ML100090050

Summary of Telephone Conference Call Held on November 11, 2009, Between the U.S. NRC and Florida Power Corporation, Concerning a Draft RAI and the Applicant'S Response to a RAI Pertaining to the Crystal River Unit 3 Nuclear Generating Plant

ML100090050
Person / Time
Site:	Crystal River
Issue date:	03/01/2010
From:	Robert Kuntz License Renewal Projects Branch 2
To:	Office of Nuclear Reactor Regulation
KUNTZ R, NRR/DLR, 415-2989
References
Download: ML100090050 (32)

Text

March 1, 2010 LICENSEE: Florida Power Corporation FACILITY: Crystal River Unit 3 Nuclear Generating Plant

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON NOVEMBER 10, 2009, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND FLORIDA POWER CORPORATION, CONCERNING A DRAFT REQUEST FOR INFORMATION AND THE APPLICANT'S RESPONSE TO A REQUEST FOR INFORMATION PERTAINING TO THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Florida Power Corporation held a telephone conference call (teleconference) on November 10, 2009, to discuss a draft request for additional information (RAI) and the applicants's response to an RAI concerning the Crystal River Unit 3 Nuclear Generating Plant (CR-3) license renewal application. The teleconference was useful in clarifying the applicant's response to RAIs and to provide clarification on a draft RAI.

During the teleconference, the staff sought clarification on responses to RAIs 4.3.1-2, 4.3.1.2-1, 4.3.1.6-1, 4.3.3-2, 4.3.3-3, B.2.7-2, B.2.8-2, B.2.13-2, B.2.16-1, and B.3.1-2 provided in a letter dated October 13, 2009 (Agencywide Documents and Management System [ADAMS] Accession No. ML092890155) and RAI XI.S8 from letter dated October 2, 2009 (ADAMS Accession No. ML092790154). A summary of the discussion related to the RAI responses referenced are summarized below.

Safety-Related Coating Program In response to RAI XI.S8, the applicant stated that the Safety-Related Coatings Program and the CR-3 American Society of Mechanical Engineers Section Xl, Subsection IWE, Containment Inspection Program ensure that there will be proper maintenance of the protective coatings inside containment such that they will not become a debris source that could impact the operability of post-accident safety systems. The staff sought confirmation that the Safety-Related Coatings Program would remain applicable during the period of extended operation. The applicant stated that the program is a requirement as detailed in the CR-3 Final Safety Analysis Report.

License Renewal Application (LRA) Section 4.3 "Metal Fatigue" and LRA Aging Management Program (AMP) B.3.1 "Reactor Coolant Pressure Boundary Fatigue Monitoring Program" In response to RAI 4.3.1.2-1, the applicant provided endurance limits for non-bolting reactor vessel internals. The staff sought clarification on the basis cycles used for estimating the endurance limits.

Florida Power Corporation In response to RAI 4.3.1.6-1, the applicant stated that structural evaluations for the pressurizer surge nozzle, surge line and hot leg surge nozzle are described in BAW-2127. The staff recommended several actions to be resolved by the BAW-2127 authors in the staff's safety evaluation report (SER). The staff sought clarification from the applicant on the status of the action recommended in the staff's SER. The applicant stated that the current licensing basis is dependent on the resolution of those items and are therefore addressed outside of the license renewal process.

In response to RAI 4.3.3-2, the applicant stated that the combined usage factor (CUF) is permitted to exceed 1.0 when considering the Functional Specification 40-year design transients. The staff sought clarification on why the CUF was permitted to exceed 1.0. The applicant stated that the CUF was permitted to exceed 1.0 for calculation purposes and not for actual usage.

Also in response to RAI 4.3.3-2, the applicant stated that in the fatigue usage calculations for the low stratification transients, the most severe F en of 15.35 is used. The staff sought clarification on what the term low stratification transients meant. The applicant stated that these transients are those that have small top to bottom temperature gradient.

Also in response to RAI 4.3.3-2, the applicant stated that high-pressure injection (HPI) suction check valve test will occur 156 times which seemed in conflict with LRA Table 4.3-1 which indicates 240. The staff sought clarification on the proper number of tests will be performed on the HPI suction check valve as well as the core flood tank check valve. The applicant stated that the LRA assumed tests were conservative to bound the actual values to occur during extending period of operation.

In response to RAI 4.3.3-3, the applicant stated that prior to December 31, 1992, CR-3 did not maintain reactor coolant system (RCS) dissolved oxygen records and that prior to that date the expectation that maintaining overpressure of hydrogen in the Make-Up Tank and maintaining RCS hydrogen >15 cm 3/kg would ensure that RCS dissolved oxygen levels would remain <5 parts per billion. The staff sought clarification on how the hydrogen levels were procedurally controlled during that period and if there were records to document the maintenance of the hydrogen levels as stated.

In response to RAI B.3.1-2, the applicant stated that high cycle fatigue is not a concern for license renewal since it would be discovered during the current license period. The staff sought clarification on what the applicant would do if high cycle fatigue cracking were discovered.

LRA AMP B.2.7, "Flow Accelerated Corrosion Program" The response to RAI B.2.7-2 included Wear Rate Analysis: Combined Summary Report table. In the table, the CHECWORKS predicted value was in some cases greater than the initial value in the tables. The staff sought clarification on how the predicted value could be less than the initial value in the table. The applicant stated that the initial value was a nominal value provided by the manufacturer and that the actual value could very by some margin from the nominal value.

Florida Power Corporation LRA AMP B.2.8 "Bolting Integrity Program" In Enclosure 2 of the October 13, 2009 letter, LRA Section B.2.8 was amended in response to RAI B.2.8-2. The amendment to the LRA stated that the sampling sizes will be based on methodology in Electric Power Research Institute TR-107514. The staff sought further clarification on the applicant's sampling plans, specifically the number of samples planned and the basis for that number. The applicant stated that they sample population would be based on a "90/90" confidence level.

LRA AMP B.2.13 "Fire Protection Program" In RAI B.2.13-2, the staff requested the applicant to provide a basis for exceeding the Generic Aging Lessons Learned (GALL) Report recommended frequency of every outage for inspection of the fire barrier walls, ceilings, and floors. The applicant's response stated that the CR-3 Fire Protection Program performs visual inspection of walls, ceilings, and floors on a frequency commensurate with the safety significance of the structure and its condition but not to exceed 10 years. The staff sought clarification on how these inspections are conducted and the basis for the inspection frequency.

LRA AMP B.2.16 "Fuel Oil Chemistry Program"

The response to RAI B.2.16-1 state that new preventive maintenance periodic activities using ultrasonic testing (UT) and internal tank inspections have recently been generated for FST-2A and FST-2B. The staff sought clarification on the frequency of the UT and internal inspections. The applicant stated that the inspections hadn't been completed to date and that they would be a one-time inspection to determine the extent of condition. The necessity of future inspection would be based on the findings of the one time inspections.

Enclosure 1 provides a listing of the participants and Enclosure 2 contains a listing of the draft RAIs discussed with the applicant, including a brief description on the status of the items.

The applicant had an opportunity to comment on this summary.

/RA Robert F. Kuntz, Sr. Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosures:

As stated cc w/encls: See next page

ML100090050 OFFICE PM:RPB2:DLR LA:RPOB:DLR BC:RPB2:DLR PM:RPB2:DLR NAME RKuntz IKing DWrona RKuntz (Signature) DATE 01/23/10 01/20/10 02/23/10 03/1/10 Memorandum to Florida Power Corporation from Robert F. Kuntz dated March 1, 2010

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON NOVEMBER 10, 2009, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND FLORIDA POWER CORPORATION, CONCERNING A DRAFT REQUEST FOR INFORMATION AND THE APPLICANT'S RESPONSE TO A REQUEST FOR INFORMATION PERTAINING TO THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT LICENSE RENEWAL APPLICATION

DISTRIBUTION

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RKuntz DBrittner AJones, OGC LLake, RII MSykes, RII TMorrissey, RII RReyes, RI ENCLOSURE 1 TELEPHONE CONFERENCE CALL CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS NOVEMBER 10, 2009

PARTICIPANTS AFFILIATIONSRobert Kuntz U.S. Nuclear Re gulator y Commission (NRC) Seun g Min NRCAbdul Sheikh NRC

Duc N g u yen NRCDavid Alle y NRCAndrew Prinaris NRC Clifford Doutt NRC Albert Won g NRC Chuan g-Yeh Yan g NRC Alo ysius Abodoako NRCEmma Won g NRCMadhumita Sircar NRC Allen Hiser NRC James Medoff NRC Todd Mintz Center for Nuclear Waste Regulatory Analysis (CNWRA)

Yi-Min Pan CNWRA Keith Axler CNWR AMike Heath Florida Power Cor poration (FPC)Jeff Lane FPCChris Malner FPC

Bob Re ynolds FPCMike Fletcher FPC Ton y Po plis FPCTom Atkinson FPC

Wa yne Bickleme yer FPC ENCLOSURE 2 DRAFT REQUEST FOR INFORMATION CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT NOVEMBER 10, 2009 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Florida Power Corporation (FPC or the applicant) held a telephone conference call on November 10, 2009, to discuss and clarify the following draft request for additional information (D-RAI) concerning the Crystal River Unit 3 Nuclear Generating Plant (CR-3) license renewal application (LRA).

D-RAI 3.1.2.2.2.1-1

Background

LRA Section 3.1.2.2.2.1 addresses the loss of materiel due to general, pitting, and crevice corrosion in the steel pressurized-water reactor (PWR) once-through steam generator shell exposed to treated water and steam. The staff reviewed LRA Section 3.1.2.2.2.1 against the criteria of Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants (SRP-LR) Section 3.1.2.2.2.1, which states that loss of material due to general, pitting, and crevice corrosion could occur in the steel PWR steam generator shell assembly exposed to secondary feedwater and steam. The LRA considers the same aging mechanisms. It also states that CR-3 will manage the loss of material due to general, pitting and crevice corrosion in the steel components exposed to secondary feedwater/steam and reactor coolant in the steam generator with the Water Chemistry Program. In addition, CR-3 will implement a one-time inspection (OTI) program for susceptible locations to verify the effectiveness of the Water Chemistry Program in managing the loss of material due to general, pitting and crevice corrosion.

Issue The LRA proposes to extend the aging management of loss of material due to general, pitting, and crevice corrosion in the steel PWR steam generator shell assembly to other components of the steam generators, in relation with the material, the environment and the aging effect, such as the tube support plate assembly (tube support plate, rods, nuts-), the steam generator main feedwater spray nozzle flanges, the steam generator baffle assemblies, the steam outlet nozzle, the steam generator auxiliary feedwater nozzle thermal sleeves, the steam generator secondary side nozzles and the steam generator secondary manway and handhole opening covers. In LRA Table 3.1.2-1, for these additional components, the applicant considers that these items are consistent with the Generic Aging Lessons Learned (GALL) Report in all aspects (Note A), whereas the components are different from the one recommended in the GALL Item IV.D2-8.

Moreover, it is not clear to the staff how the OTI program will be implemented for other components than the shell assembly recommended in the GALL Report and will be able to detect adequately the aging effect, especially inside the tube bundle in the case of the tube support plate assembly.

Request Please explain how you will implement the OTI program (non-destructive examination techniques, sample, etc.) for steam generator components whose access appears more difficult than for shell assembly in order to verify the effectiveness of the water chemistry program and the absence of the aging effect of concern.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.1.2.1-4

Background

In LRA Table 3.1.2-1, the applicant addresses the steam generator tube sheets aging effects for reactor coolant and air-indoor uncontrolled. However, the applicant does not address the aging effect for the surface of the low alloy steel steam generator tube sheets in the environment of secondary feedwater/steam.

Issue For similar component/environment combinations (such as GALL Report Item IV.D2-8) the GALL Report identifies an aging effect of concern of loss of materiel due to general, pitting, and crevice corrosion.

Request Clarify why this aging effect for the steam generator tube sheets is not of concern at CR-3. If you need to address this aging effect, please clarify how it will be managed.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.1.2.1-5

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Background===

LRA Table 3.1.1 Item number 59, states that the aging effect of wall thinning due to flow accelerated corrosion for steam generator feedwater and auxiliary feedwater nozzles and safe ends, and steam nozzles and safe ends is not applicable to its steam generators. This aging effect corresponds to GALL Report Item IV.D2-7.

Issue The staff noted that the LRA does not provide any explanation for eliminating this aging effect.

Request Clarify why wall thinning due to flow accelerated corrosion for steam generator feedwater and auxiliary feedwater nozzles and safe ends, and steam nozzles and safe ends is not an aging effect of concern at CR-3.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.1.2.1-6

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Background===

LRA Table 3.1.2-1 addresses aging management review (AMR) item of reduction of heat transfer effectiveness due to fouling of heat transfer surfaces for nickel alloy steam generator tubes and sleeves exposed to reactor coolant (inside) and to treated water (outside). As stated by the applicant, this aging effect is not in the GALL Report (Note H).

Issue The applicant states in plant-specific Note 104 that fouling of the steam generator tubes has not been observed at CR-3. It is not clear to the staff whether this comment applies to fouling from the inner diameter (ID), outer diameter (OD), or both. In addition, it is not clear that the aging mechanism of fouling from the ID surface of the steam generator tubes had been detected at any U.S. plant and should be taken into account.

Moreover, the applicant does not explain how the aging management programs (AMPs) it prescribes, especially the steam generator tube integrity program, can manage ID fouling of the steam generator tubes.

Request 1. Explain why you selected the aging mechanism of fouling of the steam generator tubes from the inside surface. 2. Discuss how the AMPs you prescribed can manage this effect.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.1.2.1-7

Background

LRA Table 3.1.2-1 addresses AMR items for loss of material due to crevice and pitting corrosion for the steam generator tubes and sleeves made of nickel base alloys and exposed to reactor coolant (inside).

While the GALL Report does not have an exact corresponding AMR for these steam generator components, the LRA relates the components to GALL Report Item IV.C2-15 which identifies an aging effect of loss of material due to crevice and pitting corrosion in relation to the material and the environment. The LRA states it will manage this aging effect with only the Water Chemistry Program as recommended by GALL Report Item IV.C2-15.

Issue The staff finds the LRA does not provide enough information to verify whether the Water Chemistry Program according to the GALL Item IV.C2-15 is sufficient to manage the aging effect of loss of material due to pitting and crevice corrosion for the steam generator tubes, sleeves and plugs.

The staff concludes that the applicant should apply some condition monitoring Water Chemistry Program or complete this program with a confirmatory inservice inspection (ISI)-based program, for example on the basis of the steam generator tube integrity program, in order to verify that the Water Chemistry Program achieves its preventive purposes.

Request Clarify why you consider that the Water Chemistry Program by itself will be sufficient to manage the loss of material due to pitting and crevice corrosion for these components, without any additional condition monitoring or ISI-based program.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI B.2.9-6

Background

LRA Section B.2.9 states that the steam generators at CR-3 are scheduled to be replaced in 2009. However, the staff noted that the applicant did not provide any information in the LRA regarding the design of the new steam generators that will be installed this year.

Issue The staff cannot determine if the current AMR and AMP addressed by the applicant in sections of LRA Table 3.1.2-1 related to the present steam generators will still be relevant for the replacement ones. Based on the information provided, the staff needs further information in order to evaluate the sufficiency of the AMR proposed and the associated AMPs that could evolve because of the installation of the new steam generators.

Request 1. Specify all differences between the original steam generators and the replacement ones, especially concerning their design and the materials used.

2. For any differences identified, provide the revised items of LRA Table 3.1.2-1 related to the steam generator and affected by those modifications.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.4.2.2.8-1

Background

The GALL Report in relevant table rows describe that it is possible to have microbiologically influenced corrosion (MIC) occurring in stainless steel piping, piping components, piping elements, and other plant components when exposed to contaminants in lubricating oil. GALL XI.M39 AMP titled "Lubricating Oil Analysis Program," relies on the periodic sampling and analysis of lubricating oil to maintain contaminants to within acceptable limits, thereby minimizing the exposure of stainless steel to a corrosive environment. The GALL Report, for this program accepts that a OTI of selected components at susceptible locations to be an acceptable method to ensure that corrosion is not occurring and that the components' intended functions will be maintained during the period of extended operation.

Issue LRA Section 3.4.2.2.8, titled "Steam and Power Conversion System Stainless Steel Piping, Piping Components, and Piping Elements and Heat Exchanger Components Exposed to Lubricating Oil," states that CR-3 does not take steps to predict MIC in lubricating oil systems unless indicated by operating experience. Microbacterial growth could be prominent in aqueous and oil exposed environments. The staff identified instances of operating experience where water had infiltrated CR-3s lubricating oil environment. Since MIC requires metal, nutrients, and an electrolyte for growth, draining and refilling the systems with oil may not curb the growth of microorganisms. In addition, SRP-LR clearly states, that control of lube oil contaminants, which can serve as nutrients to biofilms, may not always be adequately monitored to preclude corrosion. For stainless steel, it is possible, to have the steel's protective surface film depleted or damaged by such microorganisms. For carbon and low alloy steel MIC may even be more exacerbated. In none of the listed structures, systems, and components (SSCs) the applicant identifies how to deal effectively with MIC during extended operation, other than committing to the OTI Program.

Request 1. What kind of measures does CR-3 use to identify, curb, and manage aging effects due to MIC? 2. Provide the frequency of oil sampling and identify the monitored parameters.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.3.2.33-1

Background

GALL AMP, XI.M36 titled "External Surface Monitoring Program," is a condition monitoring program. It focuses to have inspectors visually identify general corrosion aging effects in steel and other ferrous materials. It notes that general corrosion can also manifest itself as a byproduct (e.g., discoloration or coating degradation) of other forms of corrosion, e.g., pitting and crevice. This AMP, however, does not address galvanic corrosion. There is no discussion in the Scope of Program, whether this form of corrosion can manifest itself as a byproduct for general corrosion.

Issue The GALL Repot, in Auxiliary Systems for Piping, Piping Components, and Piping Elements, identifies an aging effect of concern of loss of material due to general, pitting, and/or crevice corrosion. For items in the LRA, however, galvanic corrosion is identified as the aging mechanism of interest. This mechanism is rooted in the interaction of the two dissimilar metals with different potentials when placed in electrical contact in an electrolyte. The effects of this mechanism may not be as visible and detectable as that of general corrosion, especially when the adjacent dissimilar metals exhibit a small differential in electrical potentials.

Request How will the aging effects of loss of material due to galvanic corrosion of external surfaces be managed?

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI B.2.25-1.1

Background/Issue Progress Energy Letter 3F1009-07, dated October 13, 2009, submitted responses to RAIs related to different AMPs. The response to RAI B.2.25-1 stated that the degraded area at the liner to moisture barrier interface that was ultrasonic testing (UT) examined in 1997 was not designated as a Surface Area Requiring Augmented Examination in accordance with American Society of Mechanical Engineers (ASME) Subsection IWE-1241. There have been no additional inspections of the degraded area since 1997. One area had a measured pit depth of 0.065 in. with a remaining wall thickness of 0.307 in. at an area of the liner with a UT thickness reading of 0.372 in.

Request 1. Explain why the degraded area of the liner plate was not designated for augmented inspection even after the IWE program was implemented at CR-3 in 1997 since the pit due to corrosion at the subject area was 0.065 inch or 17.5 percent of the liner plate thickness. ASME Subsection IWE requires augmented inspection if the base metal thickness is reduced by greater than 10 percent.

2. Provide plans for inspecting the subject area during the current and future refueling outage.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI B.2.25-2.1

Background/Issue The response to RAI B.2.25-2 (in the aforementioned October 13, 2009 letter) stated that CR-3 has planned for a full visual examination of the accessible ASME Subsection IWE components including the accessible liner wall and moisture barrier in the 2009 refueling outage (RF016). In addition, CR-3 will be performing repairs of the degraded moisture barrier as needed to ensure a watertight seal between the concrete and the liner plate. Any areas of corrosion of the liner plate which are unsatisfactory will be further evaluated as to the extent of the degradation and any addition corrective actions to be performed. There are no plans to remove the moisture barrier to investigate the condition of the liner plate at the interface point of the liner and the moisture barrier or to remove concrete to inspect the floor liner plate during the 2009 refueling outage. Request Explain why CR-3 has no plans to remove the moisture barrier to investigate the condition of the liner plate corrosion at the moisture barrier and wall and floor liner plate below moisture barrier since moisture barrier degradations have been documented starting in 2003 even after the moisture barrier was reinstalled in 1997. In 2007, the moisture barrier was found to be damaged at 12 locations around the circumference. The damaged moisture barrier provides a path for water penetration and corrodes the liner plate. In addition, in 1997, the liner plate was found to be degraded at a number of locations. There has not been any follow up examination of the liner plate even though the moisture barrier has been damaged since 2003.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI B.2.25-3.1

Background/Issue The response to RAI B.2.25-3 (in the October 13, 2009 letter) stated that there has been no testing to determine the gaps between the liner plate and concrete. Bulges or indications of bulges determined through tapping are identified on inspection data sheets. During the refueling outage in 2007, 28 bulges in the liner plate at various locations were identified during the general visual examination. Two of the bulged areas were 12 in. x 36 in., one was 12 in. x 24 in. and the remainders were all 12 in. x 12 in. It was determined that the areas were minor in nature and did not adversely affect the structural integrity of the Reactor Building or its capability to perform its intended function over the next refueling cycle. These areas will continue to be visually inspected in accordance with ASME Section XI, Subsection IWE requirements.

Request Explain in detail the basis for the determination that 28 bulges in the liner plate did not adversely affect the structural integrity of the reactor building. Specifically, provide the analysis/review that was performed to conclude the liner plate bulged area of 12 in x 36 in., with no contact with concrete, would be able to resist the design loads during a design basis accident condition.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI B.2.26-1.1

Background/Issue The response to RAI B.2.26-1 (in the letter dated October 13, 2009) stated that the original wire relaxation curve, provided by test data from the wire vendor, forms the bases for the wire relaxation value. The original wire relaxation curve was based on the wire described in the Final Safety Analysis Report (FSAR) Section 5.2.2.3 and the relaxation curve shown on FSAR Figure 5-26. The values on FSAR Figure 5-26 for wire number six were multiplied by a factor of 2.68 to obtain the relaxation loss in percent at specific years. The 2.68 multiplication factor was from two factors. A 1.47 factor was determined to allow for a long term temperature of 104°F versus 68°F on FSAR Figure 5-26. A 1.82 factor was determined based on a conservative relaxation value of two percent at 40 years, as opposed to a 1.1 percent on FSAR Figure 5-26 (2.0/1.1).

Request Explain in detail the basis for the 1.47 factor that was used for relaxation of prestressing steel due to a long term temperature of 104°F versus 68°F or alternately any test data to support this assumption.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI B.2.31-1.1

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Background===

GALL AMP X1.E1, under Element 4 (Detection of Aging Effects) states that a representative sample of accessible electrical cables and connection installed in adverse localized environment should be visually inspected for cable and connections jacket surface anomalies. LRA AMP B.2.31 stated that it will utilize plant operating experience to determine the areas to be inspected. It further stated that based on this review of operating experience, the plant areas to be inspected become localized in nature, consisting of limited area of a much larger plant areas or zone. In a letter dated September 11, 2009 (RAI B2.31-1), the staff requested technical justification how Element 4 of AMP B.2.31 is consistent with that in GALL AMP XI.E1 and how it will envelop electrical cables and connections in the scope of this AMP located in adverse localized environments.

The response to the staff request, in a letter dated October 13, 2009, stated that the CR-3 AMP utilizes operating experience to establish where adverse localized environment may exist and determine the plant area to be inspected. Operating experience covers a wide range of plant-specific documents and industry related guidance. The RAI response also stated that site specific operating experience includes the use of environmentally qualified zone maps, environmental survey, maintenance record, corrective actions and conversations with plant personnel to establish where the adverse localized environments may exist based on past cable failures, cables that exhibited the effects of aging, areas of localized overheating, hot spots, etc.

Issue The staff questioned the basis for determining adverse localized environments. Solely relying on operating experience alone may not identify/envelop all adverse localized environments. The adverse localize environment could be those created by elevated temperature such as steam generators, feedwater heaters, main steam valves, uninsulated or unshielded hot process piping, steam or packing leaks, high-powered incandescent lighting, motor exhaust air vents, areas with equipment that operate at high temperature, areas with inadequate ventilation, etc., are sources of adverse localized environments. Electrical cables and connections normally within three feet of these sources may be subjected to an adverse localized environment. Adverse localized environment can be identified through plant operating experience reviews, communication with maintenance, operations, and radiation protection personnel, and the use of environmental surveys.

Request: Provide additional technical justification of how utilizing operating experience alone will identify/envelop all adverse localized environments.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.1.2.2.16.2-1

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Background===

Section 3.1.2.2.16 of the SRP-LR indicates that stress corrosion cracking (SCC) can occur for stainless steel pressurizer spray heads. The GALL Report recommends the water chemistry and the OTI programs to manage this degradation mechanism.

Issue LRA Section 3.1.2.2.16.2 indicates that the pressurizer spray heads are not applicable to CR-3 because they have no intended function. It is not clear to the staff why this material must not be controlled under an aging management program. Request Provide additional information on why the pressurizer spray heads do not need to be considered for any aging degradation mechanisms and as such, subject to an AMR.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.2-1

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Background===

The LRA addresses hardening and loss of strength of external surfaces exposed to air of:

• elastomeric flexible connections due to degradation;

• elastomers in expansion joints, piping, piping components, piping elements, and tanks due to degradation;

• poly-vinyl chloride (PVC) or thermoplastic ducting, ducting components, piping, piping components, piping elements and tanks due to elastomer/plastic degradation;

• fiberglass or fiber reinforced plastic piping, piping components, piping elements and tanks due to elastomer/plastic degradation; and

• elastomers in expansion joints, piping, piping components, piping elements, and tanks due to degradation.

The LRA acknowledges that aging may occur for this combination of materials and environments and proposes to manage it through the use of its AMP "External Surfaces Monitoring" (LRA B.2.22).

Issue In its review of these items the staff noted that the external surfaces monitoring program contained in the GALL Report is a visual inspection program and that its scope is limited to steel surfaces. The staff also noted that the LRA has committed to enhance its external surfaces monitoring program to include components constructed from materials other than steel and to detect additional aging effects associated with those materials, including hardening and loss of strength. The staff further noted that the LRA has not explicitly committed to enhancing its program to include inspection techniques other than visual inspection. Lastly, the staff noted that hardening and loss of strength are not directly detected by visual examinations and that visual changes in elastomers and plastics may, but need not, occur in conjunction with hardening and loss of strength.

Request Confirm that the enhancements proposed for the External Surfaces Monitoring Program will specifically include physical manipulation and other investigative methods designed specifically to detect hardening and loss of strength in elastomers.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.2.2.1-1

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Background===

The GALL Report, Table 1, indicates that for stainless steels or steels with stainless steel cladding, exposed to reactor coolant, there is a potential for cracking due to cyclic loading (Item IV.C2-26). The AMP recommended in the GALL Report is ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD.

Issue The LRA indicates that there are stainless steel components (e.g. Reactor Coolant Pressure Boundary [RCPB] piping; Reactor Coolant Pump Safe Ends) that are subjected to the reactor coolant environment. These components do not include the aging effect of cracking due to cyclic loading. It is not clear to the staff why cyclic loading and a corresponding AMP have not been included for these components.

Request Provide additional information indicating why the aging mechanisms of cyclic loading is not included for stainless steel components exposed to the reactor coolant environment including Reactor Coolant Pump Safe Ends (RCPB piping), Flow Meter Assembly (RCPB Piping), Hot Leg Surge Line Nozzle (RCPB Piping), Hot Leg Surge Line Nozzle Safe End (RCPB Piping),

Surge Line Nozzle Thermal Sleeve (Pressurizer), Spray Line Nozzle Thermal Sleeve (Pressurizer), and the Surge Line Nozzle Safe End (Pressurizer).

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.2.2.2-1

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Background===

On page 3.2-28 of the LRA, in Table 3.2.2-2, for the nickel base alloy core flood tanks in treated water environment, the Nickel Alloy Commitment is credited to managing cracking due to SCC.

Issue In LRA, Section A.1.1 and LRA Commitment No. 2, the applicant committed to complying with applicable U.S. Nuclear Regulatory Commission Orders and implementing applicable bulletins, generic letters, and staff-accepted industry guidelines. Table 3.2.2-2 of the LRA correctly identifies that the GALL Report does not contain any nickel-alloy components in the Engineered Safety Features, Emergency Core Cooling System (PWR) Table (Table V.D1). However, Table V.D1 does identify SCC as an aging effect of concern for stainless steel piping managed by the Water Chemistry Program. For other systems in the LRA and GALL Report, management of SCC in nickel alloy components is managed by the Nickel Alloy Commitment and various AMPs including the Water Chemistry Program and the ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD, Program.

Request Provide justification and explain how the Nickel Alloy Commitment provides adequate aging management for the aging effect of cracking due to SCC in nickel base alloy core flood tanks exposed to a treated water environment.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.2.2.2.3.1-1

Background

In the GALL Report, Table 2, stainless steel containment isolation piping and components internal surfaces exposed to treated water are subjected to loss of material due to pitting and crevice corrosion. The AMPs in the GALL Report suggested to manage this degradation is Water Chemistry and OTI programs.

Issue In the LRA, the containment isolation piping and components subjected to treated water is not listed under stainless steel containment isolation piping and components internal surfaces exposed to treated water in Table 3.2.1 (Item 3.2.1-03). Instead it is listed under stainless steel piping, piping components, piping elements, and tanks exposed to treated borated water in Table 3.2.1 (Item 3.2.1-49). As such, the loss of material due to pitting and crevice corrosion for this component is singularly managed under the Water Chemistry Program. It is not clear to the staff why the proposed program is adequate to manage this particular aging management concern. Request Provide additional information on why the use of the Water Chemistry Program without the OTI Program is adequate to manage the loss of material due to pitting and crevice corrosion for this aging management issue.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.2.2.2.3.6-1

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Background===

In the GALL Report, Table 2, it is indicated that stainless steel piping, piping components, piping elements, and tank internal surfaces exposed to condensation may potentially undergo loss of material due to pitting and crevice corrosion.

Issue LRA Section 3.2.2.2.3.6 indicated that the reactor building spray piping inside containment is verified drained, not subjected to wetting through system operation, and is kept in standby at ambient conditions. Therefore, it was indicated in the LRA that the reactor building spray piping is not considered susceptible to condensation. It is unclear to the staff how the piping is ensured to be drained and moisture is kept out of it; thus, eliminating the ability for condensation.

Request Provide additional information regarding how the reactor building spray piping inside containment is ensured to be drained, and how moisture is not allowed to pass through seals into the spray piping.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.2.2.3-1

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Background===

LRA Tables 3.2.2-2, 3.2.2-3, 3.3.2-20, 3.3.2-22, 3.3.2-23, 3.3.2-24, 3.3.2-27, 3.3.2-33, 3.3.2-42, 3.3.2-53, 3.3.2-54, 3.3.2-57, 3.4.2-2, 3.4.2-7, 3.4.2-8, and 3.4.2-12 contain items addressing piping insulation exposed to outdoor air and uncontrolled indoor air. The LRA proposes that neither the component nor the material and environment combination is evaluated in the GALL Report (Note J). The LRA further proposes that this combination of environment and material is not subject to aging and that no AMP is required.

Issue In its review of these items the staff noted that, depending on the application, piping insulation may be fabricated from many materials. These materials commonly include polymeric foams, inorganic fibers, and solid ceramics. The staff also noted that the applicant did not state the type of insulation which was being used, the material of the pipe over which it was being applied or the range of temperatures expected at the interface between the pipe and the insulation. The staff further noted that some types of insulation, e.g., polymeric foams, are subject to aging and may require aging management. Finally, the staff noted that the combined use of some forms of insulation and piping materials in some environments, e.g., chloride containing insulation over stainless steel pipe in humid environments, may create additional aging effects in the piping material.

Request Please provide sufficient information concerning: the type of insulation being used; the type of pipe over which it will be applied; the compatibility between the insulation and the pipe; and whether the presence of condensation or other moisture is possible; to allow the staff to conclude whether the insulation is subject to aging or whether the use of the insulation will result in unexpected aging of the pipe material.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.3.2.2-1

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Background===

Atmospheric chloride is known to induce various degradation mechanisms, which can affect the lifetime of stainless steel materials. These degradation mechanisms include pitting, crevice corrosion, and SCC. Locations near the coast will have much higher concentration of chloride aerosol particles in the air and a higher susceptibility towards these various degradation mechanisms.

Issue In the LRA, various tables including but not limited to Table 3.3.2-2, Table 3.2.2-10, and Table 3.2.2-12, indicate that components are subjected to uncontrolled air. These components are listed as having no degradation mechanisms and as such require no aging AMP. It is unclear to the staff how the chlorides from the coast are removed from the uncontrolled air source so that the aging mechanisms associated with chloride aerosols do not need to be evaluated.

Request Provide additional information that will highlight why degradation mechanisms associated with chloride aerosols (i.e., pitting, crevice corrosion, SCC) do not need to be evaluated for stainless steel materials in uncontrolled air environments.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.3.2.21-1

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Background===

On page 3.3-188 of the LRA in Row 2 of Table 3.3.2-21, the nickel base alloy cooler tubes exposed to treated water is managed by the Water Chemistry Program. Issue The GALL Report recommends the use of the Water Chemistry Program and the OTI Program to manage this aging issue (GALL Report, Item V.A-16). The OTI Program provides measures to verify the effectiveness of the Water Chemistry Program. It is not clear how the Water Chemistry Program alone provides adequate aging management for this aging effect in these components.

Request Provide a detailed technical justification of why the OTI Program is not needed to verify the effectiveness of water chemistry control in managing the aging effect of reduction of heat transfer effectiveness due to fouling of heat transfer surfaces in these nickel base alloy components.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.3.2.28-1

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Background===

LRA Tables 3.3.2-28 and 3.3.2-36 addressed the loss of preload of carbon or low alloy steel/ stainless steel closure bolting in the fuel oil system and fire protection system, respectively, of the auxiliary systems, which are exposed to soil (outside). The LRA stated that the aging effect of the AMR items is due to thermal effects, gasket creep and self-loosening and no Table 1 item is related with the AMR items. The consistency note that the applicant claimed for the AMR items was Note J, which means neither the component nor the material environment combination are evaluated in the GALL Report.

Issue In relation to the closure bolting items exposed to soil, the staff noted that the LRA did not provide detailed information on how the Bolting Integrity Program manages the loss of preload and loss of material of the buried closure bolting components especially in terms of the inspection extent and schedules. The staff also found a need to review relevant operating experience regarding the loss of preload and loss of material of the buried closure bolting components and associated leakage.

Request 1. Describe how the Bolting Integrity Program manages the loss of preload and loss material of the buried closure bolting components including the inspection extent and schedule. 2. Clarify whether the bolts exposed to soil are coated. 3. Provide operating experience regarding the loss of preload and loss of material of the buried closure bolting and associated leakage as relevant.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.3.2.35-1

Background

In the GALL Report, Table 3 indicates that for many stainless steel materials subjected to treated water, a potential degradation mechanism is fouling. The AMP suggested by the GALL Report is the Water Chemistry Program along with the OTI Program.

Issue LRA Tables 3.3.2-35, 3.3.2-36, and 3.3.2-53 contain stainless steel material in an environment of treated water. For the aging mechanism of fouling, the AMP only includes the Water Chemistry Program.

Request Provide additional information on why only the Water Chemistry Program and not both the Water Chemistry and OTI programs are necessary to control fouling of stainless steel components in a treated water environment.

Discussion

The applicant stated that it credits both programs as recommended in the GALL Report. The staff verified that the LRA is consistent with the GALL Report, therefore, this question is withdrawn and will not be sent as a formal RAI.

D-RAI 3.3.2.36-1

Background

LRA Table 3.3.2-36 contains items which address hardening and loss of strength due to elastomer/plastic degradation of PVC or thermoplastic piping, piping components, standpipes, hydrants and tanks exposed to fire water. The applicant proposes that neither the component nor the material and environment combination is evaluated in the GALL Report (Note J). The applicant acknowledges that aging may occur for this combination of materials and environments and proposes to manage it through the use of its AMP "Fire Water System" (LRA B.2.14).

Issue In its review of these items, the staff noted that hardening and loss of strength of PVC and thermoplastics are not directly detected by visual examinations and that visual changes in elastomers and plastics may, but need not, occur in conjunction with hardening and loss of strength. The staff also noted that hardening and loss of strength of PVC and thermoplastic materials need not be accompanied by a change in wall thickness. The staff further noted that the fire water system AMP contained in the GALL Report is designed to detect changes in pipe wall thickness through visual inspections and other means but does not contain any test method which will directly assess hardening or loss of strength.

Request Justify how the proposed AMP will detect changes in hardness and strength of the plastic components under consideration or propose an aging management program which will directly measure these changes.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.3.2.36-2

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Background===

LRA Table 3.3.2-36 contains items which address PVC or thermoplastic piping, piping components, standpipes, hydrants and tanks exposed to soil. The applicant proposes that neither the component nor the material and environment combination is evaluated in the GALL Report (Note J). The applicant further proposes that this combination of environment and material is not subject to aging and that no AMP is required.

Issue In its review of these items, the staff noted that there are many polymeric materials which fall within the definition of "PVC and thermoplastics." The staff also noted that it is unlikely that all the materials within this class of materials will respond in the same manner to exposure to soil and ground water.

Request Identify the specific material or materials in use and justify why these materials do not experience aging when exposed to soil or ground water or, alternatively, propose an AMP to manage the aging of these materials.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.3.2.36-3

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Background===

On page 3.3-284 of the LRA, in Table 3.3.2-36, the AMR result for steel components in fuel oil environment with an aging effect of loss of materials due to MIC indicates that the Fire Protection and Fuel Oil Chemistry AMPs are credited.

Issue The GALL Report recommends the use of the Fuel Oil Chemistry Program and the OTI Program to manage the aging effect of loss of materials due to MIC for steel components in fuel oil environment (GALL Report, Item VII.H1-10). The OTI Program provides measures to verify the effectiveness of the Fuel Oil Chemistry Program. It is not clear how the Fire Protection Program and the Fuel Oil Chemistry Program provide adequate aging management for this aging effect in these components.

Request Provide a detailed technical justification of why the OTI Program is not needed to verify the effectiveness of fuel oil chemistry control in managing the aging effect of loss of materials due to MIC in the identified components.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.3.2.49-1

Background

LRA Table 3.3.2-49 addresses hardening and loss of strength due to degradation of external surfaces of elastomers in expansion joints exposed to uncontrolled indoor air. The applicant proposes to manage this aging process through the use of its AMP, "Open Cycle Cooling Water System" (LRA B.2.10). The LRA proposes that neither the component nor the material and environment combination being considered is included in the GALL Report (Generic Note J).

Issue In its review of Table 3.3.2-49, the staff noted that the LRA AMP "Open-Cycle Cooling Water System" has been enhanced from the corresponding GALL AMP to include periodic maintenance of nuclear services and decay heat seawater expansion joints. The staff also noted that the Open-Cycle Cooling Water System AMP relies on procedures established by Generic Letter 89-13 and that this generic letter only addresses issues associated with the interaction of the inner surface of pipes and service water. The staff further noted that neither the Open-Cycle Cooling Water System AMP nor the generic letter contain test methods suitable for identifying hardening or loss of strength of elastomers. Given that the external surfaces of elastomer expansion joints are not within the scope of the Open-Cycle Cooling Water System AMP and given that this AMP does not contain appropriate test methods for detecting hardening or loss of strength of elastomers, the staff is unsure how this AMP will adequately manage the aging effect in question. The notes that the LRA has proposed to use the External Surfaces Monitoring AMP (LRA B.2.22) to manage aging for elastomers in other piping systems.

Request Explain why it is appropriate to use the proposed AMP to manage aging and how the proposed AMP will adequately accomplish that task. Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.4.2.1-1

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Background===

The GALL Report indicated in Table 4, line Item 33, that stainless steel heat exchanger components exposed to raw water may undergo loss of material due to pitting, crevice, and MIC, and fouling. In Table 4, line Item 34, the GALL Report indicates that steel, stainless steel, and copper alloy heat exchanger tubes exposed to raw water may undergo reduction of heat transfer due to fouling. The GALL Report further suggests that this degradation mechanism can be managed by the Open-Cycle Cooling Water System Program.

Issue In LRA Table 3.4.2-1, it is indicated that the loss of material due to pitting, crevice corrosion, and MIC of stainless steel piping, piping components, piping elements, tanks, and condenser vacuum pump heat exchanger exposed to raw water is managed by the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program. It is not clear to the staff how this aging management program will be able to address this aging issue.

Request Provide additional information indicating how the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program is acceptable for managing loss of material of stainless steel exposed to raw water.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.4.2.2-1

Background

In the GALL Report, Table 4 indicates that steel piping, piping components, and piping elements exposed to steam for the steam and power conversion system can be subject to loss of material due to general corrosion. The GALL Report suggests managing this degradation using a Water Chemistry Program and a OTI Program.

Issue In the LRA various carbon or low alloy steel components for the steam and power conversion system are subjected to an environment of steam and may undergo general corrosion. The AMP for this material aging process is Water Chemistry Program. It is not clear to the staff how the use of a Water Chemistry Program alone is consistent with the GALL Report and will be able to manage this aging issue.

Request Provide additional information on why a OTI Program is not necessary to manage the general corrosion of carbon or low alloy steel components in the steam and power conversion system.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.4.2.2.3-1

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Background===

In the GALL Report, Table 4, steel piping, piping components, and piping elements exposed to raw water in the steam and power conversion system are subjected to possible loss of material from general corrosion, pitting, crevice corrosion, MIC, and fouling. The recommended AMP is suggested as being plant-specific.

Issue LRA, Section 3.4.2.2.3 indicated that there is no steel piping or piping components exposed to raw water, so the aging mechanisms in this environment does not need to be considered.

However, in Table 3.4.2-1, the piping, piping components, piping elements, and tanks are identified as a carbon or low alloy steel in an environment of raw water.

Request Provide additional information on why Section 3.4.2.2.3 of the LRA indicates that there is no steel piping exposed to raw water, whereas Table 3.4.2-1 indicates the opposite.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.4.2.3-1

Background

LRA Table 3.4.2-3 contains items which address hardening and loss of strength due to elastomer/plastic degradation of fiberglass or fiber reinforced plastic piping, piping components, piping elements and tanks exposed to outdoor air. The applicant proposes that neither the component nor the material and environment combination is evaluated in the GALL Report (Note J). The applicant acknowledges that aging may occur for this combination of materials and environments and proposes to manage it through the use of its AMP "External Surfaces Monitoring" (LRA B.2.22).

Issue In its review of these items the staff noted that the external surfaces monitoring program contained in the GALL Report is a visual inspection program and that its scope is limited to steel surfaces. The staff also noted that the applicant has committed to enhance its external surfaces monitoring program to include components constructed from materials other than steel and to detect additional aging effects associated with those materials, including hardening and loss of strength. The staff further noted that the applicant has not explicitly committed to enhancing its program to include inspection techniques other than visual inspection. Lastly, the staff noted that hardening and loss of strength are not directly detected by visual examinations and that visual changes in elastomers and plastics may, but need not, occur in conjunction with hardening and loss of strength.

Request Justify how the proposed AMP will detect changes in hardness and strength of the plastic components under consideration or propose an AMP which will directly measure these changes.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.4.2.4-1

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Background===

The GALL Report indicated in Table 4, line Item 16, that stainless steel piping, piping components, piping elements, tanks, and heat exchanger components exposed to treated water may undergo loss of material due to pitting and crevice corrosion. The GALL Report further suggests that this degradation mechanism can be managed by the Water Chemistry and OTI programs.

Issue In the LRA, Table 3.4.2-4, it is indicated that the loss of material due to pitting and crevice corrosion of stainless steel piping, piping components, piping elements, tanks, and containment isolation piping and components exposed to treated water is not evaluated in the GALL Report. There are other similar components found in the LRA Table 3.4.2-7. The applicant indicates that these aging effects will be managed by the Internal Surfaces in Miscellaneous Piping and Ducting Components program. It is not clear to the staff why the proposed program is adequate to manage this particular aging management concern.

Request Provide additional information indicating why the Internal Surfaces in Miscellaneous Piping and Ducting Components is adequate to manage loss of material due to pitting and crevice corrosion for stainless steel components exposed to treated water.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.5.2.2-1

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Background===

In the GALL Report, Table 5 indicates that fuel pool liners can undergo SCC, pitting, and crevice corrosion. The AMP suggested in the GALL Report to manage these degradation modes are the Water Chemistry Program and the Monitoring of Spent Fuel Pool Water Level and Level of Fluid in the Leak Chase Channel Program.

Issue In the LRA two components subjected to spent fuel pool environment are the spent fuel pool liner and expansion bellows. The fuel pool liner in Table 3.5.2-1 and expansion bellows in Table 3.5.2-2 indicate that the Water Chemistry Program is enough to manage the aging effects of cracking and loss of materials.

Request Provide additional information on why the monitoring of spent fuel pool level and monitoring leakage from the leak chase channels is not included for the fuel pool liner and expansion bellows in contact with treated water.

Discussion

The applicant stated that the spent fuel pool level and leak chase channels are continuously monitored. Therefore, this question is withdrawn and will not be sent as a formal RAI.

D-RAI 3.5.2.2.1.7-1

Background

The GALL Report, Table 5, indicates that SCC of stainless steel penetration sleeves can occur in all types of PWR containments. In addition, SCC may cause aging effects, particularly if the stainless steel material is not shielded from the corrosive environment. SCC of stainless steels is known to occur in air containing atmospheric chlorides. Locations near the coast will have much higher concentration of chloride aerosol particles and have a higher susceptibility for SCC. Issue LRA Section 3.5.2.2.1.7 indicates that SCC is not applicable for penetration sleeves and dissimilar metal welds because these materials are in the air-indoor environment and not subject to an aggressive chemical environment. It is not clear to the staff how the air-indoor environment is controlled in order to eliminate the chloride aerosols that are prevalent on the coast lines.

Request Provide additional information on why atmospheric chloride induced SCC does not need to be evaluated for penetration sleeves and dissimilar metal welds in an indoor air environment and why no AMP has been assigned to these components.

Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.5.2.3-1

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Background===

LRA Table 3.5.2-6 contains items addressing melamine (Willtec) foam exposed to indoor air. The applicant proposes that neither the component nor the material and environment combination is evaluated in the GALL Report (Note J). The applicant further proposes that this combination of environment and material is not subject to aging and that no AMP is required.

Issue In its review of these items, the staff noted that, at least one manufacturer of melamine foam acoustic insulation panels list the life expectancy of these panels as 12-14 years under normal conditions and 7-11 years under high humidity conditions.

Request Based on the advertised life expectancy of melamine foam, please justify the position that this material is not subject to aging in indoor air.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI B.2.23

Background

The LRA Section (AMP) B.2.23, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components," commits to consistency with the GALL Report AMP XI.M33, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components," with no exceptions or enhancements. GALL Report AMP XI.M.38 is applicable to steel (carbon steel) components to detect loss of material with the use of visual inspections.

Issue The applicant's LRA program basis documents and AMR line items stated that the LRA AMP B2.23 is relied upon to manage materials beyond the scope of the GALL Report AMP XI.M33, including stainless steel, aluminum and aluminum alloys, copper and copper alloys, and titanium in a variety of environments. The CR-3 LRA had also expanded the scope of aging effects managed by this AMP to include cracking due to SCC. The proposed expansion of AMP B2.23 is beyond the scope of GALL AMP XI.M38, which was meant for steel components and loss of material. The staff is not convinced that the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program using visual inspection provides adequate aging management for detecting tight stress corrosion cracks.

Request 1. Provide justification for not considering the expansion in the scope of material to include additional metallic components and in the scope of aging effects to include cracking due to SCC should not be considered enhancements to GALL AMP XI.M38. 2. Provide justification that the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program is adequate for managing the aging effect of cracking due to SCC in the identified stainless steel, aluminum, aluminum alloys, copper, copper alloys, and titanium components. 3. Identify and justify the inspection techniques used by this program that will be capable of detecting SCC for the materials (and the components) added to the scope of this program or provide an appropriate program to manage cracking due to SCC for these components.

Discussion

The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

Crystal River Unit 3 Nuclear Generating Plant cc: Mr. R. Alexander Glenn Associate General Counsel (MAC-BT15A) Florida Power Corporation P.O. Box 14042 St. Petersburg, FL 33733-4042

Mr. James W. Holt Plant General Manager Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, FL 34428-6708 Mr. William A. Passetti, Chief Department of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin #C21 Tallahassee, FL 32399-1741

Attorney General Department of Legal Affairs The Capitol Tallahassee, FL 32304

Mr. Ruben D. Almaguer, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, FL 32399-2100

Chairman Board of County Commissioners Citrus County 110 North Apopka Avenue Inverness, FL 34450-4245 Mr. Stephen J. Cahill Engineering Manager Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, FL 34428-6708

Mr. Daniel R. Westcott Supervisor, Licensing & Regulatory Programs Crystal River Nuclear Plant 15760 W. Power Line Street Crystal River, FL 34428-6708

Senior Resident Inspector Crystal River Unit 3 U.S. Nuclear Regulatory Commission 6745 N. Tallahassee Road Crystal River, FL 34428

Mr. Jack E. Huegel Manager, Nuclear Oversight Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, FL 34428-6708

Mr. David T. Conley Associate General Counsel II - Legal Dept. Progress Energy Service Company, LLC P.O. Box 1551 Raleigh, NC 27602-1551 Mr. Michael P. Heath Supervisor, License Renewal Progress Energy 8470 River Road, 2E Southport, NC 28461 Mr. Mark Rigsby Manager, Support Services - Nuclear Crystal River Nuclear Plant (SA2C) 15760 W. Power Line Street Crystal River, FL 34428-6708 Mr. Robert J. Duncan II Vice President, Nuclear Operations Progress Energy P.O. Box 1551 Raleigh, NC 27602-1551 Crystal River Unit 3 Nuclear Generating Plant cc: Mr. Brian C. McCabe Manager, Nuclear Regulatory Affairs Progress Energy P.O. Box 1551 Raleigh, NC 27602-1551

Mr. Jon Franke, Vice President Crystal River Nuclear Plant (NA1B) ATTN: Supervisor, Licensing & Regulatory Programs 15760 W. Power Line Street Crystal River, FL 34428-6708