.3-159 3.3.2.A-17 3.3-162 3.3.2.A-19 3.3-173 3.3.2.A-23 3.3-188 3.3.2.B-1 3.3-191 3.3.2.B-2 3.3-194 3.3.2.B-5 3.3-197 Page 1 of 30

LRA Table Number LRA Page Number 3.3.2.B-6 3.3-200 3.3.2.B-13 3.3-215 3.3.2.B-14 3.3-223 3.3.2.B-23 3.3-241 3.3.2.B-24 3.3-245 3.3.2.B-26 3.3-257 3.3.2.B-28 3.3-265 3.3.2.B-29 3.3-269 3.3.2.B-30 3.3-273 3.4.1.A 3.4-20 3.4.1.B 3.4-23 3.4.2.A-2 3.4-33 3.4.2.A-3 3.4-42 3.4.2.A-4 3.4-43 3.4.2.B-3 3.4-50 3.4.2.B-4 3.4-54 3.5.1.A 3.5-52 3.5.1.B 3.5-65 3.5.2.C-1 3.5-141 Page 2 of 30

'1)

Table 3.1.1.A NMP1 Summary of Aging Management Programs for the Reactor Vessel, Internals, and Reactor Coolant Systems Evaluated in Chapter IV of NUREG-1 801 Item Aging Effect/

Aging Further Iter Component Mechanism Management Evaluation Discussion N

Programs Recommended 3.1.1.A-26 Reactor coolant Loss of material due to Bolting integrity No Consistent with NUREG-1 801, with the pressure wear; loss of preload due following exceptions:

boundary (RCPB) to stress relaxation; crack valve closure initiation and growth due Not applicable for pressurizer bolting bolting, manway to cyclic loading and/or because this component does not exist and holding SCC at NMP1.

bolting, and closure bolting in high-pressure and high-temperature systems Table 3.1.1.B NMP1 Summary of Aging Management Programs for the Reactor Vessel, Internals, and Reactor Coolant Systems Evaluated In Chapter IV of NUREG-1 801 Item Aging Effect/

Aging Further Number Component Mechanism Management Evaluation Discussion Programs Recommended 3.1.1.B-26 Reactor coolant Loss of material due to Bolting integrity No Consistent with NUREG-1 801, with the pressure wear; loss of preload due following exceptions:

boundary (RCPB) to stress relaxation; crack valve closure initiation and growth due Not applicable for pressurizer bolting bolting, manway to cyclic loading and/or because this component does not exist and holding SCC at NMP2.

bolting, and closure bolting in high-pressure and high-temperature systems Page 3 of 30

Table 3.1.2.A-3 Reactor Vessel, Internals, and Reactor Coolant System NMP1 Reactor Vessel Instrumentation System - Summary of Aging Management Evaluation n

ENUREG-Component Intended Aigi Environmentng Management 1801 Table I Notes TpFucinManagement Program Volume 2 Item

_ _ _ _ _Ite m_

Closure Bolting PB Carbon or Low Closure Bolting Cumulative Fatique Monitoring IV.C1.3-g 3.1.1.A-01 A

Alloy Steel for Non-Borated Fatigue Program (Yield Strength Water Systems Damage 2100 Ksi) with operating Loss of Bolting Integrity IV.C1.3-e 3.1.1.A-26 E

temperatures Material Program

Ž2120F Loss of Bolting Integritv IV.C1.3-f 3.1.1.A-26 E

Preload Program Table 3.1.2.A-4 Reactor Vessel, Internals, and Reactor Coolant System NMPI Reactor Recirculation System - Summary of Aging Management Evaluation NUREG-Component Intended Aging Effect AgngMnREG-101 Tbl Type Function Material Environment Requiring A

Program Volum e 2 Table m Notes Management Prgrmtolme2 Im Closure Bolting PB Carbon or Low Closure Bolting Cumulative Fatique Monitoring IV.C1.2-f 3.1.1.A-01 A

Alloy Steel for Non-Fatigue Program IV.C1 3-g 3.1.1 A-01 A

(Yield Strength >

Borated Water Damage

_.C.3.1._.

100 Ksi)

Systems with Loss of Bolting Integrity IV.C1.2-d 3.1.1.A-26 E

operating Material Program IV.C.3-e 3.1.1.A-26 E

temperatures

Ž2120 F Loss of Preload Bolting Integrity IV.C1.2-e 3.1.1.A-26 E

Programrr IV.C1.3-f 3.1.1.A-26 E

Page 4 of 30

Table 3.1.2.B-3 Reactor Vessel, Internals, and Reactor Coolant System NMP2 Reactor Pressure Vessel Instrumentation System - Summary of Aging Management Evaluation Aging Effect NUREG-Component Intended Material Environment Requiring Aging Management 1801 Table I Notes TpFucinManagement Program Volume 2 Item

___Item Closure Bolting PB Carbon or Low Closure Bolting Cumulative Fatigue Monitoring IV.C1.3-g 3.1.1.B-01 A

Alloy Steel (Yield for Non-Borated Fatigue Program Strength >100 Water Systems Damage Ksi) with operating temperatures 2 Loss of Bolting Integrity IV.C1.3-e 3.1.1.B-26 E

212°F Material Prograrri Loss of Bolting Integrity IV.C1.3-f 3.1.1.B-26 E

Preload Program Martensitic, Closure Bolting Cumulative Fatigue Monitorinq IV.C1.3-g 3.1.1.B-01 A

Precipitation for Non-Borated Fatigue Program Hardenable, and Water Systems Damage Superferritic with operating Stainless Steels temperatures 2 Cracking Bolting Integritv Ho 43 212°F Program Loss of Bolting Integrity IV.C1.3-e 3.1.1.B-26 E

Material Proaramry Loss of Bolting IntegritY IV.C1.3-f 3.1.13.B-26 H

Preload Program Page 5 of 30

Table 3.1.2.B-4 Reactor Vessel, Internals, and Reactor Coolant System NMP2 Reactor Recirculation System - Summary of Aging Management Evaluation Aging ffectNUREG-Component Intended Agn fet Aging Management 1801 Table I oe Type Function Material Environment Requiring Program Volume 2 ITem N

Management Prgrmtolme2 im Closure Bolting PB Carbon or Low Closure Bolting Cumulative Fatigue Monitoring IV.C1.2-f 3.1.1.B-01 A

Alloy Steel for Non-Fatigue Program IV.C1.3-g 3.1.1.B-01 A

(Yield Strength Borated Water Damage 2100 Ksi)

Systems with operating temperatures Loss of Material Bolting Integrity IV.C1.2-d 3.1.13.B-26 E

2212°F Program_

IV.C1.3-e 3.1.1.B-26 E

Loss of Preload Bolting IntegritV IV.C1.2-e 3.1.1.A-26 E

Program IV.C1.3-f 3.1.1.A-26 E

Wrought Closure Bolting Cumulative Fatique Monitorinq F

Austenitic for Non-Fatigue Program Stainless Steel Borated Water Damage Systems with operating temperatures 2212°F Loss of Preload Boltinq Integrity IV.C1.2-e 3.1.1.A-26 H

Program Page 6 of 30

- j Table 3.2.1.A NMP1 Summary of Aging Management Programs for the Engineered Safety Features Systems Evaluated in Chapter V of NUREG-1 8011 Item Aging Effect/

Aging Further Number Component Mehni Management Evaluation Discussion NubrMcaimPrograms Recommended 3.2.1.A-18 Closure bolting in Loss of material due to Bolting integrity No Consistent with NUREG-1 801, Volume 2 high-pressure or general corrosion; with the exceptions noted in Appendix high-temperature crack initiation and B2.1.361 systems growth due to cyclic loading and/or SCC Table 3.2.1.B NMP1 Summary of Aging Management Programs for the Engineered Safety Features Systems Evaluated in Chapter V of NUREG-1 8011 ItmAigEfc/Aging Further Number Component Mechanism Management Evaluation Discussion Number Mechanism Programs Recommended 3.2.1.B-18 Closure bolting in Loss of material due to Bolting integrity No Consistent with NUREG-1 801, Volume 2 high-pressure or general corrosion; with the exceptions noted in Appendix high-temperature crack initiation and 82.1.36i systems growth due to cyclic loading and/or SCC Page 7 of 30

-I Table 3.2.2.A-1 Engineered Safety Features Systems NMPI Containment Spray System - Summary of Aging Management Evaluation Agin EffeNUREG.

Component ntn Material Environment R

Effuecit Aging Management 1801 Table 1 Notes TpFucinManagement Program Volume 2 Item Item Bolting PB Carbon or Low Air Loss of Material Bolting Integrity V.E.1-b 3.2.1.A-10 E, 22 Alloy Steel Program (Yield Strength

.100 Ksi)

Wrought Air None None None Austenitic Stainless Steel Table 3.2.2.A-2 Engineered Safety Features Systems NMPI Core Spray System - Summary of Aging Management Evaluation Aging ffectNUREG-Component Intended Agn fet Aging Management 1801 Table I Noe Type Function Material Environment Requiring Program Volume 2 Item Notes Management Prgrmtolme2 Im Bolting PB Carbon or Low Air Loss of Material Bolting Integrity V.E.1-b 3.2.1.A-10 E, 22 Alloy Steel Program (Yield Strength 2100 Ksi)

Wrought Air None None None Austenitic Stainless Steel Page 8 of 30

'3 Table 3.2.2.A-3 Engineered Safety Features Systems NMPI Emergency Cooling System - Summary of Aging Management Evaluation Copnn neddAging Effect NUREG-Component Function Material Environment Requiring Aging Management 1801 Table I Notes TpFucinManagement Program Volume 2 Item Ite m Bolting PB Carbon or Low Closure Cumulative Fatigue Monitoring G

Alloy Steel Bolting for Fatigue Daiige Program (Yield Strength Non-Borated Cracking Bolting Integrity V.E.2-b 3.2.1.A-18 B

2100 Ksi)

Water Programri Systems with Loss of Material Bolting Integrity V.E.2-a 3.2.1.A-18 B

operating Program temperatures 2212 0F, Leaking Pid_

Table 3.2.2.6-1 Engineered Safety Features Systems NMP2 Hydrogen Rec ombiner System - Summary of Ag ing Management Evaluation Aging ffectNUREG-Component Intended Material Environmen querinct Aging Management 1801 Table 1 Notes TpFucinManagement Program Volume 2 Item Bolting PB Carbon or Low Air with Loss of Material Bolting Integrity V.E.1-b 3.2.1.B-10 E. 22 Alloy Steel Moisture or Program (Yield Strength

Wetting,

>100 Ksi) temperature

<140 0F Martensitic, Air with Loss of Material Bolting Integrity K

Precipitation Moisture or Program Hardenable, and

Wetting, Superferritic temperature Stainless Steels

<140 0F Page 9 of 30

1P Table 3.2.2.B-2 Engineered Safety Features Systems NMP2 High Pressure Core Spray System - Summary of Aging Management Evaluation Copnn neddAging Effect NUREG-Noe Component Function Material Environment Requiring Aging Management 1801 Table TpFucinManagement Program Volume 2 Item

____Item Bolting PB Carbon or Low Air with Loss of Material Bolting Integrity V.E.1-b 3.2.1.B-10 E 22 Alloy Steel (Yield Moisture or Program Strength 2100

Wetting, Ksi) temperature

<1400F Closure Cumulative Fatigue Monitoring G

Bolting for Fatigue Damage Program Non-Borated Cracking Bolting Integrity V.E.2-b 3.2.1.B-18 B

Water Programrr Systems with Loss of Material Bolting Integrity V.E.2-a 3.2.1.B-18 B

operating Program temperatures

Ž212 0F, Re1ig Fluiid Martensitic, Air with Loss of Material Bolting IntearitV K

Precipitation Moisture or Program Hardenable, and

Wetting, Superferritic temperature Stainless Steels

<140 0F Martensitic, Closure Cumulative Fatigue Monitorinq G

Precipitation Bolting for Fatigue Damaige Program Hardenable, and Non-Borated Cracking Bolting Integrity K

Superferritic Water Program Stainless Steels Systems with Loss of Material Bolting operating Program temperatures

Ž2120F,

_Leaking FaiiTi Page 10 of 30

-j Table 3.2.2.B-3 Engineered Safety Features Systems NMP2 Low Pressure Core Spray Syste

- Summary of Aging Management Evaluation Aging Effect NUREG-Component intended Material Environmen Requiring Aging Management 1801 Table I TpFucinManagement Program Volume 2 Item Noe

____Item Bolting PB Carbon or Low Closure Cumulative Fatigue Monitoring G

Alloy Steel Bolting for fatigue Damage Program (Yield Strength Non-Borated Cracking Bolting Integrity V.E.2-b 3.2.13.B-18 B

2100 Ksi)

Water Progran_

Systems with Loss of Material Bolting Integrity V.E.2-a 3.2.1.B-18 B

operating Pro-ram temperatures 2212°F, eaking IFui Martensitic, Closure Cumulative Fatigue Monitorinq G

Precipitation Bolting for Fatigue D Program_

Hardenable, and Non-Borated Cracking Bolting Integrity K

Superferritic Water Prograni Stainless Steels Systems with Loss of Material Bolting Integrity K

operating Program temperatures 2212 0F, Leaking Fluid Page 11 of 30

.1 Table 3.2.2.B-4 Engineered Safety Features Systems NMP2 Reactor Core Isolation Cooling System - Summary of Aging Management Evaluation AgnEfc NUREG-Component Intended Agn fet Aging Management NUREG Table I Type Function Material Environment Requiring Program Volume 2 Item Notes Management Progra Bolting PB Carbon or Low Air with Loss of Material Bolting IntegritV V.E.1-b 3.2.1.B-10 E+/- 22 Alloy Steel Moisture or Program (Yield Strength

Wetting,

>1 00 Ksi) temperature 21400F Closure Cumulative Fatigue Monitoring G

Bolting for Fatigue Damage Program Non-Borated Cracking Bolting Integrity V.E.2-b 3.2.1.B-18 B

Water Prograrm_

Systems with' Loss of Material Bolting Integrity V.E.2-a 3.2.1.B-18 B

operating Program temperatures

>2120F, i eaking F d_

Martensitic, Air with Cracking Bolting Integrity K

Precipitation Moisture or Program Hardenable, and

Wetting, Loss of Material Bolting Integrity K

Superferritic temperature Program Stainless Steels

Ž1400F Martensitic, Closure Cumulative Fatigue Monitoring G

Precipitation Bolting for Fatigue Damage6 Program_

Hardenable, and Non-Borated Cracking Bolting Integrity K

Superferritic Water Program Stainless Steels Systems with Loss of Material Bolting Integritv K

operating Proqram temperatures

>2120F, Leaking Fluid Page 12 of 30

V,

Table 3.2.2.B-5 Engineered Safety Features Systems NMP2 Residual Heat Removal System - Summary of Aging Management Evaluation Copnn neddAging Effect Aging NUREG-Momoet ntended Material Environment Requiring Management 1801 Table I Notes Type Function Management Program Vlm Item Bolting PB Carbon or Low Air with Loss of Material Bolting Integrity V.E.1-b 3.2.1.B-10 E 22 Alloy Steel Moisture or Program (Yield Strength

Wetting, 2100 Ksi) temperature

,2140°F Closure Bolting Cumulative Fatigue Monitoring G

for Non-Fatigue Damage Program Borated Water Cracking Bolting Integrity V.E.2-b 3.2.1.B-18 B

Systems with Prograrm operating Loss of Material Bolting Integrity V.E.2-a 3.2.13.B-18 B

temperatures Program

22121F, Lkirig Fl1d Martensitic, Air with Cracking Bolting Integrity K

Precipitation Moisture or Program_

Hardenable, and

Wetting, Loss of Material Bolting Integrity K

Superferritic temperature Program Stainless Steels 214O0 F Closure Bolting Cumulative Fatigue Monitoring G

for Non-Fatigue Damiag Program Borated Water Cracking Bolting Integrity K

Systems with Program operating Loss of Material Bolting IntegritV K

temperatures Program

22120F, Leaking Fluid Page 13 of 30

Table 3.2.2.B-6 Engineered Safety Features Systems NMP2 Standby Gas Treatment System - Summary of A ing Management Evaluation NUREG-Component Intended Ageil Eniomnt Rqiinggffc Aging Management 1801 Table I Notes Type Functio n Material Environment Requ iring~rga

____meZ l1Noe TpFucinManagement Program Volume 2 Item

~~Item__

Bolting PB Carbon or Low Air with Loss of Bolting Integrity V.E.1-b 3.2.1.B-10 E 22 Alloy Steel (Yield Moisture or Material Program Strength 2100

Wetting, Ksi) temperature

<1400F Martensitic, Air with Loss of Bolting Integrity K

Precipitation Moisture or Material Program Hardenable, and

Wetting, Superferritic temperature Stainless Steels

<140 0F Page 14 of 30

Table 3.3.1.A NMP1 Summary of Aging Management Programs for the Auxiliary Systems Evaluated in Chapter VII of NUREG-1 801 ItmAgn ffc/Aging Further Number Component Mechanism Management Evaluation Discussion Programs Recommended 3.3.1.A-24 Closure bolting Loss of material due to Bolting integrity No Consistent with NUREG-1801, Volume 2 general corrosion; with' the exceptions noted in Appendix crack initiation and B2.1.36' growth due to cyclic loading and SCC Table 3.3.1.B NMP1 Summary of Aging Management Programs for the Auxiliary Systems Evaluated In Chapter VII of NUREG-1 801 Item Aging Effect/

Aging Further Nubr Component McaimManagement Evaluation Discussion Programs Recommended 3.3.1.B-24 Closure bolting Loss of material due to Bolting integrity No Consistent with NUREG-1801, Volume 2 general corrosion; with the exceptions noted in-Appendix crack initiation and B2.1.361 growth due to cyclic loading and SCC Page 15 of 30

Table 3.3.2.A-3 Auxiliary Systems NMP1 Com ressed - Summary ot Aging Mana ement Evaluation Aging Effect NUREG-Component Intended Material Environment Requiring Aging Management 1801 Table I Notes TpFucinManagement Program Volume 2 Item Bolting PB Carbon or Low Air Loss of Material Bolting Integrity VII.D.1-a 3.3.1.A-19 E 14 Alloy Steel Program (Yield Strength

<100 Ksi)

Carbon or Low Air Loss of Material Bolting Integrity VII.D.1-a 3.3.1.A-19 E

Alloy Steel Program (Yield Strength

_ __1O00 Ksi)

Table 3.3.2.A-4 Auxiliary Systems NMP1 Containment Systems - Summary of Aging Management Evaluation Aging ffectNUREG-Component Intended AMaterEal lEnvironment Riregct Aging Management l 1801 Table I lo; Type Function Maeral Evionengequirng Program Volume 2 Item Noe ManagmentItem Bolting PB Carbon or Low Air Loss of Material Boltinq Integrity VII.l.1-b 3.3.1.A-05 D, 5 Alloy Steel Program (Yield Strength

<100 Ksi)

Table 3.3.2.A-5 Auxiliary Systems NMP1 Control Room HVAC System - Summary of Aging Management Evaluation Aging ffectNUREG-Component Intended Material Environmeft Requiring Aging Management 1801 Table 1 Notes Type Function Matrilnnvrometmequrng Program Volume 2 Item ManagmentItem Bolting PB Carbon or Low Air Loss of Material Bolting Integrity VII.F1.1-a 3.3.1.A-05 E

Alloy Steel Program (Yield Strength

___100 Ksi)

Page 16 of 30

Table 3.3.2.A-7 Auxiliary Systems Fmmrapnrv Diesel Gnranrtnr !Svqtem - 5uivmmnrv nf Aninn Mannaament Fuanhntinn NMPI Component Intended A

Environment Requiring Aging Management 1801 Table I Notes TpFucinManagement Program Volume 2 Item Bolting PB Carbon or Low Air Loss of Material Bolting Integrity ViI.1.1-b 3.3.1.A-05 D, 5 Alloy Steel Program (Yield Strength

<100 Ksi)

Table 3.3.2.A-8 Auxiliary Systems NMP1 Fire Detection and Protection System - Summary of Aging Management Evaluation Component Agn fetNUREG-Type Intended Ageil niomet Rqing n

Eft Aging Management 1801 Table I oe Function Management Program Volume 2 Item Bolting NFS Carbon or Low Air Loss of Material Bolting Integrity VII.1.1-b 3.3.1.A-05 0 5 Alloy Steel Program (Yield Strength

<100 Ksi Table 3.3.2.A-10 Engineered Safety Features Systems NMP1 Liquid Poison System - Summary of Aging Management Evaluation Aging Effect Aging NUREG-Component Intended Mtra Eniomn ReuigMngmnt1801 Table I Notes Type Function Material tEnvironment Requirin Management Volume 2 Item Management Program

~Item Bolting PB Carbon or Low Air Loss of Material Bolting Integrity V1I.1.1-b 3.3.1.A-05 D, 5 Alloy Steel

_Program (Yield Strength Closure Bolting Cumulative Fatigue Monitoring G

2100.Ksi) for Non-Fatigue Damaige Programr_

Borated Water Cracking Bolting Integrity V1.1.2-b 3.2.1.A-24 B

Systems with PrograM operating' Loss of Material Bolting Integrity VY1.1.2-a 3.2.1;A-24 B

temperatures Prooram Leaking FEBid Page 17 of 30

Table 3.3.2.A-14 Auxiliary Systems NMP1 Radioactive Waste System - Summary of Agin Management Evaluation Copnn neddAging Effect NUIREG-L oTypen l Intended Material Environment Requiring Aging Management 1801 Table I Notes TpFucinManagement Program Volume 2 Item

_ _ _ _ _ _ _Ite m_

Bolting PB Carbon or Low Air Loss of Material Bolting Integrity V1.1.1-b 3.3.1.A-05 D, 5 Alloy Steel Program (Yield Strength 100 Ksi)

Table 3.3.2.A-16 Auxiliary Systems NMP1 Reactor Buildi g HVAC System - Summary of Ag ng Management Evaluation Aging Effect NUREG-Copnn nedd Material Environment Requiring Aging Management 1801 Table I Notes Type Function Management Program Volume 2 Item Ite m Bolting PB Carbon or Low Air Loss of Material Bolting IntegritV VII.F2.1-a 3.3.1.A-05 B

Alloy Steel Proqgram' (Yield Strength

<100 Ksi)

Table 3.3.2.A-17 Auxiliary Systems NMPI Reactor Water Cleanup System - Summary of Ag ng Management Evaluation Aging Effect NUREG-Component Intended Material Environment Rquiring Aging Management 1801 Table 1 Notes Type Function Maeral EnirnenaRqurigVolume 2

Item Noe Management Progra Bolting PB Carbon or Low Air Loss of Material Bolting Integrity Vil.1.1-b 3.3.1.A-05 D, 5 Alloy Steel Program (Yield Strength Closure Cumulative Fatigue Monitoring G

2100 Ksi)

Bolting'for Fatigue Damage Program Non-Boratd Cracking Boltinq Integritv VII.I.2-b 3.2.1.A-24 B

Water Prograrn_

System-swith Loss of Material Bolting Integrity VII.l.2-a 3.2.1.A-24 B

operating Program temperatures

>212 0F__

Leaking Fluid Page 18 of 30

Table 3.3.2.A-19 Auxiliary Systems NMP1 Service Water System - S mmary of Aging Management Evaluation Component Intended Aging Effect Aging NUREG-le Type inten Material Environment Requiring Management Volume 2 Table Notes TpFucinManagement Program Item Bolting PB Carbon or Low Air Loss of Material Bolting Integrity V11.1.1-b 3.3.1.A-05 D, 5 Alloy Steel Proaram (Yield Strength

_ 100 Ksi)

Table 3.3.2.A-23 Auxiliary Systems NMP1 Turbine Building HVAC System - Summary of Agi g Management Evaluation Component Intended Aging Effect Aging NUREG-le Type Function Material Environment Requiring Management Volu801e Tltem Notes TpFucinManagement ProgramVoue2 tm Bolting NFS, PB Carbon or Low Air Loss of Material Boltinq Integrity VI1.1.1-b 3.3.1.A-05 D, 5 Alloy Steel Program (Yield Strength

<100 Ksi Table 3.3.2.B-1 Auxiliary Systems NMP2 Air Startup Standby Diesel Generator System - Summar x of Aging Management Evaluation Aging Effect NUREG-Component Intended Material Environment Remeng Aging Management 1801 Table 1 Notes TpFucinManagement Program Volume 2 Item Bolting PB Carbon or Low Air Loss of Material Bolting Integrity V11.1.1-b 3.3.1.B-05 D, 5 Alloy Steel Program (Yield Strength

<100 Ksi Page 19 of 30

I Table 3.3.2.B-2 Auxiliary Systems NMP2 Alternate Decay Heat Removal System - Summary of Aging Management Evaluation Aging Effect Aging NUREG-Component Intended Material Environment Requiring Management Vo1801e 2 tem1 Notes Type Function 1801mn Pora olm Tablem Noe Management ProgramItem Bolting PB Carbon or Low Air Loss of Material Bolting IntegritV Vl1.1.1-b 3.3.1.B-05 D, 5 Alloy Steel Program (Yield Strength 2 100 Ksi)

Table 3.3.2.B-5 Auxiliary Systems NMP2 Compressed Air Systems - Summary of Aging Management Evaluation Aging Effect Aging NUREG-Component Intended Material Environment Requiring Management Vo1801e 2 I tNeom Type Function 1801mn Pora olm Tablem Noe Manaemen ProramItem Bolting PB Carbon or Low Air Loss of Material Bolting Integrity VII.D.2-a 3.3.1.B-19 E

Alloy Steel Program (Yield Strength

<100 Ksi)

Martensitic, Air None None None Precipitation Hardenable, and Superferritic Stainless Steels Table 3.3.2.B-6 Auxiliary Systems NMP2 Containment Atmosp ere Monitoring System - Summary of Aging Manageme t Evaluation Copnn neddAging Effect Aging NUREG-TalI Compnent Fintended Material Environment Requiring Management Vo1801 2 tble Notes TpFucinManagement Program Itluem2 Ie Bolting PB Martensitic, Air, Moisture or Cracking Bolting Integrity K

Precipitation

Wetting, Proqram Hardenable, and temperature Loss of Material Bolting Integrity K

Superferritic 2140°F Program Stainless Steels Page 20 of 30

I1 Table 3.3.2.B-13 Auxiliary Systems NMP2 Fire Detection and Protection System-Summary of Aging Management Evaluation Aging ffectNUREG-Component Intended rial Environme Requiring E

Aging Management 1801 Table I Notes TpFucinManagement Program Volume 2 Item

_ _ _Ite m

Bolting NFS Carbon or Low Air, Moisture Loss of Material Bolting Integrity V11.1.1-b 3.3.1.B-05 D, 5 Alloy Steel or Wetting, Program (Yield Strength temperature

<100 Ksi

<140 0F Carbon or Low Air Loss of Material Bolting Integrity V11.1.1-b 3.3.1.B-05 D, 5 Alloy Steel Program (Yield Strength Air, Moisture Loss of Material Bolting Integrity V11.1.1-b 3.3.1.B-05 D, 5 2100 Ksi) or Wetting, Program temperature

<1400F Table 3.3.2.B-14 Auxiliary Systems NMP2 Floor and Equipment Drains System - Summary of AgIn' Management Evaluation NUREG-Component Intended Material Environmen Aging Effect Aging Management 1801 Table I N

Type Function Maeil Evrnet Requiring Program Volume 2 Item Noe Management Item Bolting NFS Carbon or Low Air Loss of Material Bolting Integrity V11.1.1-b 3.3.1.B-05 D, 5 Alloy Steel Program (Yield Strength 21 00 Ksi)

Martensitic, Air None None None Precipitation Hardenable, and Superferritic Stainless Steels Page 21 of 30

'I Table 3.3.2.B-23 Auxiliary Systems NMP2 Reactor Building HVAC System - Summary of Aging Management Evaluation Aging Effect Aging NUREG-Component Intended Material Environment Requiring Management Volume 2 l bItem l

Type Function 1801e Itabem Nte Management Program Item Bolting PB Carbon or Low Air Loss of Material Boltinq IntegritV VII.F2.1-a 3.3.1.B-05 B

Alloy Steel Program (Yield Strength

<100 Ksi)

Carbon or Low Air Loss of Material Bolting Integrity VII.F2.1-a 3.3.13.B-05 B

Alloy Steel Program (Yield Strength 2100 Ksi)

Table 3.3.2.B-24 Auxiliary Systems NMP2 Reactor Water Cleanup System - Summary of Aging Management Evaluation Copnn neddAging Effect Aging NRG Type Inten Material Environment Requiring Management 1801 Table 1 Notes Type Function MaaeetPormVolume 2

Item Management Program Item Bolting PB Carbon or Low Air Loss of Material Bolting Integrity V11.1.1-b 3.3.13.B-05 D, 5 Alloy Steel Program (Yield Strength Closure Bolting Cumulative Fatigue Monitoring G

2100 Ksi) for Non-Fatigue Daiiide Program Borated Water Cracking Bolting Integrity Vl1.1.2-b 3.2.1.B-24 B

Systems with Program__

operating Loss of Material Bolting Integrity V11.1.2-a 3.2.13.B-24 B

temperatures Program

'Ž2120F,'

Leaking Fuidt Wrought Austenitic Air None None None Stainless Steel I

Page 22 of 30

Table 3.3.2.B-26 Auxiliary Systems NMP2 Service Water System - S mmary of Aging Management Evaluation Copnn neddAging Effect Aging NUREG-Type intended Material Environment Requiring Management 1801 Table I Notes Type Function MaaeetPormVolume 2

Item Management Program

~Item Bolting PB Carbon or Low Air Loss of Material Bolting Integrity V1.1.1-b 3.3.1.8-05 D, 5 Alloy Steel Proqrarm (Yield Strength 2_ 100 Ksi)

Table 3.3.2.B-28 Auxiliary Systems NMP2 Standby Diesel Generator Fuel Oil Srstem - Summary of Aging Management Evaluation Component Intended Material Environment Reguirng E

Managemen 1801 Table I Notes Type FunctionReurn ManagementPrga Volume 2 Item Managemen ProgramItem Bolting PB Carbon or Low Air Loss of Material Bolting Integrity V11.1.1-b 3.3.1.B-05 D, 5 Alloy Steel Program (Yield Strength

<100 Ksi)

Table 3.3.2.B-29 Auxiliary Systems NMP2 Standby Diesel Generator Protection (Gener ator) System - Summary of Aging Mana ement Evaluation Component IntendedAging Effect NRG oe l oType Function Material Environment Requiring Aging Management 1801 TableI Notesl TpFucinManagement Program Volume 2 Item

_ _ _Ite m

Bolting PB Carbon or Low Air Loss of Material Bolting Integrity Vl1.1.1-b 3.3.13.B-05 D, 5 Alloy Steel Program (Yield Strength

<100 Ksi)

Page 23 of 30

Table 3.2.2.B-30 Engineered Safety Features Systems NMP2 Standby Liquid Control System - Summary of Aging Management Evaluation Aging Effect Aging NUREG-Component Function Material Environment Requiring Management VlolumTe I

Notes Managemen ProgramItem Bolting PB Carbon or Low Air Loss of Material Boltinq Integrity V11.1.1-b 3.3.1.B-05 D 5 Alloy Steel Progra_

(Yield StreRi Closure Bolting Cumulative Fatigue Monitorinq G

2100 Ksi) for Non-,

Fatigue Damage Program BoCracking Bolting Integrity V11.1.2-b 3.2.1.B-24 B

Systems with Program operating___

Loss of Material Bolting IntegritY V11.1.2-a 3.2.1.B-24 B

temperatures Program 221 20Fng e a i g i ii

__Le a k in g_

Page 24 of 30

I, Table 3.4.1.A NMP1 Summary of Aging Management Programs for the Steam and Power Conversion Systems Evaluated in Chapter VIII of NUREG-1 801 ItmAigEfclAging Further Number Component Mechanism Management Evaluation Discussion Number MechanismPrograms Recommended 3.4.1.A-08 Closure bolting in Loss of material due to Bolting integrity No Consistent with NUREG-1 801, Volume 2 high-pressure or general corrosion; crack with the exceptions noted in Appendix high-temperature initiation and growth due B2.1.36!

systems to cyclic loading and/or SCC.

Table 3.4.1.B NMP1 Summary of Aging Management Programs for the Steam and Power Conversion Systems Evaluated in Chapter VIII of NUREG-1801 Item Aging Effect/

Aging Further Number Component Mechanism Management Evaluation Discussion N

Programs Recommended 3.4.1.B-08 Closure bolting in Loss of material due to Bolting integrity No Consistent with NUREG-1 801, Volume 2 high-pressure or general corrosion; crack With the exceptions noted in Appendix high-temperature initiation and growth due B2.1.36.

systems to cyclic loading and/or SCC.

Page 25 of 30

Table 3.4.2.A-2 Steam and Power Conversion System NMP1 Feedwater1High Pressur Coolant Injecti n System - Summary of Aging Management Evaluation Copnn neddAging Effect NUREG-l oTyoe intendldMaterial Environment Requiring Aging Management 1801 Table I Notes Type Function Management Program Volume 2 Item Ite m Bolting NFS Carbon Steel, Closure Cumulative Fatigue Monitoring G

Low Alloy Steel Bolting for Fatigue Dam-aie Program (Yield Strength Non-Borated Cracking Bolting Integrity VIII.H.2-b 3.4.1.A-08 B

< 100 Ksi)

Water Proqram Systems with Loss of Material Bolting IntegritV VIII.H.2-a 3.4.1.A-08 B

operating Program temperatures 2212°F,

_ Laki ng Fluid PB Carbon Steel, Closure Cumulative Fatigue Monitoring G

Low Alloy Steel Bolting for Fatigue Damage Program (Yield Strength Non-Borated Cracking Bolting Integrity VIIl.H.2-b 3.4.1.A-08 B

< 100 Ksi)

Water Prograni Systems with Loss of Material Bolting Integrity VIII.H.2-a 3.4.1.A-08 B

operating Program temperatures

>212 0F, Leaking Fkjid Table 3.4.2.A-3 Steam and Power Conversion System NMPI Main Generator a d Auxiliary Sys tem - Summary of Aging Management Evaluation Aging Effect NUREG-Component Intended Material AgEnvironment Requiring Management 1801 Table I 1 3 Type Function Matrilnnvrometmequrng Program Volume 2 Item Noe Management Item____

Bolting NFS Carbon Steel, Air Loss of Material Bolting Integrity VI1l.H-1-b 3.4.1.A-05 D, 11 Low Alloy Steel Program (Yield Strength

<100 Ksi)

Page 26 of 30

Table 3.4.2.A-4 Steam and Power Conversion System NMP1 Main Steam System - Summary of Aging Management Evaluation Aging ffectNUREG-Component Intended Material Environment Requiring Aging Management 1801 Table 1 Notes TpFucinManagement Program Volume 2 Item Bolting PB Carbon Steel, Closure Cumulative Fatigue Monitoring G

Low Alloy Steel Bolting for Fatigue Damage Proram (Yield Strength Non-Borated Cracking Bolting IntegritV V1II.H.2-b 3.4.1.A-08 B

2100 Ksi)

Water Program Systems with Loss of Material Bolting Integrity VIII.H.2-a 3.4;1 :A-08 B

operating Program temperatures

Ž2120F Table 3.4.2.B-3 Steam and Power Conversion System NMP2 Feedwater System - Summary of Aging Management Evaluation Aging ffectNUREG-Component Intended Material Environment igEegt Aging Management 1801 Table I Notes TpFucinManagement Program Volume 2 Item

_Ite m_

Bolting PB Carbon Steel, Closure Cumulative Fatigue Monitoring G

Low Alloy Steel Bolting for Fatigue'Damaie Proaram (Yield Strength Non-Borated Cracking Bolting Integrity VliI.H.2-b 3.4.1.A-08 B

<100 Ksi)

Water Program Systems with Loss of Material Bolting Integrity V1Il.H.2,-a 3.4.1.A-08 B

operating Program temperatures 221 20F,

_Leaking F Su id Page 27 of 30

Table 3.4.2.B-4 Steam and Power Conversion System NMP2 Main Ste am System - Su mary of Aging Management Evaluation Copnn neddAging Effect NUREG-l Typoe Functiond l

Material Environment Requiring Aging Management 1801 Table 1 Notes TpFucinManagement Program Volume 2 Item

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _Ite m

Bolting PB Carbon Steel, Closure Cumulative Fatigue Monitoring G

Low Alloy Steel Bolting for Fatigue Damage Program (Yield Strength Non-Borated Cracking Bolting Integrity VIII.H.2-b 3.4.1.A-08 B

<100 Ksi)

Water Program Systems with Loss of Material Bolting Integrity VlII.H.2-a 3.4.1.A-08 B

operating Program temperatures 221 20F, Leaking_ Fluid Page 28 of 30

'I Table 3.5.1.A NMP1 Summary of Aging Management Programs for Structures and Component Supports Evaluated in Chapter II and lil of NUREG-1801 Item 1 Aging Effect/

Aging Further Number Component Mechanism I

Management Evaluation Discussion Programs Recommended Component Supports 3.5.1.A-33 Group B1.1: high Crack initiation and Bolting integrity No Consistent with NUREG-1801, Volume 2 strength low-alloy growth due to SCC with the exceptions notedjin Appendix bolts 3B2.1.36.

Table 3.5.1.B NMP1 Summary of Aging Management Programs for Structures and Component Supports Evaluated In Chapter II and IlIl of NUREG-1801 Item T tAging Effect/

Aging Further 1

Number Component.

Mechanism Management Evaluation Discussion III Programs IRecommended I

Component Supports 3.5.13.B-33 Group B1.1: high Crack initiation and Bolting integrity No 1 Consistent with NUREG-1 801 Volume 2 strength low-alloy growth due to SCC with the exceptions noted in Appendix bolts I

_3__

2.1.36.

Page 29 of 30

P Table 3.5.2.C-1 Structures and Component Supports Component Supports - Sum ary of Aging Mana ement Evaluation IneddAging Effect Aging NUREG-Component IntendedIMaterial Environmentl Requiring Management 1801 Table I Notes Type Function MaaeetPormVolume 2

Item Manaemen ProramItem Fasteners (High SFS Carbon or Low Air Cracking Boltinq Integrity Il.B1.1.2-a 3.5.1.A-33 B

Strength Carbon Alloy Steel (Yield Program 3.5.1.B-33 and Low Alloy Strength 2100 Ks)

Steel) in Air SFS Carbon or Low Air Loss of Material ASME Section Xl lll.B13.1.1-a 3.5.1.A-32 B

SNSR Alloy Steel (Yield Inservice 11.B13.2.1-a 3.5.1.B-32 Strength 2100 Ksi)

Inspection I I.B13.3.1-a (Subsection IWF)

Program Structures III.B4.1-a 3.5.1.A-29 A

Monitoring Proqram Ill.B5.1-a 3.5.1.B-29 Page 30 of 30

ATTACHMENT 3 Nine Mile Point Nuclear Station New LRA Sections A1.1.38 and A2.1.37, Bolting Integrity Prosram

  • Revise Table of Contents page A-ii to add new Section A1.1.38, Bolting Integrity Program.
  • Revise Table of Contents page A-iv to add new Section A2. 1.37, Bolting Integrity Program.
  • Add new Sections Al.1.38 and A2.1.37, Bolting Integrity Program, as shown on the following pages.

Page 1 of 3

A1.1.38 Bolting Integrity Program The Bolting Integrity Program manages aging effects due to loss of preload, cracking and loss of material of bolting within the scope of license renewal including safety-related bolting, high-strength bolting for NSSS component supports, and bolting for other pressure retaining components. Program activities include material selection and testing, bolting preload control, inservice inspection, plant operation and maintenance, and evaluation of the structural integrity of bolted joints. This program implements the guidance contained in EPRI Reports NP-5769, as modified by NUREG-1339, and TR-104213 except as stated below.

The Bolting Integrity Program takes exceptions to NUREG-1 801,Section XI.M18 (Bolting Integrity) under the scope and monitoring attributes. Specifically, this program does not include structural bolting since this category of bolting is adequately managed by the ASME Section XI Inservice Inspection (Subsection IWF)

Program (Section Al.1.3) and Structures Monitoring Program (Section Al.1.34).

With respect to the monitoring attribute, the frequency of monitoring a leak from bolting for pressure retaining components (not covered by ASME Section XI) will be based upon the safety significance of the component and the radiological conditions in the vicinity of the component.

Enhancements to the Bolting Integrity Program include the following revisions to existing activities that are credited for license renewal:

  • Clearly restrict the use of lubricants containing molybdenum disulfide for bolting applications.
  • Clearly restrict the use of high-strength (Ž>150 ksi yield strength) bolting material to only those applications that require it.
  • Reference the evaluation method for assuring integrity of bolting material in component support applications from EPRI NP-5769 as an acceptable method in the design process.
  • Update implementing procedures to include EPRI Reports NP-5769 and TR-104213 and NUREG-1339 as reference documents, as appropriate.

Enhancements are scheduled for completion prior to the period of extended operation.

Page 2 of 3

I A2.1.37 Bolting Integrity Program The Bolting Integrity Program manages aging effects due to loss of preload, cracking and loss of material of bolting within the scope of license renewal including safety-related bolting, high-strength bolting for NSSS component supports, and bolting for other pressure retaining components. Program activities include material selection and testing, bolting preload control, inservice inspection, plant operation and maintenance, and evaluation of the structural integrity of bolted joints. This program implements the guidance contained in EPRI Reports NP-5769, as modified by NUREG-1339, and TR-104213 except as stated below.

The Bolting Integrity Program takes exceptions to NUREG-1801,Section XI.M18 (Bolting Integrity) under the scope and monitoring attributes. Specifically, this program does not include structural bolting since this category of bolting is adequately managed by the ASME Section XI Inservice Inspection (Subsection IWF)

Program (Section A2.1.3) and Structures Monitoring Program (Section A2.1.34).

With respect to the monitoring attribute, the frequency of monitoring a leak from bolting for pressure retaining components (not covered by ASME Section XI) will be based upon the safety significance of the component and the radiological conditions in the vicinity of the component.

Enhancements to the Bolting Integrity Program include the following revisions to existing activities that are credited for license renewal:

Clearly restrict the use of lubricants containing molybdenum disulfide for bolting applications.

  • Clearly restrict the use of high-strength ( 2150 ksi yield strength) bolting material to only those applications that require it.
  • Reference the evaluation method for assuring integrity of bolting material in component support applications from EPRI NP-5769 as an acceptable method in the design process.
  • Update implementing procedures to include EPRI Reports NP-5769 and TR-104213 and NUREG-1339 as reference documents, as appropriate.

Enhancements are scheduled for completion prior to the period of extended operation.

Page 3 of 3

ATTACHMENT 4 Nine Mile Point Nuclear Station New LRA Section B2.1.36, Bolting Integritv Program

  • Revise Table of Contents page B-ii to add new Section B2.1.36, Bolting Integrity Program.

"36. Bolting Integrity Program (Section B2.1.36) [Existing]."

  • Revise Section B2.0 (page B-8), "Aging Management Programs," to replace "Not applicable" with the Bolting Integrity Program in the "Nine Mile Point Program" column for NUREG-1 801 Number XI.M18, as follows:

NUREG.!!

1801

'NURG PR N

MIE POINT, 1NUMBER; PROGRAM XLIM18 Bolting Integrity Bolting Integrity Program (Section B2.1.36)

  • Add new Section B2. 1.36, Bolting Integrity Program, as shown on the following pages.

Page 1 of 4

\\

^

t B2.1.36 Bolting Integrity Program The Bolting Integrity Program manages aging effects due to loss of preload, cracking and loss of material of bolting within the scope of license renewal including safety-related bolting, high-strength bolting for NSSS component supports, and bolting for other pressure retaining components. Program activities include material selection and testing, bolting preload control, inservice inspection, plant operation and maintenance, and evaluation of the structural integrity of bolted joints. This program implements the guidance contained in EPRI Reports NP-5769, as modified by NUREG-1339, and TR-104213 except as stated below.

NUREG-1801 Consistency The Bolting Integrity Program is an existing program that takes exceptions to certain NUREG-1 801, Section Xl.M1 8 (Bolting Integrity) evaluation elements (Reference 2), and requires enhancements to be consistent with others.

Exceptions to NUREG-1801 The program described in NUREG-1801, Section XL.M18, includes structural bolting within the scope of the program and recommends that leaks in bolted joints for pressure retaining components (not covered by ASME Section XI) be inspected daily.

The scope of the Bolting Integrity program in NUREG-1 801 primarily applies to the ASME code piping and components including high strength bolting used in NSSS component supports where the actual yield strength is greater than 150 ksi (NUREG-1801 item number III.B.1.1.2-a). Other structural bolting used in supports, including expansion and anchor bolts, are managed under the ASME Section XI Inservice Inspection (Subsection IWF) Program (LRA Section B2.1.25) or the Structures Monitoring Program (LRA Section B2.1.28) in accordance with NUREG-1 801. The inspection frequency of leaks in bolting for non-ASME pressure retaining components will be determined based upon the safety significance and radiological conditions of the leaking component. In maintaining radiological exposure as low as reasonably achievable (ALARA), NMP will balance the safety significance of the leak with the expected personnel exposure to determine the proper leak inspection frequency.

Program Elements Affected Scope of Program Structural bolting used in supports, including expansion and anchor bolts, are managed under the ASME Section XI Inservice Inspection (Subsection IWF)

Program (LRA Section B2.1.25) or the Structures Monitoring Program (LRA Section B2.1.28) in accordance with NUREG-1 801.

Page 2 of 4

e

^

f

  • Monitoring and Trending The frequency of inspection for leaks in bolting for non-ASME pressure retaining components will be determined based upon the safety significance and radiological conditions of the leaking component.

Enhancements Enhancements to the Bolting Integrity Program include revisions to existing activities that are credited for license renewal to ensure the applicable aging effects are discovered and evaluated.

Program Elements Affected Revise applicable existing documents to ensure that the documents address the following elements:

Scope The method for structural integrity evaluation of bolting material in component support applications described in EPRI NP-5769, Volume 2, Section 11, will be referenced as an acceptable method for evaluating the integrity of all bolting (with suitable modifications). The applicable documents will be updated to reference EPRI NP-5769 and NUREG-1339 for safety-related bolting, and EPRI TR-104213 for non-safety-related bolting.

  • Preventive Actions Revise the applicable documents to restrict the use of lubricants containing molybdenum disulfide for bolting applications. Also, revise the applicable documents to restrict the use of high strength ( 2150 ksi yield strength) bolting material to only those applications that require it.

Enhancements are scheduled for completion prior to the period of extended operation.

Operating Experience NMPNS has reviewed both industry and plant-specific operating experience related to the Bolting Integrity Program and is aware of the types of bolting issues that have been reported and documented in the industry. The lessons learned from the industry experiences have been incorporated into the NMPNS bolting practices such that this program has adequately detected bolting integrity issues and has been effective in correcting issues prior to the loss of intended function. This program is continually adjusted to account for industry experience and research. As additional operating experience is obtained, lessons learned will be used to adjust this program as needed.

Page 3 of 4

.- -I I

Conclusion The Bolting Integrity Program has been effective in managing the aging effects of bolting within the scope of license renewal including safety-related bolting, high strength bolting for NSSS component supports, and bolting for other pressure retaining components.

Therefore, there is reasonable assurance that aging effects will be managed by the implementation of the Bolting Integrity Program such that SSCs WSLR will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

Page 4 of 4

ATTACHMENT 5 List of Reaulatorv Commitments The following table identifies those actions committed to by Nine Mile Point Nuclear Station, LLC (NMPNS) in this submittal. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.

REGULATORY COMMITMENT DUE DATE Enhance the Bolting Integrity Program and implementing procedures to: (1) more clearly restrict the use of lubricants containing molybdenum disulfide; (2) clearly restrict the use of high-strength ( 2150 ksi yield strength) bolts to only those applications that require it; (3) reference the evaluation method in Electric Power Research Institute (EPRI) NP-5769, Volume 2, as an acceptable method for assuring integrity of bolting material in component support applications; and (4) reference the EPRI reports (NP-5769 and TR-104213) and NUREG-1339 as source documents for the implementing procedures, as appropriate.

NMP1: August 22,2009 NMP2: October 31, 2026 Page 1 of 1

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