ML11132A118

Bellefonte, Units 1 and 2 - Proposed Regulatory Framework for the Possible Completion of Construction Activities

ML11132A118
Person / Time
Site:	Browns Ferry, Watts Bar, Bellefonte
Issue date:	05/05/2011
From:	Hruby R Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML11132A118 (168)

Text

Tennessee Valley Authority, 1101 Market Street, LP 5A, Chattanooga, Tennessee 37402-2801 May 5, 2011 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Bellefonte Nuclear Plant, Units 1 and 2 Construction Permit Nos. CPPR-122 and CPPR-123 NRC Docket Nos. 50-438 and 50-439

Subject:

BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - PROPOSED REGULATORY FRAMEWORK FOR THE POSSIBLE COMPLETION OF CONSTRUCTION ACTIVITIES

References:

1. Letter from TVA to NRC, "Bellefonte Nuclear Plant (BLN) Units 1 (CPPR-1 22) AND 2 (CPPR-123) - Transition to Deferred Status,"

dated August 10, 2009 [ML092230730].

2. Letter from TVA to NRC, "Bellefonte Nuclear Plant (BLN) Units 1 (CPPR-1 22) and 2 (CPPR-1 23) - Key Regulatory Assumptions for the Possible Completion of Construction Activities," dated April 9, 2010

[ML101050030].

3. Letter from NRC to WVA, "Bellefonte Nuclear Plant, Units 1 and 2 -

Regarding Key Assumptions for Reactivation," dated August 4, 2010

[ML101880337].

4. Letter from TVA to NRC, "Bellefonte Nuclear Plant (BLN) Units 1 (CPPR-1 22) and 2 (CPPR-1 23) - Revision to Response to Regulatory Issue Summary 2010-10," dated March 1,2011.

In TVA's letter to the NRC requesting transition to deferred status dated August 10, 2009 (Reference 1), WVA communicated its intent to develop a detailed Regulatory Framework for Bellefonte (BLN) Units 1 & 2. The BLN Regulatory Framework establishes the proposed BLN licensing basis relative to conformance with NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition" (SRP) and disposition of NRC generic communications and unresolved safety issues (USIs). Providing the BLN 1 & 2 Regulatory Framework for NRC staff review is consistent with the licensing process used to establish the Regulatory Framework for the Browns Ferry Unit 1 and the current Watts Bar Unit 2 construction completion projects.

U.S. Nuclear Regulatory Commission Page 2 May 5, 2011 In TVA's letter to the NRC dated April 9, 2010 (Reference 2), TVA described the key assumptions for the possible completion of construction activities that would guide the development of the BLN 1 & 2 Regulatory Framework. The proposed BLN 1 & 2 Regulatory Framework was developed based on the key assumption that TVA would perform a case-by-case review of new regulations and guidance consistent with Section III.A.5 of the NRC Policy Statement on Deferred Plants, Generic Letter 87-15. As part of this review, TVA would continue to look for opportunities to improve plant systems and design. TVA also assumed that the NRC would apply licensing standards in the same manner as for a plant under construction, taking into account the dates of the existing Construction Permit application (June, 1973) and Operating License application (February, 1978), as addressed under the Policy Statement on Deferred Plants. The NRC provided a response to TVA's key regulatory assumptions by letter dated August 4, 2010 (Reference 3). Therefore, TVA's key regulatory assumptions and subsequent NRC feedback form the basis for determining the appropriate requirements for BLN.

The purpose of this letter is to describe the approach TVA has taken to establish the proposed Regulatory Framework for the possible completion of BLN 1 & 2 and provide the results of TVA's review for NRC staff review. Enclosure 1, "TVA's Proposed BLN Regulatory Framework," provides the tables that are described in this letter. These tables collectively establish the proposed BLN Regulatory Framework.

The scope of TVA's review to establish the BLN Regulatory Framework included an evaluation of BLN conformance with the SRP, applicability and status of NRC Generic Communications, and applicability and status of NRC Unresolved Safety Issues (USIs).

The development and submittal of the BLN Regulatory Framework is consistent with the provisions of the Policy Statement on Deferred Plants, Sections IIl.A.6.d and IIl.A.6.e.

TVA is adopting, when feasible, the acceptance criteria contained in the 2007 SRP as the licensing basis for BLN 1 & 2. When full adoption of the acceptance criteria in the 2007 SRP is not feasible, TVA will describe the deviation from the 2007 SRP and provide a proposed alternative that provides an acceptable method of compliance with the NRC rules or regulations that underlie the corresponding SRP acceptance criteria.

TVA's comprehensive review of the 2007 SRP consisted of the following major elements:

a. TVA performed a section by section comparison of requirements', guidance, and applicable industry codes and standards as specified in Section II, "Acceptance Criteria," of the 1981 and 2007 versions of each SRP section and an evaluation 1 The requirements that must be met before a plant can be licensed are defined in NRC regulations.

The NRC staff has prepared a number of guidance documents, such as the Standard Review Plan and regulatory guides, that are acceptable to the NRC staff for meeting various requirements in the regulations. Except for a few regulatory guides that are specifically referenced in a regulation, these guidance documents are not requirements. Neither the SRP nor the Regulatory Guides reviewed in this analysis is a substitute for the NRC's regulations and compliance is not required.

U.S. Nuclear Regulatory Commission Page 3 May 5, 2011 of the differences. For some SRP chapters, regulatory requirements and acceptance criteria are also contained in tables (e.g., Table 7-1). These requirements and acceptance criteria were also included and evaluated in the review.

b. TVA identified key licensing issues and their current status. These issues may be unresolved due to factors such as regulatory history, length of the BLN 1 & 2 licensing process, unique B&W issues, or other industry or BLN 1 & 2 specific issues. The issues include those identified in the TVA position papers submitted in the early 1990's and evaluated by NRC during that time period. The issues are identified in the discussion regarding related SRP sections and the key requirements from these sections have been linked to the issues.

The results of TVA's evaluation of BLN 1 & 2 conformance with the SRP are documented in Table 1 of Enclosure 1, "BLN Conformance with the NRC Standard Review Plan," and include the SRP acceptance criteria, outstanding licensing issues, and additional information that will establish the licensing basis for the potential completion of BLN 1 & 2 relative to the SRP.

Table 1 contains seven columns. Column 1 identifies the Final Safety Analysis Report (FSAR) section number and title, as provided in RG 1.70 (Rev. 3), "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition)."

Discussion with NRC staff indicated that including this column would benefit the staff in their review.

Column 2 identifies the number and title of each SRP section. The SRP sections are cross-referenced with the appropriate FSAR section. The SRP section numbers and titles generally align with the format provided in RG 1.70, although there are some minor differences. For example, section 2.4.12 of RG 1.70 addresses "Dispersion, Dilution and Travel Times of Accidental Releases of Liquid Effluents in Surface Waters," whereas the corresponding section of the SRP is numbered 2.4.13 and is titled "Accidental Releases of Radioactive Liquid Effluents in Ground and Surface Waters."

Column 3 identifies the revision of the SRP acceptance criteria that will comprise the BLN licensing basis for the associated SRP section. An asterisk in column 3 is used to denote instances where full adoption of an acceptance criterion, referenced revision of regulatory guide, code or standard is not feasible. In these instances, an explanation of the adopted approach is included in column 7, "Additional Information."

Column 4 includes a list of the NRC regulations and guidance identified in the acceptance criteria within the corresponding section of the adopted SRP revision.

Column 5 includes a summary of the key issues related to each SRP section as described above.

U.S. Nuclear Regulatory Commission Page 4 May 5, 2011 Column 6 includes a current status of each key issue as determined by review of docketed correspondence, new or imminent regulations, guidance, codes and standards and BLN 1 & 2 project plans.

Column 7 includes additional information pertaining to the associated SRP section or key issues, including NRC Generic Communications containing subject matter most relevant to the section and any full or partial exceptions taken to the referenced SRP acceptance criteria, referenced regulation or guidance.

As previously noted, the review of the SRP included regulatory guides that provide applicable guidance for each of the SRP sections, with the appropriate regulatory guides listed for each section. TVA intends to follow the guidance of those regulatory guides listed in the table, including the referenced revisions. When no regulatory guide revision is specified in Column 4 of Table 1, the applicable revision is noted in Column 7 with an explanation. Although TVA has identified known examples of such cases in Table 1, the potential exists for identification of further instances as engineering activities progress.

Additional instances will be included in updates to Table 1.

TVA also reviewed related industry codes and standards, such as the IEEE Standards and the ASME Code, using logic similar to that described above for regulatory guides.

For the IEEE Standards, TVA will distinguish between previously installed (legacy) equipment and the future procurement and installation of new equipment. For example, as allowed by 10 CFR 50.55a(h), IEEE Std. 279 will be used for legacy electrical equipment, and IEEE Std. 603 will be used for new equipment and major upgrades of equipment such as the digital control system upgrades.

For ASME Code-related activities and SSCs, the Code of record continues to apply for previously designed, procured, constructed and/or installed SSCs. For future ASME Code-related activities, such as for replacement steam generators, TVA will adopt the current Code when feasible. In future ASME Code-related activities, TVA will ensure consistency between design and analysis techniques, materials and installation requirements with respect to ASME Code requirements. When specific ASME Code requirements are identified in detail in the SRP acceptance criteria, they are identified in Table 1. The applicable Code will be included in BLN design basis documents (DBDs).

In addition to TVA's review of BLN 1 & 2 conformance with the SRP, TVA has reviewed NRC generic communications that may require responses for BLN 1 & 2. These include generic letters, bulletins, NUREG-0737 Three Mile Island (TMI) action items, and circulars. Table 2, "Generic Communications - Applicability and Status for BLN Units 1

& 2," of Enclosure 1 provides a status of generic communications with respect to BLN 1

& 2. This table includes NRC generic communications, their applicability to BLN 1 & 2, status, and proposed actions. An asterisk following a generic communication number is used to denote instances where the generic communication is included in the 2007 SRP and therefore will be addressed in the Operating License application update process.

The basis for determination of each item's status is included in the "Action to be

U.S. Nuclear Regulatory Commission Page 5 May 5, 2011 Completed or Justification for Closure" column. Items that TVA believes the required actions have been completed are identified as "Completed." If previous NRC communications indicate agreement with this status, the item is identified as "Closed."

Additionally, Table 2 identifies initial actions currently planned by TVA. TVA will maintain Table 2 to provide the NRC with an updated status of the generic communications.

Generic letters or bulletins that are issued between the date of this letter and the submittal of the Construction Reactivation letter will be added to this list. Once the Construction Reactivation letter is submitted, future generic communications will be responded to in accordance with the schedule of the individual generic communication and added to Table 2.

Similar to TVA's review of NRC generic communications, TVA also reviewed NRC Unresolved Safety Issues (USI's) for applicability and status at BLN 1 & 2. Table 3, "Unresolved Safety Issues - Applicability and Status for Bellefonte Units 1 & 2," of provides the same information for each USI as is provided for generic communications in Table 2.

This initial submittal of the BLN 1 & 2 Regulatory Framework is based on information available as of the date of this letter. The potential for changes to this framework based on evolving regulatory issues and emergent information during design completion and project planning exists. Should TVA determine, based on further review or emerging issues, that a different approach or additional action is appropriate, TVA will submit such changes to the NRC for review. These changes will be provided in periodic updates to the BLN 1 & 2 Regulatory Framework tables as actions are completed.

TVA plans early engagement with the NRC staff for certain key licensing issues to ensure that TVA's approach is acceptable. This is consistent with the approach outlined in TVA's letter to the NRC dated March 1, 2011 (Reference 4) voluntarily responding to Regulatory Issue Summary 2010-10, "Process For Scheduling Acceptance Reviews of New Reactor Licensing Applications and Process for Determining Budget Needs for Fiscal Year 2013." of this letter includes the tables referenced in this letter that collectively provide the proposed BLN Regulatory Framework. provides a list of TVA commitments made in this letter.

U.S. Nuclear Regulatory Commission Page 6 May 5, 2011 If you have any questions concerning this matter, please call Zackary W. Rad at (256) 574-8265.

Sincerely, Raymond A. Hruby, Jr.

General Manager Bellefonte Project Enclosure(s):

1. TVA's Proposed BLN Regulatory Framework

2.

List of TVA Commitments cc: See page 7

U.S. Nuclear Regulatory Commission Page 7 May 5, 2011 cc (w/Enclosures):

Eric Leeds, Director U.S. Nuclear Regulatory Commission One White Flint North, 13H16M 11555 Rockville Pike Rockville, Maryland 20852-2738 Stephen J. Campbell U.S. Nuclear Regulatory Commission One White Flint North, 8H4A 11555 Rockville Pike Rockville, Maryland 20852-2738 John Lamb U.S. Nuclear Regulatory Commission One White Flint North, 8H21 11555 Rockville Pike Rockville, Maryland 20852-2738 Lakshminarasimh Raghavan U.S. Nuclear Regulatory Commission One White Flint North, 8H4A 11555 Rockville Pike Rockville, Maryland 20852-2738 Victor McCree, Regional Administrator U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Avenue N.E.,

Suite 1200 Atlanta, GA 30303 Charles Casto, Deputy Regional Administrator for Construction U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Avenue N.E.,

Suite 1200 Atlanta, GA 30303 Robert Haag U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Avenue N.E., Suite 1200 Atlanta, GA 30303 Patrick Milano U.S. Nuclear Regulatory Commission One White Flint North, 8H21 11555 Rockville Pike Rockville, Maryland 20852-2738 TVA Letter dated May 5, 2011 TVA's Proposed BLN Regulatory Framework Table 1 - BLN Conformance with the NRC Standard Review Plan Table 2 - Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Table 3 - Unresolved Safety Issues - Applicability and Status for Bellefonte Units 1 & 2 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

A RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s)

StatusAdditional Information Chapter 1 - Introduction and General Description of Plant 1 Introduction and General 1

Description of Plant None 1.0 Introduction and 2007 10 CFR 50.33,.34 None NA This section is a general overview of the FSAR.

Interfaces 1.1 Introduction None 1.2 General Plant None Description 1.3 Comparison Tables None 1.3.1 Comparisons with None Similar Facility Designs 1.3.2 Comparison of Final None and Preliminary Information 1.4 Identification of Agents None and Contractors 1.5 Requirements for None Further Technical Information 1.6 Material Incorporated None by Reference 1.7 Drawings and Other None Detailed Information 1.7.1 Electrical, None Instrumentation, and Control Drawings 1.7.2 Piping and None Instrumentation Diagrams Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 1 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG R000sP SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 0FSAR)

Section Section Revision Acceptance Criteria Status 1.7.3 Other Detailed None Information 1.8 Conformance to NRC None Regulatory Guides 1.9 Standard Designs None 1.9.1 Interfaces None 1.9.2 Exceptions None Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 2 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

RG 1.70 (FSAR) Section Section Revision AcceptanceKey Issue(s)

Additional Information Chapter 2 - Site Characteristics 2 Site Characteristics 2.0 Site Characteristics NA None NA SRP Section 2.0 is not applicable to CP & OL applications and Site Parameters submitted under 10CFR50.

2.1 Geography and None None None NA Demography 2.1.1 Site Location and 2.1.1 10 CFR 50.34(a)(1)

None NA Although the BLN site was initially approved in compliance Description 10CFR 100, Subpart B with the reactor site criteria in 10 CFR 100 Subpart A (100.10 &.11), providing the NRC assurance of BLN 2007 compliance with the reactor site criteria in 10 CFR 100 Subpart B (which includes 100.20,.21,.23 & Appendix A) is consistent with TVA's decision to comply with 10 CFR 50 App S (see sect. 3.7.1).

2.1.2 Exclusion Area 2.1.2 10 CFR 100, Subpart B None NA Authority and Control 2007 10 CFR 50.33,.34(a)(1) 2.1.3 Population 2.1.3 10 CFR 50.34(a)(1),

None NA Distrbution 2007 10 CFR 100, Subpart B RG 1.70 R3, 4.7 R2 Positions C.3

& C.4 2.2 Nearby Industrial, None Transportation, and Military Facilities 2.2.1 Location and Routes 2.2.1 - 2.2.2 Identification 10 CFR 50.34(a)(1)(i)

Potential Aircraft See Section 2.2.2 Descriptions of Potential Hazards in 2007 10 CFR 100, Subpart B Hazard 3.5.1.6.

Site Vicinity RGs 1.70 R3, 1.91 R1 2.2.3 Evaluation of 2.2.3 10 CFR 100, Subpart B Potential Aircraft See Section Potential Acciden 1_2007 11CFR 50.34(a)(1)(i)

Hazard 3.5.1.6.

Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 3 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section

[

s Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria ey Issue(s)

Status 2.3 Meteorology None 2.3.1 Regional Climatology 2.3.1 10 CFR 50 App. A GDC 2, 4 None NA 2007 10 CFR 100, Subpart B RGs 1.27 R1, 1.76 R1 2.3.2 Local Meteorology 2.3.2 10 CFR 50 App. A GDC 2 None NA 2007 10 CFR 100, Subpart B RGs 1.23 R1, 1.70 R3 2.3.3 Onsite Meteorological 2.3.3 10 CFR 50 App. A GDC 19, App. I, None NA Measurements Program

.47(b)(4,8,9), App. E Sect. IV.E.2 2007 10 CFR 100, Subpart B 10 CFR 20 Subpart D RG 1.23 R1 2.3.4 Short-Term Diffusion 2.3.4 Short-term 10 CFR 50 App. A GDC 19 None NA Estimates Atmospheric Dispersion 10 CFR 50.34(a)(1)(ii)(d)

Estimates for Accident 2007 10 CFR 100, Subpart B Releases RGs 1.23 R1, 1.70 R3, 1.78 R1, 1.145 R1, 1.194 RO 2.3.5 Long-Term Diffusion 2.3.5 Long-Term 10 CFR 50,.34a, App. I None NA Estimates Atmospheric Dispersion 10 CFR 20 Subpart D Estimates for Routine 2007 10 CFR 100, Subpart B Releases RGs 1.23 R1, 1.70 R3, 1.109 R1, 1.112 R1 2.3.6 BOP Interface None 2.4 Hydrologic Engineering None Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 4 of 88 Revision 0 TVA Letter dated May 5, 2011 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision AcceptanceCriteriaoKayInssueaoStatus 2.4.1 Hydrologic 2.4.1 10 CFR 50 App. A GDC 2 None NA Description 2007 10 CFR 100, Subpart B RGs 1.27 R1, 1.29 R4, 1.59 R2, 1.102 R1 2.4.2 Floods 2.4.2 10 CFR 50 App. A GDC 2 Hydrology Project Open BLN 3&4 PMF and seismic dam failure submittals have 7 10 CFR 100, Subpart B been sent to NRC and are awaiting technical review.

2007 10CR10SuprB RGs 1.27 R1, 1.29 R4, 1.59 R2, GL 89-22, Potential for Increased Roof Load Due to 1.102 R1 Changes in Maximum Precipitation.

2.4.3 Probable Maximum 2.4.3 10 CFR 50 App. A GDC 2 See 2.4.2.

Open Flood (PMF) on Streams 10 CFR 100, Subpart B and Rivers 2007 RGs 1.27 R1, 1.29 R4, 1.59 R2, 1.102 R1 2.4.4 Potential Dam 2.4.4 Potential Dam 10 CFR 50 App. A GDC 2, 44 See 2.4.2.

Open Failures, Seismically Failures 10CFR100, Subpart B Induced 2007 RGs 1.27 R1, 1.29 R4, 1.59 R2, 1.102 R1 2.4.5 Probable Maximum 2.4.5 10 CFR 50 App. A GDC 2,44 See 2.4.2.

Open Surge and Seiche Flooding 2007 10 CFR 100, Subpart B RGs 1.27 R1, 1.29 R4, 1.59 R2, 1.102 R1 2.4.6 Probable Maximum 2.4.6 Probable Maximum 10 CFR 50 App. A GDC 2 None NA Tsunami Flooding Tsunami Hazards 2007 10 CFR 100, Subpart B RGs 1.27 R1, 1.29 R4, 1.59 R2, 1.102 R1 2.4.7 Ice Effects 2.4.7 10 CFR 100, Subpart B None NA 2007 10 CFR 50 App. A GDC 2 RGs 1.27 R1, 1.29 R4, 1.59 R2, 1.102 R1 Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 5 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) I SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria KeyIsse(

Status 2.4.8 Cooling Water Canals 2.4.8 10 CFR 50 App. A GDC 1,2,44 None NA and Reservoirs 2007 10 CFR 100, Subpart B RGs 1.27 R1, 1.29 R4, 1.59 R2, 1.102 R1, 1.125 R2 2.4.9 Channel Diversions 2.4.9 10 CFR 50 App. A GDC 1,2,44 None NA 2007 10 CFR 100, Subpart B RGs 1.27 R1, 1.29 R4, 1.59 R2, 1.102 Ri 2.4.10 Flooding Protection 2.4.10 10 CFR 50 App. A GDC 2,44 None NA Requirements 2007 10 CFR 100, Subpart B RGs 1.29 R4, 1.59 R2, 1.102 R1 2.4.11 Low Water 2.4.11 10 CFR 50 App. A GDC 2,44 None NA Considerations 2007 10 CFR 100, Subpart B RG 1.27 R1, 1.29 R4 2.4.12 Dispersion, Dilution, 2.4.13 Accidental 10 CFR 100, Subpart B None NA and Travel Times of Releases of Radioactive 10 CFR 50 App. A GDC 2 Accidental Releases of Liquid Effluents in Ground 2007 BTP 11-6 Liquid Effluents in Surface and Surface Waters RG 1.113 Ri Waters 2.4.13 Groundwater 2.4.12 Groundwater 10 CFR 50.55, 50.55a, None NA 10 CFR 50 App. A, GDC 2,4,5,44 10 CFR 100, Subpart B RG 1.27 R1 2.4.14 Technical 2.4.14 10 CFR 50.36 None NA Specification and 10 CFR 50 App. A GDC 2,44 Emergency Operation 2007.

10 CFR 100, Subpart B Requirements RGs 1.29 R4, 1.59 R2, 1.102 R1 2.5 Geology, Seismology, None and Geotechnical Engineering Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 6 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 2.5.1 Basic Geologic and 2.5.1 10 CFR 50 App. A GDC 2 Seismic Information 10CFR 100, Subpart B RGs 1.132 R2, 1.138 R2, 1.198 RO, 1.208 RO, 4.7 R2 2.5.2 Vibratory Ground 2.5.2 10 CFR 50 App. A, GDC 2 Use of new site Preparing NRC SER dated October 4, 1991 in response to position Motion 10 CFR 100, Subpart B specific spectra summary paper accepted ground response spectra anchored to an RGs 1.60 R1, 1.132 R2, 1.208 RO, consistent with discussion on acceleration of.18 g 4.7 R2 CEUS & ETSZ use of spectra and of criteria 2007 consistent with App. S to Part 50.

Resolution of this issue will address position paper on ground motion (TAC No. 79275) 2.5.3 Surface Faulting 2.5.3 10 CFR 50 App. A, GDC 2 None NA 0 10CFR 100, Subpart B RGs 1.132 R2, 1.198 RO, 1.208 RO, 4.7 R2 2.5.4 Stability of 2.5.4 10 CFR 50.55a, App. A GDC None NA Subsurface Materials and 1,2,44, App. B, App. S Foundations 2007 10 CFR 100, Subpart B RGs 1.27 R1, 1.28 R4, 1.132 R2, 1.138 R2, 1.198 RO 2.5.5 Stability of Slopes 2.5.5 10 CFR 50.55a, App. A, GDC None NA 1,2,44, App. B, App. S 2007 10 CFR 100, Subpart B RGs 1.27 R1, 1.28 R4, 1.132 R2, 1.138 R2, 1.198 RO Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 7 of 88 Revision 0 TVA Letter dated May 5, 2011 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 2.5.6 Embankments and None DamsI Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 8 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status Chapter 3 - Design of Structures, Components, Equipment, and Systems 3 Design of Structures, None Components, Equipment, and Systems 3.1 Conformance with NRC None General Design Criteria 3.2 Classification of None Structures, Components, and Systems 3.2.1 Seismic Classification 3.2.1 2007 10 CFR 50, App. A, GDCs 1,2,61, None NA For existing (legacy) equipment TVA will use RG 1.151 RO.

App B and App. S For newly procured/major modified equipment, TVA will 10 CFR 100, Subpart B use RG 1.151 Ri.

RGs 1.29 R4, 1.143 R2, 1.151, 1.189 R2 3.2.2 System Quality Group 3.2.2 2007 10 CFR 50, App. A, GDC 1, None NA Classifications 50.55a RG 1.26 R4 3.3 Wind and Tornado None Loadings 3.3.1 Wind Loadings 3.3.1 2007 10 CFR 50, App. A, GDC 2 None NA RG 1.76 R1 3.3.2 Tornado Loadings 3.3.2 Tomado Loads 2007 10 CFR 50, App. A, GDC 2 None NA 3.3.3 BOP Interface None 3.4 Water Level (Flood)

None Design 3.4.1 Flood Protection 3.4.1 Intemal Flood 2007 10 CFR 50, App. A, GDC 2, 4 None NA Protection for Onsite RGs 1.29 R4 Equipment Failures Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 9 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 3.4.2 Analytical and Test 3.4.2 Analysis Procedures 2007 10 CFR 50, App. A, GDC 2 None NA Procedures 3.4.3 NSSS Interface None 3.4.3 BOP Interface None 3.5 Missile Protection None 3.5.1 Missile Selection and None Description None 3.5.1.1 Internally 2007 10 CFR 50, App. A, GDC 4 None NA Generated Missiles RG 1.115 R1, 1.117 R1 (Outside Containment)

None 3.5.1.2 Internally 2007 10 CFR 50, App. A, GDC 4 None NA Generated Missiles (Inside Containment)

None 3.5.1.3 Turbine Missiles 2007 10 CFR 50, App. A,GDC 4 None NA 10 CFR 100, Subpart B RGs 1.115 R1, 1.117 R1 None 3.5.1.4 Missiles Generated 2007 10 CFR 50, App. A, GDCs 2 & 4 None NA by Tornadoes and RG 1.76 R1 Extreme Winds None 3.5.1.5 Site Proximity 2007 10 CFR 100, Subpart B None NA Missiles (Except Aircraft)

CFR 50, App. A, GDC 4 RG 1.91 R1 Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 10 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan I

NUREG 0800 (SRP)

Section SRP Revision SRP Section Acceptance Criteria Key Issue(s)

Key Issue(s)

Status Additional Information RG 1.70 (FSAR) Section None 3.5.1.6 Aircraft Hazards 2007 10 CFR 100, Subpart B For potential Preparing TVA will develop action plans for each requirement listed in 10 CFR 50, App. A, GDCs 3 & 4 aircraft accidents, summary 10 CFR 50.54(hh) and provide this plan to NRC.

RG 1.117 R1 BLN had CP discussion on issued prior to security which the effective date will include of the final rule 50.54(hh) for consideration requirements of aircraft impact.

related to Thus, the rule security.

does not apply to them. However, TVA will comply with the requirements of 10 CFR 50.54(hh).

3.5.2 Structures, Systems, 3.5.2 2007 10 CFR 50, App. A, GDCs 2 & 4 None NA and Components to be RGs 1.13 R2., 1.27 R1, 1.115 R1 Protected from Externally Generated Missiles 3.5.3 Barrier Design 3.5.3 2007 10 CFR 50, App. A, GDCs 2 & 4 None NA TVA will use ACI 318-71 Procedures RG 1.76 R1, 1.142 R2 3.5.4 NSSS Interface None 3.5.4 BOP Interface None 3.6 Protection Against None Dynamic Effects Associated with the Postulated Rupture of Piping Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 11 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 3.6.1 Postulated Piping 3.6.1 Plant Design for 2007 10 CFR 50, App. A, GDCs 2 & 4 None NA IEB 80-04, Analysis of a PWR Main Steam Line Rupture Failures in Fluid Systems Protection Against BTP 3-3 (replaces SPLB 3-1) with Continued Feedwater Addition.

Outside of Containment Postulated Piping Failures in Fluid Systems Outside Containment 3.6.2 Determination of 3.6.2 Determination of 2007 10 CFR 50, App. A, GDC 4 None NA Break Locations and Rupture Locations and BTP 3-4 Dynamic Effects Associated Dynamic Effects with the Postulated Rupture Associated with the of Piping Postulated Rupture of Piping None 3.6.3 Leak-Before-Break 2007 10 CFR 50, App. A, GDC 4 LBB is factored TVA is preparing Evaluation Procedures into assessments a summary of BLN capability discussion of use to withstand new of spectra and response spectra consideration of and use will LOCA loads.

require NRC acceptance and consideration of Alloy 600 concerns.

3.7 Seismic Design None 3.7.1 Seismic Input 3.7.1 Seismic Design 2007 10 CFR 100, Subpart B Licensing basis Resolution of this Analysis features and criteria required to successfully Parameters 10 CFR 50, App. A, GDC 2; and of position paper issue will address complete seismic analysis of BLN structures and App. S related to design issue regarding equipment include spatially incoherent ground motion, RGs 1.60 R1, 1.61 R1

& analysis, and seismic analysis equipment-structure interaction and potentially enriched consideration of of Category 1 spectra at lower frequencies.

high frequency structures (TAC content.

No. 79276).

WVA will apply site specific spectra consistent with CEUS &

ETSZ in determining final positions for piping and commodities to address open issues as a result of previously submitted position papers.

Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 12 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section 1

s Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance CrteriaKey Issues Status 3.7.2 Seismic System 3.7.2 2007 10 CFR 100, Subpart B Use of new site See 3.2.1 Analysis 10 CFR 50, App. A, GDC 2; and specific spectra TVA will review App. S consistent with position paper RGs 1.92 R2, 1.122 R1 ETSZ & licensing and NRC SER basis of position against current paper related to requirements to seismic determine interactions (TAC appropriate No. 79280) position.

3.7.3 Seismic Subsystem 3.7.3 2007 10 CFR 50, App. A, GDC 2, App. S Use of new site See 3.2.1 Analysis 10 CFR 100, Subpart B specific spectra TVA will review NUREG/CR-1061 consistent with position paper CEUS, ETSZ &

and NRC SER licensing, basis of against current position paper requirements to involving determine structural appropriate adequacy of position.

distributive systems (TAC No. 79278) 3.7.4 Seismic 3.7.4 2007 10 CFR 20 None NA Instrumentation 10 CFR 50 App S RGs 1.12 R2, 1.166 RO 3.7.5 NSSS Interface None 3.7.5 BOP Interface None 3.8 Design of Category I None Structures Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 13 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 3.8.1 Concrete 3.8.1 2007 10 CFR 50, AppA, GDCs 1, 2,4, None NA TVA will use ACI 318-71 and ASME Code of Record Containment 16, 50, Apps. B and J, 50.44, 50.55a, IEB 80-24, Prevention of Damage Due to Water Leakage RGs 1.7 R3, 1.35 R3, 1.35.1 R0, Inside Containment 1.90 R1, 1.91 R1, 1.107 R1, 1.115 R1, 1.136 R3 3.8.2 Steel Containment 3.8.2 2007 10 CFR 50, App A, GDCs 1, 2, 4, None NA TVA will use ACI 318-71 and ASME Code of Record.

16, 50, Apps. B and J, 50.44, Revision of RG 1.84 will be consistent with requests to use 50.55a, Code Cases.

RGs 1.7 R3, 1.57 R1, 1.84,1.193 R3 3.8.3 Concrete and Steel 3.8.3 2007 10 CFR 50, App. A, GDCs 1, 2,4, None NA See 3.8.1 Internal Structures of Steel 16, 50, App B, 50.55a IEB 80-08, Examination of Containment Liner Penetration or Concrete Containments RGs 1.57 R1, 1.69 R1, 1.136 R3, Welds 1.142 R2, 1.143 R2, 1.160 R2, 1.199 RO 3.8.4 Other Seismic 3.8.4 2007 10 CFR 50, App A,GDCs 1,2, 4, 5, None NA See 3.8.1 Category I Structures App B,.55a IEB 80-11, Masonry Wall Design RGs 1.60 R1, 1.61 R1, 1.69 R1, 1.91 R1, 1.92 R2, 1.115 Ri, 1.127 R1, 1.142 R2, 1.143 R2, 1.160 R2, 1.199 RO 3.8.5 Foundations 3.8.5 2007 10 CFR 50, App A, GDCs 1, 2, 4, None NA TVA will use ACI 318-71 5,.55a,.65 RGs 1.127 R1, 1.142 R2, 1.160 R2 3.8.6 NSSS Interface None 3.8.6 BOP Interface None 3.9 Mechanical Systems None and ComponentsI Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 14 of 88 Revision 0 TVA Letter dated May 5, 2011 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRPP Section Key Key Issue(s)

Additional Information RG 1.70 (FSAR) Section NRC00 S

R Section Rvso e Issue(s)

Adtoa nomto Section R

on Acceptance Criteria Status 3.9.1 Special Topics for 3.9.1 2007 10 CFR 50, App. A, GDCs 1, 2, 14, None NA Mechanical Components 15, App. B, App. S 10 CFR 100, Subpart B 3.9.2 Dynamic Testing and 3.9.2 Dynamic Testing and 2007 10 CFR 50, App A, GDCs 1, 2, Qualification of TVA is Revision of RG 1.84 will be consistent with requests to use Analysis Analysis of Systems, 4,14, 15, App. B & App. S,.55a components for considering Code Cases.

Structures, and RGs 1.20 R3, 1.61 R1, 1.68 R3, high frequency several testing Components 1.84, 1.92 R2 motion options and mitigating devices 3.9.3 ASME Code Class 1, 3.9.3 2007*

10 CFR 50, App. A, GDCs 1,2, 4, None NA TVA will not adopt the elements of Appendix A to this 2, and 3 Components, 14,15, App S, 55a section related to environmentally assisted fatigue.

Component Supports, and RGs 1.124, 1.130 TVA will use Code of Record and applicable code cases for Core Support Structures existing (legacy) equipment, and current code, with applicable code cases, for newly procured equipment.

For existing (legacy) equipment, TVA will use the following:

RGs 1.124 R1, 1.130 R1 For newly procured/major modified equipment, TVA will use the following: RGs 1.124 R2, 1.130 R2 IEB 74-03, Failure of Structural or Seismic Support Bolts on Class I Components IEB 79-13, Cracking in Feedwater System Piping IEB 80-21, Valve Yokes Supplied by Malcolm Foundry Co IEB 82-02, Degradation of Threaded Fasteners in the Reactor Coolant Pressure Boundary of PWR Plants IEB 83-05, ASME Nuclear Code Pumps and Spare Parts Manufactured by Hayward Tyler Pump Co IEB 88-08, Thermal Stresses in Piping Connected to the Reactor Coolant System IEB 88-11, Pressurizer Surge Line Thermal Stratification GL 85-20, Resolution of Generic Issue 69, High Pressure Injection/Make-up Nozzle Cracking Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 15 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)Ke sus)AdtoaInrmin RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s)

Status NUAc00cSR)

SP R epac rteion

[ e Ssaues)AdtoaInoatn 3.9.4 Control Rod Drive 3.9.4 2007 10 CFR 50, App A, GDCs 1,2,14, None NA Systems 26, 27, 29,.55a RG 1.26 R4 3.9.5 Reactor Pressure 3.9.5 2007 10 CFR 50.55a, 10 CFR 50, App None NA For existing (legacy) equipment, TVA will use RG 1.20 R2.

Vessel Internals A, GDCs 1, 2, 4, 10,.55a For newly procured/major modified equipment, WVA will RG 1.20 use RG 1.20 R3.

3.9.6 Inservice Testing of 3.9.6 Functional Design, 2007 10 CFR 50.55a (including None NA IEB 74-01, Valve Deficiencies Pumps and Valves Qualification, and 50.55a(b)-(g)), 10 CFR 50, App A, IEB 75-03, Incorrect Lower Disc Spring and Clearance Inservice Testing GDCs 1,2, 4, 14, 15, 37, 40, 43, Dimension in Series 8300 and 8302 ASCO Solenoid Programs for Pumps, 46, 54, App. B Valves Valves, and Dynamic RGs 1.174 R1, 1.175 RO, 1.192 RO IEB 76-06, Diaphragm Failures in Air Operated Auxiliary Restraints Actuators for Safety/Relief Valves IEB 79-15, Deep Draft Pump Deficiencies IEB 80-23, Failures of Solenoid Valves Manufactured by Valcor Eng. Corp IEB 81-02 & S1, Failure of Gate Type Valves to Close Against Differential Pressure IEB 85-03, Motor Operated Valve Common Mode Failures During Plant Transients due to improper Switch Settings GL 80-14, LWR Primary Coolant System Pressure Isolation Valves GL 89-04, Guidelines on Developing Acceptable Inservice Testing Programs GL 95-07, Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves 3.9.7 NSSS Interface 3.9.7 Risk-Informed 2007 10 CFR 50.55a, 50.59, and App. B None NA Inservice Testing RGs 1.174 R1, 1.175 RO Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 16 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status None 3.9.8 Risk-Informed 2007 10 CFR 50.55a and Appendix A None NA Inservice Inspection of RGs 1.174 R1, 1.178 RO Piping 3.10 Seismic Qualification 3.10 Seismic and Dynamic 2007 10 CFR 50, App. A, GDCs 1, 2, 4, Position paper on TVA will review TVA position will include approach to qualification of of Seismic Category I Qualification of Mechanical 14, 30, App. B & S seismic position paper equipment subjected to high frequency content.

Instrumentation and and Electrical Equipment 10 CFR 100, Subpart B qualification of and NRC SER Electrical Equipment RGs 1.61 R1, 1.92 R2, 1.97 R4, equipment (TAC against current 1.100 R3 No. 79279) requirements to determine appropriate position.

3.10.1 Seismic Qualification None Criteria 3.10.2 Methods and None Procedures for Qualifying Electrical Equipment and Instrumentation 3.10.3 Methods and None Procedures of Analysis or Testing of Supports of Electrical Equipment and Instrumentation 3.10.4 Operating License None Review 3.10.5 NSSS Interface None Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 17 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP SectionK Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 3.11 Environmental Design 3.11 Environmental 2007*

10 CFR 50.49, 50.65, 50.67, App EQ approach for TVA will provide For existing (legacy) equipment, WVA will use the following:

of Mechanical and Qualification of Mechanical A, GDCs 1, 2, 4, 23 and App. B completion of current position RGs 1.63 R2, 1.89 RO Electrical Equipment.

and Electrical Equipment RGs 1.40 RO, 1.63,1.73 RO, 1.89, BLN.

on licensing basis For newly procured/major modified equipment, TVA will 1.97 R4, 1.156 RO, 1.158 RO, of this issue (TAC use the following: RGs 1.63 R3, 1.89 R1, 1.180 R1 1.160 R2, 1.180,1.183 R0, No. 79273), and Equipment procured by TVA as of Aug. 31, 1991 will be NUREG588, 0737,.B.2 roa qualified to at least the standards of NUREG-0588, NURG-088,073, l.B.

"approach to EQ Category 11.

for BLN prior to construction Equipment procured after Aug. 31, 1991 will be qualified to reactivation, the standards of NUREG-0588, Category I unless "sound reasons to the contrary" (as defined in RG 1.89) exist.

Where "sound reasons to the contrary" exist, qualification will be at least to the standards of NUREG-0588, Category II.

IEB 77-07, Containment Electrical Penetration Assemblies at Nuclear Power Plants under Construction IEB 78-02, Terminal Block Qualification IEB 78-04, Environmental Qualification of Certain Stem Mounted Limit Switches Inside Reactor Containment IEB 79-01, Environmental Qualification of Class 1E Equipment.

TMI Action Item - ll.B.2, Plant shielding IEB 86-02, Static "0" Ring Differential Pressure Switches GL 81-05, Information Regarding EQ of Safety Related Electrical Equipment GL 82-09, EQ of Safety Related Electrical Equipment 3.11.1 Equipment None Identification and Environmental Conditions 3.11.2 Qualification Tests None and Analyses Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 18 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Ke Issue's)

Key Issue(s)

Additional Information Section Revision Acceptance Criteria Status 3.11.3 Qualification Test None Results 3.11.4 Loss of Ventilation None 3.11.5 Estimated Chemical None and Radiation Environment 3.11.6 NSSS Interface None None 3.12 ASME Code Class 1, 2007 10 CFR 50.55a, App A, GDCs 1, 2, Position paper on TVA will review TVA will use Code of Record. Revision of RG 1.84 will be 2, and 3 Piping Systems, 4, 14, 15 and App. S, structural position paper consistent with requests to use Code Cases.

Piping Components and RG 1.84 analysis methods and NRC SER IEB 73-03, Defective Hydraulic Snubbers and Restraints.

their Associated Supports for piping, tubing against current IEB, 73-04, Defective Bergen-Patterson Hydraulic Shock and supports requirements to Absorbers.

(TAC No. 79277) determine appropriate IEB 75-05, Operability of Category I Hydraulic Shock and posiion.

Sway Suppressors.

position.

IEB 78-10, Bergen-Patterson Hydraulic Shock Suppressor Accumulator Spring Coils.

IEB 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts.

IEB 79-03, Longitudinal Weld Defects in ASME SA-312 Type 304 SS Pipe Spools Fabricated by Youngstown Welding & Engineering.

IEB 79-04, Incorrect Weights for Swing Check Valves Manufactured by Velan Engineering.

IEB 79-07, Seismic Stress Analysis of Safety-Related Piping.

IEB 79-14, Seismic Analysis for As-Built Safety-Related Piping Systems.

IEB 81-01, Surveillance of Mechanical Snubbers.

GL 78-02, Asymmetric Loads Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 19 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s)

Status None 3.13 Threaded Fasteners -

2007 10 CFR 50.55a, App A, GDCs 1,4, None NA TVA will use Code of Record for existing (legacy)

ASME Code Class 1, 2, 14, 30, 31, Apps. B, and & G equipment and current code for newly procured equipment.

and 3 RG 1.37 For existing (legacy) equipment, TVA will use RG 1.37 RO.

For newly procured/major modified equipment, TVA will use RG 1.37 R1.

IEB 89-02, Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or Valves of Similar Nature.

None BTP 3-1 Classification of NA-BWRs only Main Steam Components Other than the Reactor Coolant Pressure Boundary for BWR Plants None BTP 3-2 Classification of NA - BWRs only BWR/6 Main Steam and Feedwater Components Other than the Reactor Coolant Pressure Boundary I

None BTP 3-3 Protection 2007 10 CFR 50, App. A, GDCs 2 & 4 None NA Against Postulated Piping RGs 1.26 R4, 1.29 R4 Failures in Fluid Systems Outside Containment None BTP 3-4 Postulated 2007 10 CFR 50, App. A, GDC 4 None NA Rupture Locations in Fluid RG 1.11 Ri System Piping Inside and Outside Containment Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 20 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status Chapter 4 - Reactor 4 Reactor 4

4.1 Summary Description None 4.2 Fuel System Design 4.2 2007 10 CFR 50, App. A, GDCs 2, 10, 27 None NA 35, 50.34,.46,.67, 10 CFR 100, Subpart B N U REG-75/077, -0085, -0303, -

0308, -0401, -0418, -0609, -0630,

/CR-1018, /CR-1019, /CR-1020,

/CR-1380, -1883, & /CR-6534 RGs 1.4 R2, 1.25 RO, 1.60 R1, 1.77 RO, 1.126 R2, 1.157 RO, 1.183 RO, 1.196 R1 4.2.1 Design Bases None 4.2.2 Description and None Design Drawings 4.2.3 Design Evaluation None 4.2.4 Testing and None Inspection Plan 4.3 Nuclear Design 4.3 2007 10 CFR 50, App. A, GDCs 10, 11, None NA 12, 13, 20, 25, 26, 27, & 28 RGs 1.77 RO, 1.126 R2 4.3.1 Design Bases None 4.3.2 Description None 4.3.3 Analytical Methods None 4.3.4 Changes None Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 21 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section KeyKey Issue(s)

RG 1.70 (FSAR) Section Section Revision A

t Cria Status 4.4 Thermal and Hydraulic 4.4 2007 10 CFR 50, App. A, GDCs 10 & 12 None NA GL 81-21, Natural Circulation Cooldown Design NUREG-0737 & -1449 GL 93-04, Rod Control System Failure and Withdrawal of RGs 1.68 R3, 1.133 R1 Rod Control Cluster Assemblies, 10 CFR 50.54(f).

TMI Action Item - I1.K.2.13, Thermal Mechanical Report (Reactor Vessel) 4.4.1 Design Bases None 4.4.2 Description of None Thermal and Hydraulic Design of the Reactor Core 4.4.3 Description of the None Thermal and Hydraulic Design of the Reactor Coolant System 4.4.4 Evaluation None 4.4.5 Testing and None Verification 4.4.6 Instrumentation None Requirements 4.5 Reactor Materials None 4.5.1 Control Rod Drive 4.5.1 Control Rod Drive 2007 10 CFR 50, App. A, GDCs 1,14, &

None NA For existing (legacy) equipment, TVA will use RG 1.44 RO.

System Structural Materials Structural Materials 26, 50.55a For newly procured/major modified equipment, TVA will RG 1.44 use RG 1.44 RI.

GL 78-26, Excessive Control Rod Guide Tube Wear 4.5.2 Reactor Internals 4.5.2 Reactor Internal and 2007 10 CFR 50, App. A, GDC 1, None NA For existing (legacy) equipment, TVA will use RG 1.44 RO.

Materials Core Support Structure 50.55a For newly procured/major modified equipment, TVA will Materials NUREG-1823 use RG 1.44 RI.

RGs 1.31 R3, 1.44, 1.84 Revision of RG 1.84 will be consistent with requests to use Code Cases.

4.6 Functional Design of 4.6 Functional Design of 2007 10 CFR 50, App. A, GDCs 4, 23, None NA Reactivity Control Systems Control Rod Drive System 25, 26, 27, 28, 29, 50.62(c)(3)

Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 22 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP SectionK s

Key Issue(s)

RG 1.70 (FSAR) Section Section Revision AcceptanceKey Issue(s)

Additional Information 4.6.1 Information for CRDS None 4.6.2 Evaluations of the None CRDS 4.6.3 Testing and None Verification of the CRDS 4.6.4 Information for None Combined Performance of Reactivity Systems 4.6.5 Evaluations of None Combined Performance None BTP 4-1 Westinghouse Constant Axial Offset Control (CAOC)

Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 23 of 88 Revision 0 TVA Letter dated May 5, 2011 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status Chapter 5 - Reactor Coolant System and Connected Systems 5 Reactor Coolant System 5

and Connected Systems 5.1 Summary Description None 5.1.1 Schematic Flow None Diagram 5.1.2 Piping and None Instrumentation Diagram 5.1.3 Elevation Drawing None 5.2 Integrity of Reactor None Coolant Pressure Boundary 5.2.1 Compliance with None Codes and Code Cases None 5.2.1.1 Compliance with 2007 10 CFR 50.55a None NA the Codes and Standards 10 CFR 50, App. A, GDC 1 Rule, 10 CFR 50:55a RG 1.26 R4 None 5.2.1.2 Applicable Code 2007 10 CFR 50, App. A, GDC 1 None NA TVA will use code cases originally referenced per Code of Cases 10 CFR 50.55a Record for existing (legacy) equipment and currently RGs 1.84, 1.147 approved code cases for newly installed equipment.

Revision of RG 1.84 and 1.147 will be consistent with requests to use Code Cases.

Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 24 of 88 Revision 0 TVA Letter dated May 5, 2011 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria A

lStatus 5.2.2 Overpressure 5.2.2 2007 10 CFR 50, App. A, GDCs 1, 15, None NA WVA will use the existing code of record plus TMI Protection 30, & 31, 50.55a qualification tests. Should new equipment be required, it RG 1.84 will be purchased to the latest code which has received NUREG-0737, I1.K.3.3, Il.D.1, &

regulatory approval at the time of order, and will be ll.D.3, NUREG 1430 reconciled to the original code of record.

GLs 82-16, and 90-06 Revision of RG 1.84 will be consistent with requests to use Code Cases.

GL 82-16, NUREG-0737 Technical Specifications GL 90-06, Resolution of Generic Issues 70, "PORV and Block Valve Reliability," and 94, "Additional LTOP Protection for PWRs" GL 96-03, Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits TMI Action Item - I1.K.3.3, Reporting SV and RV failures and challenges TMI Action Item - l1.D.1, Relief and safety-valve test requirements TMI Action Item - l1.D.3, Valve position indication TMI Action Item - I1.K.2.14, Lift Frequency of PORVs and SVs TMI Action Item - I1.K.3.1, Auto PORV Design and Testing TMI Action Item - I1.K.3.2, Report on PORV Failures TMI Action Item - I1.K.3.7, Evaluation of PORV Opening Probability Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 25 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 5.2.3 Reactor Coolant 5.2.3 2007 10 CFR 50, App. A, GDCs 1, 4,14, Need to address TVA is preparing Plan to implement Alloy 600 program to mitigate PWSCC Pressure Boundary 30 & 31; App. B, App. G, 50.55a concerns for a discussion of consistent with NEI initiative NEI 03-08. Will also consider Materials RGs 1.31 R3, 1.34,1.36 RO, 1.37, PWSCC of Alloy mitigating NUREG 1823 & NRC Order EA-03-009.

1.43, 1.44, 1.50, 1.71, 1.84 600 components strategy for

& dissimilar metal PWSCC of Alloy For existing (legacy) equipment, TVA will use the following:

welds (DMW) 600 components RGs 1.34 RO, 1.37 RO, 1.43 RO, 1.44 RO, 1.50 RO, 1.71 RO For newly procured/major modified equipment, TVA will use the following: RGs 1.34 R1, 1.37 R1,1.43 R1, 1.44 R1, 1.50 R1, 1.71 R1 Revision of RG 1.84 will be consistent with requests to use Code Cases.

IEB 78-12, Atypical Weld Material in Reactor Pressure Vessel Welds IEB 01-01, Circumferential Cracking of Reactor Pressure Vessel (RPV) Head Penetration Nozzles IEB 02-01, RPV Head Degradation and Reactor Coolant Pressure Boundary Integrity IEB 03-02, Leakage from RPV Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity IEB 04-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at PWRs GL 92-01, Reactor Vessel Structural Integrity GL 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations 5.2.4 Inservice Inspection 5.2.4 Reactor Coolant 2007 10 CFR 50, App. A, GDC 32, 50.2, See 5.2.3 See 5.2.3 Revision of RG 1.147 will be consistent with requests to and Testing of Reactor Pressure Boundary 50.55a use Code Cases.

Coolant Pressure Boundary Inservice Inspection and RG 1.147 IEB 02-02, RPV Head and Vessel Head Penetration Nozzle Testing GL 88-05 Inspection Program.

GL 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants.

Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 26 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Additional Information 5.2.5 Detection of Leakage 5.2.5 Reactor Coolant 2007 10 CFR 50, App. A, GDCs 2, 30 See 5.2.3 See 5.2.3 TVA will institute leak detection consistent with LBB Through Reactor Coolant Pressure Boundary RGs 1.29 R4, 1.45 R0 requirements.

Pressure Boundary Leakage Detection 5.2.6 NSSS Interface None 5.3 Reactor Vessels None 5.3.1 Reactor Vessel 5.3.1 2007*

10 CFR 50, App. A, GDCs 1, 4,14, See 5.2.3 See 5.2.3 See 5.2.3 for Alloy 600.

Materials 30, 31, 32, App. B, G, H, 50.55a, TVA will retain the 1981 SRP and will use RG 1.99 R2 with

.60..61 the exception of Section C.3.

RGs 1.31 R1, 1.34, 1.37, 1.43, For existing (legacy) equipment, TVA will use the following:

1.44, 1.50, 1.65, 1.99 R2, RGs 1.34 RO, 1.37 RO, 1.43 RO, 1.44 RO, 1.50 RO 1.161 RO For newly procured/major modified equipment, TVA will use the following: RGs 1.34 R1, 1.37 R1, 1.43 R1, 1.44 R1, 1.50 R1 TVA will use RG 1.65 RO for existing studs and RG 1.65 R1 for stud lubricant detrimental materials.

5.3.2 Pressure-5.3.2 Pressure-2007 10 CFR 50, App. A, GDCs 1, 14, TVA will use RG 1.99 R2 with the exception of Section C.3 Temperature Limits Temperature Limits, 31, 32, App. G, 50.55a,.60,.61, IEB 75-08, PWR Pressure Instrumentation.

Upper-Shelf Energy, and RGs 1.99 R2,1.161 RO GL 88-11, NRC Position on Radiation Erribdttlement of Pressurized Thermal Reactor Vessel Material Shock 5.3.3 Reactor Vessel 5.3.3 2007*

10 CFR 50, App. A, GDCs 1,4, See 5.2.3 See 5.2.3 TVA will use RG 1.99 R2 with the exception of Section C.3.

Integrity 14, 30, 31, 32, App. B, App. G, H, 50.55a,.60,.66 RG 1.99 R2 5.4 Component and 5.4 Reactor Coolant None None None Subsystem Design System Component and Subsystem Design 5.4.1 Reactor Coolant None Pumps Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 27 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status Additional Information None 5.4.1.1 Pump Flywheel 2007 10 CFR 50, App. A, GDCs 1,4,10 None None Integrity (PWR) 50.55a(a)(1) & (f)

RG 1.14 R1 5.4.2 Steam Generators None None 5.4.2.1 Steam Generator 2007 10 CFR 50, App. A, GDCs 1, 4, None None For existing (legacy) equipment, TVA will use the following:

Materials 14, 15, 30, 31, App. B, App. G, RGs 1.34 RO, 1.37 RO, 1.43 RO, 1.44 RO, 1.50 RO, 1.71 RO 50.36, 55a(b), (c), (d), & (e)

For newly procured/major modified equipment, TVA will RGs 1.31 R3, 1.34, 1.36 RO, 1.37, use the following: RGs 1.34 R1, 1.37 R1, 1.43 R1, 1.44 R1, 1.43, 1.44, 1.50,1.71, 1.84 1.50 R1, 1.71 R1 BTP 5-1 Revision of RG 1.84 will be consistent with requests to use NUREG - 1430 Code Cases.

Replacement steam generator tubing will be Alloy 690.

None 5.4.2.2 Steam Generator 2007 10 CFR 50, App. A, GDC 32, App.

See 5.4.2.1 Open The Steam Generator Program for BLN will comply with Program B, 50.36,.55a,.65 Revision 2 of "EPRI-Steam Generator Program RG 1.121 RO Administrative Procedures" and Revision 2 of NEI 97-06, NUREG-1430 "Steam Generator Program Guidelines".

IEB 89-01, Failure of Westinghouse Steam Generator Tube Mechanical Plugs GL 85-02, Recommended Actions Stemming From NRC Integrated Program for the Resolution of Unresolved Safety Issues Regarding Steam Generator Tube Integrity GL 95-03, Circumferential cracking of Steam Generator (SG) Tubes.

GL 97-05, SG Tube Inspection Techniques GL 97-06, Degradation of SG Internals GL-04-01, Requirements for SG Tube Inspection GL 06-01, SG Tube Integrity and Associated Technical Specifications TMI Action Item - I1.K.2.15, Effects of Slug Flow on OTSGS Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 28 of 88 Revision 0 TVA Letter dated May 5, 2011 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 5.4.3 Reactor Coolant None Piping 5.4.4 Main Steam Line Flow None Restrictions 5.4.5 Main Steam Line None Isolation System 5.4.6 Reactor Core 5.4.6 Reactor Core NA to BLN, BWRs only Isolation Cooling System Isolation Cooling System (BWR) 5.4.7 Residual Heat 5.4.7 Residual Heat 2007 10 CFR 50, App. A, GDCs 2, 4, None None IEB 80-12, Decay Heat Removal System Operability Removal System Removal (RHR) System 5,19, & 34, 10 CFR 50.34 GL 88-17, Loss of Decay Heat Removal RGs 1.29 R4, 1.82 R3 TMI Action Item - I11.D.1.1, Primary coolant outside BTP 5-4 containment NUREG- 0737, III.D.1.1 5.4.8 Reactor Water 5.4.8 Reactor Water NA to BLN, BWRs only Cleanup System Cleanup System (BWR) 5.4.9 Main Steam Line and None Feedwater Piping 5.4.10 Pressurizer None 5.4.11 Pressurizer Relief 5.4.11 Pressurizer Relief 2007 10 CFR 50, App, A, GDCs 2, 4 None None The reactor coolant drain tank performs the pressurizer Discharge System Tank RG 1.29 R4 relief function and will satisfy Code Case N-770.

5.4.12 Valves 5.4.12 Reactor Coolant 2007*

10 CFR 50, App. A, GDCs 1, 14, None None TVA will conform with the 1981 SRP Acceptance Criteria System High Point Vents 17, 19, 30, 32, 34, 36, App. B, for existing (legacy) equipment.

50.34(f), 44(c),.46,.46a & (b),.49,

.55a For existing (legacy) equipment, TVA will use RG 1.100 RGs 1.92 R2, 1.100 Ri.

For newly procured/major modified equipment, TVA will use RG 1.100 R3.

TMI Action Item - Il.B.1, Reactor-coolant-system vents.

Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 29 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section 1 Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 5.4.13 Safety and Relief 5.4.13 Isolation Condenser NA to BLN, BWRs only Valves System (BWR) 5.4.14 Component None Supports None BTP 5-1 Monitoring of 2007 10 CFR 50.71 None None For steam generator secondary side water chemistry, BLN Secondary Side Water will comply with latest revision of "EPRI PWR Secondary Chemistry in PWR Steam Water Chemistry Guidelines" and for primary / secondary Generators leakage compliance will be to latest revision of "EPRI PWR Primary/ Secondary Leak Guidelines."

None BTP 5-2 2007 10 CFR 50, App. G None None Overpressurization RGs 1.26 R4, 1.29 R4 Protection of Pressurized-Water Reactors While Operating at Low Temperatures None BTP 5-3 Fracture 2007 Fracture Toughness:

None None Toughness Requirements 10 CFR 50, App. G, App. H ASME Code,Section III PTS:

10 CFR 50.61 None BTP 5-4 Design 2007 10 CFR 50, App. A, GDC 1 - 5 None None Requirements of the IEEE 338-1987 Residual Heat Removal RG 1.22 RO, 1.33 R2, 1.68 R3 I _

ISystem II Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 30 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

RG 1.70 (FSAR) Section Section Revision AcceptanceKey Issue(s)

Additional Information Chapter 6 - Engineered Safety Features 6 Engineered Safety 6

Features 6.1 Engineered Safety None Feature Materials 6.1.1 Metallic Materials 6.1.1 Engineered Safety 2007 10 CFR 50, App. A,GDCs 1,4,14, None NA For existing (legacy) equipment, TVA will use the following:

Features Materials 31, 35, 41, 55a, App. B Criteria IX, RGs 1.37 RO, 1.44 R0, 1.50 RO, 1.71 RO XIII For newly procured/major modified equipment, TVA will RGs 1.7 R3, 1.31 R3, 1.36 RO, use the following: RGs 1.37 R1, 1.44 R1, 1.50 R1, 1.71 Ri.

1.37, 1.44, 1.50 1.71, 1.84 Revision of RG 1.84 will be consistent with requests to use BTP 6-1 Code Cases.

ASME Code 6.1.2 Organic Materials 6.1.2 Protective Coating 2007 10 CFR 50, App. B None NA GL 98-04, Potential for Degradation of the ECCS and the Systems (Paints) -

RG 1.54 R2 Containment Spray System After a LOCA Because of Organic Materials ASTM D5144-00, ASTM D3911-03 Construction and Protective Coating Deficiencies and Foreign Material in Containment.

6.2 Containment Systems None 6.2.1 Containment 6.2.1 None None NA IEB 73-02, Malfunction of Containment Purge Supply Valve Functional Design Switch None 6.2.1.1.A PWR Dry 2007 10 CFR 50.34(f)(3)(v)(A)(1),.46, None NA TMI Action Item - II.F.1, Accident-monitoring Containments, Including App. K, I.D.2, App. A, GDCs 4, 13, instrumentation Subatmospheric 16, 38, 50, 64 Containments BTP 7-10 NUREG-0737, Item II.F.1 Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 31 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s)

Status None 6.2.1.1.B Ice Condenser NA - Ice Condenser Containments None 6.2.1.1.C Pressure-NA - BWRs Suppression Type BWR Containments None 6.2.1.2, Subcompartment 2007 10 CFR 50, App. A, GDCs 4& 50 None NA Analysis Section 3.2 of NUREG-0609 None 6.2.1.3 Mass and Energy 2007 10 CFR 50, App. A, GDC 50, App.

None NA Release Analysis for K

Postulated Loss-of-Coolant Accidents (LOCAs)

None 6.2.1.4 Mass and Energy 2007 10 CFR 50, App. A, GDC 50 None NA Release Analysis for Postulated Secondary System Pipe Ruptures None 6.2.1.5 Minimum 2007 10 CFR 50.46(a)(1)(i),.46(a)91)(ii),

None NA Containment Pressure

.47(b)(1), App. K Analysis for Emergency RG 1.157 RO Core Cooling System C.3.12.1 Performance Capability BTP 6-2 Studies 6.2.2 Containment Heat 6.2.2 2007 10 CFR 50, App. A, GDCs 38, 39, None NA See 6.1.1 for ASME Code.

Removal Systems 40,.46(b)(5),

IEB 03-01, Potential Impact of Debris Blockage on RGs 1.82 R3, 1.174 R1 Emergency Sump Recirculation GL 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps GL 04-02, Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at PWRs Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 32 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria ey Issue(s)

Status 6.2.3 Secondary 6.2.3 2007 10 CFR 50, App. A, GDCs 4, 16, None NA For existing (legacy) equipment TVA will use RG 1.52, R1.

Containment Functional 43, App. J For newly procured/major modified equipment TVA will use Design RG 1.52 RG 1.52, R3.

BTPs 6-2, 6-3 6.2.4 Containment Isolation 6.2.4 2007 10 CFR 50, App. A, GDCs 1, 2, 4, None NA GL 79-46, Containment Purge and Venting During Normal System 16, 54, 55, 56, 57, App. K, Operation

.62(a)(2),.63(a)(2)

TMI Action Item - I1.E.4.2, Containment isolation RGs 1.11 R1, 1.26 R4, 1.29 R4, dependability.

1.141 R1, 1.155 RO BTP 6-4 NUREG-0737, I1.E.4.2 6.2.5 Combustible Gas 6.2.5 2007 10 CFR 50.44,.44(c)(5), App. A, None NA Control in Containment GDCs 5, 41, 42, 43, RG 1.7 R3 6.2.6 Containment Leakage 6.2.6 2007 10 CFR 50, App A, GDCs 52, 53, None NA Testing 54, App. J 10 CFR 100, Subpart B RG 1.163 RO BTP 6-3 None 6.2.7 Fracture Prevention 2007 10 CFR 50, App. A, GDCs 1, 16, None NA See 6.1.1 for ASME Code of Containment Pressure 51 Boundary ASME Section III Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 33 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 6.3 Emergency Core 6.3 2007 10 CFR 50.46, 50.63, App A, None NA IEB 79-05, Nuclear Incident at TMI Cooling System GDCs 2, 4, 5, 17, 27, 35, 36, 37, IEB 79-24, Frozen Lines App. K IEB 88-04, Potential Safety-Related Pump Loss RGs 1.1 R0, 1.29 R4, 1.47 R1, GL 98-02, Loss of Reactor Coolant Inventory and 1.157 RO Associated Potential for Loss of Emergency Mitigation NUREG - 0737, ll.D.3, II.F.2, Functions While in a Shutdown Condition III.D.1.1, I1.K.3.17 GL 08-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems TMI Action Item - II.F.2, Instrumentation for detection of inadequate core-cooling TMI Action Item - II.K.1.5, Review of ESF Valves TMI Action Item - I1.K.1.10, Operability Status TMI Action Item - I1.K.1.20, Prompt Manual Reactor Trip TMI Action Item - II.K.1.21, Auto SG Anticipatory Reactor Trip TMI Action Item - I.K.3.17, ECC system outages 6.3.1 Design Bases None 6.3.2 System Design None 6.3.3 Performance None Evaluation 6.3.4 Tests and Inspections None 6.3.5 Instrumentation None Requirements 6.4 Habitability Systems 6.4 Control Room 2007 10 CFR 50.2,.67, App. A, GDCs 4, None NA For existing (legacy) equipment TVA will use RG 1.52, R1.

Habitability System 5,19 For newly procured/major modified equipment TVA will use RGs 1.52, 1.78 R1, 1.183 RO, RG 1.52, R3.

Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 34 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Key Issue(s)

RG 1.70 (FSAR) Section Section Revision Issue(s)

Additional Information Reiin Acceptance Criteria Status 1.196 R1, 1.197 RO TVA plans to implement the alternate source term option.

NUREG - 0737, III.D.3.4 GL 03-01, Control Room Habitability TMI Action Item - III.D.3.4, Control room habitability 6.4.1 Design Basis None 6.4.2 System Design None 6.4.3 System Operational None Procedures 6.4.4 Design Evaluations None 6.4.5 Testing and None Inspection 6.4.6 Instrumentation None Requirement 6.5 Fission Product Removal and Control Systems 6.5.1 Engineered Safety 6.5.1 ESF Atmosphere 2007 10 CFR 50, App. A, GDCs 19,41, None NA For existing (legacy) equipment TVA will use RG 1.52 R1.

Feature (ESF) Filter Cleanup Systems 42, 43, 61, 64 For newly procured/major modified equipment TVA will use Systems RG 1.52 RG 1.52 R3.

IEB 80-03, Loss of Charcoal from Standard Type II, 2 Inch Tray Adsorber Cells 6.5.2 Containment Spray 6.5.2 Containment Spray 2007 10 CFR 50, App. A, GDCs 41,42, None NA Systems as a Fission Product 43 Cleanup System ANSI/ANS 56.5 6.5.3 Fission Product 6.5.3 Fission Product 2007 10 CFR 50, App. A,'GDCs 19, 41, None NA For existing (legacy) equipment TVA will use RG 1.52 R1.

Control Systems Control Systems and 42, 43 For newly procured/major modified equipment TVA will use Structures 10 CFR 100, Subpart B RG 1.52 R3.

RG 1.52 Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 35 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 6.5.4 Ice Condenser as a 6.5.4 NA - Ice Condenser Fission Product Cleanup System None 6.5.5 Pressure NA-BWRs Suppression Pool as a Fission Product Cleanup System 6.6 Inservice Inspection of 6.6 Inservice Inspection 2007 10 CFR 50.55a, App. A, GDCs 36, None NA GL 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning.

Class 2 and 3 Components and Testing of Class 2 and 37, 39, 40, 42, 43, 45, & 46 GL 89-10, Safety-Related Motor-Operated Valve Testing 3 Components ASME Sections III and XI and Surveillance.

6.6.1 Components Subject None to Examination 6.6.2 Accessibility None 6.6.3 Examination None Techniques and Procedures 6.6.4 Inspection Intervals None 6.6.5 Examination None Categories and Requirements 6.6.6 Evaluation of None Examination Results 6.6.7 System Pressure None Tests 6.6.8 Augmented Inservice None Inspection to Protect Against Postulated Piping Failures 6.7 Main Steam Isolation 6.7 Main Steam Isolation NA - BWRs Valve Leakage Control Valve Leakage Control System System (BWR)

Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 36 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 6.7.1 Design Bases None 6.7.2 System Description None 6.7.3 System Evaluation None 6.7.4 Instrumentation None Requirements 6.7.5 Inspection and None Testing None BTP 6 pH For None None NA Emergency Coolant Water for Pressurized Water Reactors None BTP 6 Minimum None None NA Containment Pressure Model for PWR ECCS Performance Evaluation None BTP 6 Determination of 2007 10 CFR 50, Appendix J, None NA For existing (legacy) equipment TVA will use RG 1.52 R1.

Bypass Leakage Paths in RGs 1.26 R4, 1.52, 1.96 R1 For newly procured/major modified equipment TVA will use Dual Containment Plants RG 1.52 R3.

None BTP 6 Containment 2007 10 CFR 50, App A, GDCs 54 and None NA Purging During Normal 56, App. K, Plant Operations 10 CFR 100, Subpart B None BTP 6 Currently the 2007 10 CFR 50.46 None NA Responsibility of Reactor Systems Piping From the RWST (or BWST) and Containment Sump(s) to the Safety Injection Pumps Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 37 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan 1 NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision KAcceptance Criteria StatusAI Chapter 7 - Instrumentation and Controls 7 Instrumentation and 7

Controls None 7.0 Instrumentation and None Digital I&C TVA will provide (TVA is aware of Interim Staff Guidance regarding digital Controls - Overview of an updated instrumentation and controls, and will consider this Review Process position on the guidance in the BLN final design.)

licensing basis for Digital I&C and present an overall approach.

None Appendix 7.0-A Review See 7.2 - 7.9.

See 7.0 See 7.0 TVA will identify specific requirements to be met in Process for Digital subsequent sections.

Instrumentation and Control Systems 7.1 Introduction 7.1 Instrumentation and See 7.2 - 7.9.

See 7.0 See 7.0 TVA will identify specific requirements to be met in Controls - Introduction subsequent sections.

7.1.1 Identification of None Safety-Related Systems 7.1.2 Identification of Safety None Criteria None 7.1-Table 7-1 Regulatory See 7.2 - 7.9.

See 7.0 See 7.0 WVA will identify specific requirements to be met in Requirements, subsequent sections.

Acceptance Criteria, and Guidelines for Instrumentation and Control Systems Important to Safety Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 38 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s)

StatusAdditional Information None Appendix 7.1-A See 7.2 - 7.9.

See 7.0 See 7.0 TVA will identify specific requirements to be met in Acceptance Criteria and subsequent sections.

Guidelines for Instrumentation and Controls Systems Important to Safety None Appendix 7.1-B Guidance IEEE-279-1971 See 7.0 See 7.0 for Evaluation of Conformance to IEEE Std 279 None Appendix 7.1-C Guidance IEEE-603-1991 See 7.0 See 7.0 for Evaluation of Conformance to IEEE Std 603 None Appendix 7.1-D Guidance IEEE-7-4.3.2 See 7.0 See 7.0 for Evaluation of the Application of IEEE 7-4.3.2 7.2 Reactor Trip System 7.2 2007 10 CFR 50, App. A, GDC 1, 2, 4, See 7.0 See 7.0 For existing (legacy) equipment, TVA will use IEEE 279-10, 13, 15, 19, 20, 21, 22, 23, 24, 1971.

25, 29, For newly procured/major modified equipment, TVA will 10 CFR 50.55a(a)(1),.55a(h)(2) use IEEE 603-1991, except for the TSX system which will RGs 1.22 RO, 1.47 R1, 1.53 R2, satisfy the requirements of IEEE 603-1998.

1.62 R1, 1.75, 1.105 R3, 1.118 R3, 1.151, 1.152 R2, 1.168 R1, 1.169 RO, 1.170 RO, 1.171 RO, For existing (legacy) equipment, TVA will use the following:

1.172 RO, 1.173 RO, 1.180, 1.204, RGs 1.75 R2, 1.151 RO 1.209 RO For newly procured/major modified equipment, TVA will BTPs 7-3, 7-5, 7-8, 7-9, 7-11, 7-12, use the following: RGs 1.75 R3, 1.151 R1, 1.180 R1, 1.204 7-13, 7-14, 7-17, 7-18, 7-19, 7-RO 21 NUREG-0737, I1.K.2.10 TMI Action Item - I1.K.2.10, Safety-grade trip 7.2.1 Description None Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 39 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 7.2.2 analysis None 7.2.3 NSSS Interface None 7.3 Engineered-Safety-7.3 Engineered Safety 2007 10 CFR 50, App. A, GDC 1, 2, 4, See 7.0 See 7.0 For existing (legacy) equipment, TVA will use IEEE 279-Feature Systems Features Systems 10, 13, 15, 16, 19, 20, 21,22, 23, 1971.

24, 29, 33, 34, 35, 38, 41,44, For newly procured/major modified equipment, TVA will

.55a(a)(1),.55a(h)(2) use IEEE 603-1991, except for the TSX system which will RGs 1.22 RO, 1.47 R1, 1.53 R2, satisfy the requirements of IEEE 603-1998.

1.62 R1, 1.75, 1.105 R3, 1.118 R3, 1.151, 1.152 R2, 1.168 R1, 1.169 RO, 1.170 RO, 1.171 RO, For existing (legacy) equipment, TVA will use the following:

1.172 RO, 1.173 RO, 1.180, 1.204, RGs 1.75 R2, 1.151 RO 1.209 RO For newly procured/major modified equipment, TVA will BTP 7-3, 7-4, 7-6, 7-8, 7-11, 7-12, use the following: RGs 1.75 R3, 1.151 R1, 1.180 R1, 1.204 7-13, 7-14, 7-17, 7-18, 7-19, 7-21 RO NUREG-0737,11.E.1.2, Il.E.4.2 IEB 79-21, Temperature Effects on Level Measurements IEB 80-06, Engineered Safety Features Reset Controls GL 82-28, Inadequate Core Cooling Instrumentation System TMI Action Item - II.E.1.2, Auxiliary feedwater system initiation and flow 7.3.1 Description None 7.3.2 Analysis None Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 40 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section F

Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria KeyIssues)_

Status 7.4 Systems Required for 7.4, Safe Shutdown 2007 10 CFR 50, App. A, GDC 1, 2, 4, See 7.0 See 7.0 For existing (legacy) equipment, TVA will use IEEE 279-Safe Shutdown Systems 13, 19, 24, 34, 35, 38, 1971.

50.55a(a)(1 ),50.55a(h)

For newly procured/major modified equipment, TVA will RGs 1.53 R2, 1.75,1.105 R3, use IEEE 603-1991, except for the TSX system which will 1.118 R3, 1.151, 1.152 R2, satisfy the requirements of IEEE 603-1998.

1.168 R1, 1.169 RO, 1.170 RO, 1.171 RO, 1.172 RO, 1.173 RO, 1.180, 1.189 R2, 1.204, 1.209 R0 For existing (legacy) equipment, TVA will use the following:

BTPs 7-11, 7-12, 7-13, 7-14, 7-17, RGs 1.75 R2, 1.151 RO 7-18, 7-21 For newly procured/major modified equipment, TVA will NUREG-0737, II.G.1 use the following: RGs 1.75 R3, 1.151 R1, 1.180 R1, 1.204 RO IEB 77-04, Calculation Error Affecting Performance of a System for Controlling pH of Containment Sump Water Following a LOCA TMI Action Item - II.G.1, Power supplies for pressurizer relief valves, block valves, & level indicators 7.4.1 Description None 7.4.2 Analysis None Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 41 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

RG 1.70 (FSAR) Section Section Revision AcceptanceKey Issue(s)

Additional Information 7.5 Safety-Related Display 7.5 Information Systems 2007 10 CFR 50, App. A, GDC 1, 2, 4, 13 See 7.0 See 7.0 For existing (legacy) equipment, TVA will use IEEE 279-Instrumentation Important to Safety 19, 24,.55a(a)(1), 50.55a(h) 1971.

RGs 1.47 R1, 1.53 R2, 1.75, 1.97 For newly procured/major modified equipment, TVA will R4, 1.105 R3, 1.118 R3, 1.151, use IEEE 603-1991, except for the TSX system which will 1.152 R2, 1.168 R1, 1.169 RO, satisfy the requirements of IEEE 603-1998.

1.170 RO, 1.171 RO, 1.172 RO, 1.173 RO, 1.180, 1.204, 1.209 RO BTP 7-10, 7-11, 7-12, 7-13, 7-14, 7-For existing (legacy) equipment, TVA will use the following:

17, 7-18, 7-21 RGs 1.75 R2, 1.151 RO.

NUREG-0737,11.D.3, I1.E.1.2, II.F.1, For newly procured/major modified equipment, TVA will II.F.2,11.G.1 use the following: RGs 1.75 R3, 1.151 R1, 1.180 R1, 1.204 RO.

GL 82-33, Supplement to NUREG-0737, Requirements for Emergency Response Capability 7.5.1 Description None 7.5.2 Analysis None 7.6 All Other 7.6 Interlock Systems 2007 10 CFR 50.55a(a)(1), 50.55a(h),

See 7.0 See 7.0 For existing (legacy) equipment, TVA will use IEEE 279-Instrumentation Systems Important to Safety App. A, GDC 1, 2, 4,10,13, 15, 16, 1971.

Required for Safety 19, 24, 25, 28, 33, 34, 35, 38, 41, For newly procured/major modified equipment, TVA will 44 use IEEE 603-1991, except for the TSX system which will RGs 1.47 R1, 1.53 R2, 1.75, satisfy the requirements of IEEE 603-1998.

1.105 R3, 1.118 R3, 1.151, 1.152 R2, 1.168 R1, 1.169 RO, 1.170 RO, 1.171 RO, 1.172 RO, For existing (legacy) equipment, TVA will use the following:

1.173 RO, 1.180, 1.204, 1.209 RO RGs 1.75 R2, 1.151 RO BTP 7-1, 7-2, 7-5, 7-11, 7-12, 7-For newly procured/major modified equipment, TVA will 14, 7-17, 7-18, 7-21 use the following: RGs 1.75 R3, 1.151 R1, 1.180 R1, 1.204 NUREG-0737 RO IEB 90-01, Loss of Fill Oil in Rosemount Transmitters 7.6.1 Description None 7.6.2 Analysis None Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 42 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

RG 1.70 (FSAR) Section Section Revision Acceptance Criteria SAdditional Information 7.7 Control Systems Not 7.7 Control Systems 2007 10 CFR 50.55a(a)(1), 50.55a(h),

See 7.0 See 7.0 For existing (legacy) equipment, TVA will use IEEE 279-Required for Safety App. A, GDC 1, 10, 13, 15, 19, 24, 1971.

28, 29, 44, For newly procured/major modified equipment, TVA will RGs 1.75, 1.105 R3, 1.151, use IEEE 603-1991, except for the TSX system which will 1.152 R2, 1.168 R1, 1.169 RO, satisfy the requirements of IEEE 603-1998.

1.170 RO, 1.171 RO, 1.172 RO, 1.173 R0, 1.180, 1.204, 1.209 R0 BTP 7-5, 7-11, 7-12, 7-14, 7-17, 7-For existing (legacy) equipment, TVA will use the following:

18, 7-19, 7-21 RGs 1.75 R2, 1.151 RO NUREG-0737, II.K.2.9 For newly procured/major modified equipment, TVA will use the following: RGs 1.75 R3, 1.151 R1, 1.180 R1, 1.204 RO IEB 76-07, Crane Hoist Control Circuit Modifications IEB 77-01, Pneumatic Time Delay Relay Setpoint Drift IEB 80-20, Failure of W Type W-2 Spring Return to Neutral Control Switches GL 89-19, Request for Actions Related to Resolution of Unresolved Safety Issue A-47 "Safety Implication of Control Systems in LWR Nuclear Power Plants" Pursuant to 10 CFR 50.54(f)

TMI Action Item - I1.K.2.9, FEMA on ICS 7.7.1 Description None 7.7.2 Analysis None Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 43 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria K

Status 7.8 NSSS Interface 7.8 Diverse 2007 10 CFR 50.55a(a)(1), 50.55a(h),

See 7.0 See 7.0 For existing (legacy) equipment, TVA will use IEEE 279-Instrumentation and 50.62, App. A, GDC 1, 13,19,24 1971.

Control Systems RGs 1.22 R0, 1.62 R1, 1.75, For newly procured/major modified equipment, TVA will 1.105 R3, 1.118 R3, 1.151, use IEEE 603-1991, except for the TSX system which will 1.152 R2, 1.168 R1, 1.169 RO, satisfy the requirements of IEEE 603-1998.

1.170 RO, 1.171 RO, 1.172 RO, 1.173 RO, 1.180, 1.204, 1.209 RO BTP 7-11, 7-12, 7-14, 7-17, 7-18, 7-For existing (legacy) equipment, VA will use the following:

19, 7-21 RGs 1.75 R2, 1.151 RO For newly procured/major modified equipment, TVA will use the following: RGs 1.75 R3, 1.151 R1, 1.180 R1, 1.204 RO 7.8 BOP Interface None None 7.9 Data Communication 2007 10 CFR 50. 50.55a(a)(1),

See 7.0 See 7.0 For existing (legacy) equipment, TVA will use IEEE 279-Systems 50.55a(h), 50.62, App. A, GDC 1, 1971.

2,4,13,19,21,22,23,24,29 For newly procured/major modified equipment, TVA will RGs 1.22 RO, 1.47 R1, 1.53 R2 use IEEE 603-1991, except for the TSX system which will 1.75,1.105 R3, 1.118 R3, satisfy the requirements of IEEE 603-1998.

1.152 R2, 1.168 R1, 1.169 RO, 1.170 RO, 1.171 RO, 1.172 RO, 1.173 RO, 1.180, 1.204, 1.209 RO For existing (legacy) equipment, TVA will use the following:

BTP 7-8, 7-11, 7-12, 7-14, 7-17,7-RG 1.75 R2 18, 7-19, 7-21 For newly procured/major modified equipment, TVA will NUREG-0737 use the following: RGs 1.75 R3, 1.180 R1, 1.204 RO None Appendix 7-A General Agenda, Station Site visits None Appendix 7-B Acronyms, Abbreviations, and Glossary None Branch Technical Positions (BTPs) - Index Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 44 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section K

Key Issue(s)

RG 1.70 (FSAR) Section Section Revision AcceptanceKey Issue(s)

Additional Information None BTP 7 Guidance on "

None NA Isolation of Low-Pressure Systems from the High-Pressure Reactor Coolant System None BTP 7 Guidance on None NA Requirements of Motor-Operated Valves in the Emergency Core Cooling System Accumulator Lines None BTP 7 Guidance on None NA Protection System Trip Point Changes for Operation with Reactor Coolant Pumps Out of Service None BTP 7 Guidance on None NA Design Criteria for Auxiliary Feedwater Systems None BTP 7 Guidance on None NA Spurious Withdrawals of Single Control Rods in Pressurized Water Reactors None BTP 7 Guidance on None NA Design of Instrumentation and Controls Provided to Accomplish Changeover from Injection to Recirculation Mode Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 45 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s)

StatusAdditional Information None BTP 7 Guidance for None NA Application of Regulatory Guide 1.22 None BTP 7 Guidance on None NA Requirements for Reactor Protection System Anticipatory Trips None BTP 7 Guidance on None NA Application of Regulatory Guide 1.97 None BTP 7 Guidance on None NA Application and Qualification of Isolation Devices None BTP 7 Guidance on None NA Establishing and Maintaining Instrument Setpoints None BTP 7 Guidance on None NA Cross-Calibration of Protection System Resistance Temperature Detectors None BTP 7 Guidance on None NA Software Reviews for Digital Computer-Based Instrumentation and Control Systems None BTP 7 Guidance on None NA NA - Part 52 the Level of Detail Required for Design Certification Applications Under 10 CFR Part 52 Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 46 of 88 Revision 0 TVA Letter dated May 5, 2011 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status None BTP 7 Guidance on None NA Self-Test and Surveillance Test Provisions None BTP 7 Guidance on None NA the Use of Programmable Logic Controllers in Digital Computer-Based Instrumentation and Control Systems None BTP 7 Guidance for None NA Evaluation of Diversity and Defense-in-Depth in Digital Computer-Based Instrumentation and Control Systems None BTP 7 Guidance on None NA Digital Computer Real-Time Performance Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 47 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s)

StatusAdditional Information Chapter 8 - Electric Power 8 Electric Power 8

8.1 Introduction 8.1 Electric Power-Introduction 8.2 Offsite Power System 8.2 2007 10 CFR 50 App A, GDCs 2, 4, 5, None NA For newly procured/major modified equipment, TVA will 17, 18, 33, 34, 35, 38, 41, & 44, use RG 1.204 RO.

50.63, 50.65(a)(4)

RGs 1.32 R3, 1.155 RO, 1.160 R2, GL 06-02, Grid Reliability and the Impact on Plant Risk and 1.182 R0, 1.204 the Operability of Offsite Power.

NUREG-0737 8.2.1 Description None 8.2.2 Analysis None 8.2.3 NSSS Interface None 8.2.3 BOP Interface None 8.3 Onsite Power Systems None 8.3.1 A. C. Power Systems 8.3.1 AC Power Systems 2007 10 CFR 50, App A, GDCs 2, 4, 5, Cables:

TVA will review For existing (legacy) equipment, TVA will use IEEE 279-(Onsite) 17, 18, 33, 34, 35, 38, 41,44 & 50, SWBP and its existing 1971.

50.55a(h), 50.63, 50.65(a)(4)

Jamming Position Papers For newly procured/major modified equipment, TVA will RGs 1.6 RO, 1.9 R4, 1.32 R3, 0

Bend Radius and the NRC use IEEE 603-1991.

1.47 R1, 1.53 R2, 1.63, 1.75, SERs on cables 1.106 R1, 1.118 R3, 1.153, 1.155 Pullby RO, 1.160 R2, 1.182 RO, 1.204 For existing (legacy) equipment, TVA will use the following:

BTP 8-5 RGs 1.63 R2, 1.75 R2 NUREG/CR-0660 For newly procured/major modified equipment, TVA will NUREG-0737, II.E.3.1, II.G.1 use the following: RGs 1.63 R3, 1.75 R3, 1.153 R1,.1.204 RO IEB 73-01, Faulty Overcurrent Trip Delay Device in Circuit Breakers for Engineered Safety Systems Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 48 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section 1

1 Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section 1

Revision KAcceptance Criteria KeytismStatust IEB 74-06, Defective Westinghouse Type W-2 Control Switch Component IEB 74-08, Deficiency in the ITE Molded Case Circuit Breakers, Type HE-3 IEB 74-09, Deficiencies in GE Model 4KV Magne-Blast Circuit Breakers IEB 74-12, Incorrect Coils in W Type SG Relays at Trojan IEB 74-13, Improper Factory Wiring on GE Motor Control Centers at Fort Calhoun IEB 74-15, Misapplication of Cutler-Hammer Three Position Maintained Switch Model No. 10250T IEB 76-02, Relay Coil Failures IEB 76-03, Relay Malfunctions - GE Type STD Relays IEB 76-05, Relay Failures IEB 77-02, Potential Failure Mechanism in Certain WAR Relays with Latch Attachments IEB 77-05, Electrical Connector Assemblies IEB 77-08, Assurance of Safety and Safeguards During an Emergency - Locking Systems IEB 78-01, Flammable Contact-Arm Retainers in GE CR120A Relays IEB 78-05, Malfunctioning of circuit Breaker Auxiliary Contact Mechanism IEB 78-06, Defective Cutler-Hammer Type M Relays and DC Coils IEB 79-09, Failure of GE Type AK-2 Circuit Breaker in Safety Related Systems IEB 79-11, Faulty Overcurrent Trip Device in Circuit Breakers for Engineering Safety Systems IEB 79-23, Potential Failure of Emergency Diesel Generator Field Exciter Transformer IEB 79-25, Failures of W BFD Relays in Safety Related Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 49 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s)

Status Systems IEB 79-27, Loss of Non-Class 1E I & C Power System Bus During Operation IEB 79-28, Possible Malfunction of NAMCO Model EA 180 Limit Switches at Elevated Temperatures IEB 80-15, Possible Loss of Emergency Notification System with Loss of Offsite Power IEB 80-19 & R1, Mercury-Wetted Matrix Relay in Reactor Protective Systems IEB 82-04, Deficiencies in Primary Containment Electrical Penetration Assemblies IEB 83-01, Failure of Trip Breakers (Westinghouse DB-50) to Open on Automatic Trip Signal IEB 83-04, Failure of the Undervoltage Trip Function of Reactor Trip Breakers IEB 83-08, Electrical Circuit Breakers with Undervoltage Trip in Safety Related Applications other than the Reactor Trip System IEB 84-02, Failure of GE Type HFA Relays in Use in Class 1 E Safety Systems IEB 85-02, Undervoltage Trip Attachment of W DB-50 Type Reactor Trip Breakers IEB 88-01, Defects in W Circuit Breakers IEB 88-03, Inadequate Latch Engagement in HFA Type Latching Relays Manufactured by General Electric (GE)

Company IEB 88-10, Nonconforming Molded-Case Circuit Breakers GL 79-36, Adequacy of Station Electric Distribution System Voltages GL 80-18, CR3 Reactor Trip GL 96-01, Testing of Safety Related Circuits GL 07-01, Inaccessible or Underground Power Cable Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 50 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status Failures that Disable Accident Mitigation Systems or Cause Plant Transients TMI Action Item - II.E.3.1, Emergency Power for Pressurizer Heaters 8.3.2 D. C. Power Systems 8.3.2 DC Power Systems 2007 10 CFR 50 App A, GDCs 2, 4, 5, None NA For existing (legacy) equipment, TVA will use IEEE 279-(Onsite) 17, 18, 33, 34, 35, 38, 41, 44, 50, 1971.

50.55a(h), 50.63, 50.65(a)(4)

For newly procured/major modified equipment, TVA will RGs 1.6 RO, 1.32 R3, 1.47 R1, use IEEE 603-1991.

1.53 R2, 1.63, 1.75,1.106 R1, 1.118 R3, 1.128, 1.129, 1.153, 1.155 RO, 1.160 R2, 1.182 RO, For existing (legacy) equipment, TVA will use the following:

1.204 RGs 1.63 R2, 1.75 R2, 1.128 R1, 1.129 Ri.

NUREG-0737 For newly procured/major modified equipment, TVA will BTP 8-5 use the following: RGs 1.63 R3, 1.75 R3, 1.128 R2, 1.129 R2, RG 1.153 R1, 1.204 RO 8.3.3 Fire Protection for None Cable systems None 8.4 Station Blackout 2007 10 CFR 50, App A, GDCs 17 & 18, Station Blackout TVA will address 50.63,.65(a)(4)

Station Blackout RGs 1.9 R4, 1.155 R0, 1.160 R2, in response to 1.182 RO USI A-44 None Appendix 8-A General Agenda, Station Site Visits (formerly Appendix B)

None 8-A Branch Technical Positions (PSB)

None 8-B General Agenda, Station Site Visits None BTP 8 Requirements None None NA on Motor-Operated Valves in the ECCS Accumulator Lines Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 51 of 88 Revision 0 TVA Letter dated May 5, 2011 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status None BTP 8 Use of Diesel-None None NA Generator Sets for Peaking None BTP 8 Stability of None None NA Offsite Power Systems None BTP 8 Application of None None NA the Single Failure Criterion to Manually Controlled Electrically Operated Valves None BTP 8 Supplemental None None NA Guidance for Bypass and Inoperable Status Indication for Engineered Safety Features Systems None BTP 8 Adequacy of None None NA Station Electric Distribution System Voltages None BTP 8 Criteria for None None NA Alarms and Indications Associated with Diesel-Generator Unit Bypassed and Inoperable Status Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 52 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section K

Key Issue(s)

A

ý7n AcceptanceI Criteus RG 1.70 (FSAR) Section Section Revision Criteria Status Chapter 9 - Auxiliary Systems 9 Auxiliary Systems 9

9.1 Fuel Storage and None Handling 9.1.1 New Fuel Storage 9.1.1 Criticality Safety of 2007 10 CFR 50 App. A, GDC 62, 50.68 None NA IEB 84-03, Refueling Cavity Water Seal Fresh and Spent Fuel 10 CFR 70.24 IEB 89-03, Potential Loss of Required Shutdown Margin Storage Handling ANSI/ANS 57.1, 57.2, 57.3 During Refueling Operations 9.1.2 Spent Fuel Storage 9.1.2 New and Spent Fuel 2007 10 CFR 50 App. A, GDCs 2, 4, 5, None NA Storage 61, 63, 50.68 10 CFR 70.24, 10 CFR 20.1101(b)

RGs 1.13 R2, 1.29 R4, 1.115 R1, 1.117 R1, 8.8 R3 ANS 57.2, 57.3 9.1.3 Spent Fuel Pool 9.1.3 2007 10 CFR 50 App. A, GDCs 2, 4,5, None NA For existing (legacy) equipment TVA will use RG 1.52 R1.

Cooling and Cleanup 61, 63 For newly procured/major modified equipment TVA will use System 10 CFR 20.1101 (b)

RG 1.52 R3.

RGs 1.13 R2, 1.26 R4, 1.29 R4, 1.52 9.1.4 Fuel Handling System 9.1.4 Light Load Handling 2007 10 CFR 50 App. A, GDCs 2, 5, 61, None NA NUREG-0612, Control of Heavy Loads.

System (Related to 62 GL 81-07, Control of Heavy Loads Refueling)

RG 1.29 R4 ANSI/ANS 57.1-1992 Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 53 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

RG 1.70 (FSAR) Section Section Revision AcceptanceKey Issue(s)

Additional Information None 9.1.5 Overhead Heavy 2007 10 CFR 50 App. A, GDCs 1,2,4,5 None NA IEB 96-02, Movement of Heavy Loads over Spent Fuel, Load Handling Systems 10 CFR 100, Subpart B over Fuel in the Reactor, or over Safety-Related Equipment RGs 1.13 R2, 1.29 R4 NUREG 0554 ANSI N14.6 9.2 Water Systems None 9.2.1 Station Service Water 9.2.1 2007 10 CFR 50 App. A, GDCs 2, 4, 5, None NA IEB 81-03, Flow Blockage to Cooling Water by Asiatic System 44, 45, 46 Clams and Mussels RG 1.29 R4 GL 89-13, Service Water System Problems Affecting GL 89-13, GL 96-06 Safety Related Equipment GL 96-06, Assurance of Equipment Operability and Containment Integrity During DBA Conditions 9.2.2 Cooling System for 9.2.2 Reactor Auxiliary 2007 10 CFR 50 App. A, GDCs 2, 4, 5, None NA For newly procured/major modified equipment TVA will use Reactor Auxiliaries Cooling Water System 44,45,46 RG 1.153 RI.

RGs 1.29 R4, 1.153, 1.155 R0 NUREGs-0718 & 737 BTP ASB 3-1, 3-3 GL 96-06 9.2.3 Demineralized Water 9.2.3 Section 9.2.3 Withdrawn NA NA Makeup System 9.2.4 Potable and Sanitary 9.2.4 2007 10 CFR 50 App. A, GDC 60 None NA The Potable and Sanitary Water Systems serve no safety Water Systems related functions 9.2.5 Ultimate Heat Sink 9.2.5 2007 10 CFR 50 App. A, GDCs 2, 5, 44, None NA 45, 46 RGs 1.27 R1, 1.72 R2 9.2.6 Condensate Storage 9.2.6 2007 10 CFR 50 App. A, GDCs 2, 5, 44, None NA The Condensate Storage and Transfer System serves no Facilities 45, 46, 60, 50.63 safety related function RGs 1.29 R4, 1.59 R2, 1.76 R1, 1.102 R1, 1.117 R1, 1.143 R2, 1.155 RO Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 54 of 88 Revision 0 TVA Letter dated May 5, 2011 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s)

Status 9.2.7 BOP Interface None 9.3 Process Auxiliaries None 9.3.1 Compressed Air 9.3.1 Compressed Air 2007 10 CFR 50 App. A, GDCs 1, 2, 5, None NA GL 88-14, Instrument Air Supply System Problems Systems System 50.63 Affecting Safety-Related Equipment.

RGs 1.29 R4, 1.155 R0 ANSI/ISA $7.3-R1981 9.3.2 Process Sampling 9.3.2 Process and Post-2007 10 CFR 50 App. A, GDCs 1, 2,13, None NA TMI Action Item - ll.B.3, Post-accident sampling.

System accident Sampling 14, 26, 41, 60, 63, 64 systems 10 CFR 20.1101 (b)

RGs 1.21 R2, 1.26 R4, 1.29 R4, 1.97 R4, 8.8 R3 NUREG-0737, II1.D.1.1 ANSI/HPS N13.1-1999 9.3.3 Equipment and Floor 9.3.3 2007 10 CFR 50 App. A, GDCs 2, 4, 60 None NA Drainage System 9.3.4 Chemical and Volume 9.3.4 Chemical and 2007 10 CFR 50 App. A, GDCs 1, 2, 5, None NA IEB 80-05, Vacuum Condition Resulting in Damage to Control System Volume Control System 14, 29, 33, 35, 60, 61, 50.55(a),

Chemical Volume Control System Holdup Tanks (PWR) (Including Boron 50.63(a)(2)

IEB 80-18, Maintenance of Adequate Minimum Flow Thru Recovery System)

RGs 1.26 R4, 1.29 R4, 1.155 RO Centrifugal Charging Pumps Following a Secondary Side NUREG-0737, III.D.1.1 High Energy Rupture IEB 80-05 GL 80-21, Vacuum Condition Resulting in Damage to Chemical Volume Control System Holdup Tanks 9.3.5 Standby Liquid 9.3.5 Standby Liquid NA - BWRs only Control System Control System (BWR) 9.4 Air Conditioning, None Heating, Cooling, and Ventilation Systems Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 55 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 9.4.1 Control Room Area 9.4.1 2007 10 CFR 50 App. A, GDCs 2, 4, 5, None NA For existing (legacy) equipment TVA will use RG 1.52 R1.

Ventilation System 19, 60; 50.63 For newly procured/major modified equipment TVA will use 10 CFR Part 20 RG 1.52 R3.

RGs 1.29 R4, 1.52, 1.78 R1, 1.140 R2, 1.155 RO 9.4.2 Spent Fuel Pool Area 9.4.2 2007 10 CFR 50 App. A, GDCs 2, 5, 60, None NA For existing (legacy) equipment TVA will use RG 1.52 R1.

Ventilation System 61 For newly procured/major modified equipment WVA will use 10 CFR Part 20 RG 1.52 R3.

RGs 1.13 R2, 1.25 RO, 1.29 R4, 1.52, 1.140 R2 9.4.3 Auxiliary and 9.4.3 2007 10 CFR 50 App. A, GDCs 2, 5, 60 None NA For existing (legacy) equipment TVA will use RG 1.52 Ri.

Radwaste Area Ventilation 10 CFR Part 20 For newly procured/major modified equipment TVA will use System RGs 1.29 R4, 1.52,1.140 R2 RG 1.52 R3.

9.4.4 Turbine Building Area 9.4.4 Turbine Area 2007 10 CFR 50 App. A, GDCs 2, 5, 60 None NA For existing (legacy) equipment TVA will use RG 1.52 Ri.

Ventilation System Ventilation System 10 CFR Part 20 For newly procured/major modified equipment TVA will use RGs 1.29 R4, 1.52, 1.140 R2 RG 1.52 R3.

The Turbine Building Area Ventilation System serves no safety function.

9.4.5 Engineered-Safety-9.4.5 2007 10 CFR 50 App. A, GDCs 2, 4, 5, None NA For existing (legacy) equipment TVA will use RG 1.52 RI.

Feature Ventilation System 17, 60; 50.63 For newly procured/major modified equipment TVA will use 10 CFR Part 20 RG 1.52 R3.

RGs 1.29 R4, 1.52, 1.140R2, TMI Action Item - I1.E.4.1, Dedicated Hydrogen 1.155 RO Penetrations NUREG-CR/0660 9.4.6 BOP Interface None 9.5 Other Auxiliary Systems None 9.5.1 Fire Protection None System Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 56 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section K

Key Issue(s)

RG 1.70 (FSAR) Section Section Revision Key Issue(s)

Additional Information None 9.5.1.1 Fire Protection NA This section is not applicable since TVA will implement a Program risk-informed, performance-based fire protection program consistent with the methodology of the NFPA 805 standard.

See SRP Section 9.5.1.2.

None 9.5.1.2 Risk-Informed (RI) 2007 10 CFR 50 App. A, GDC 3, BLN Fire TVA will update TVA plans to submit its position on implementation of a Performance-Based (PB) 50.48(a),.48(c),.109 Protection the BLN fire risk-informed, performance-based fire protection program Fire Protection Program 10 CFR Part 20 Licensing Basis protection consistent with the methodology of the NFPA 805 standard (FPP)

RGs 1.174 R1, 1.189 R2, licensing basis as the BLN licensing basis.

1.200 R2, 1.205 R1 for this issue NUREGs-1600, -1824, 1852, CR-(TAC No. 79283)

IEB 75-04, Cable Fire at BFNPP 6850 since TVA will IEB 92-01, Failure of Thermo-Lag 330 Fire Barrier System NRC Management Directive 8.4 implement a risk-to Maintain Cabling in Wide Cable Trays and Small NFPA 805 (2001 Version)

informed, Conduits Free from Fire Damage & to Perform its Specified performance-Fire Endurance Function based FPP.

GL 92-08, Thermo-Lag 330-1 Fire Barriers GL 06-03, Potentially Nonconforming Hemyc and MT Fire Barrier Configurations 9.5.2 Communication 9.5.2 Communications 2007 10 CFR 50 App. A, GDCs 1, 2, 3, None NA TMI Action Item - III.A.1.2, Upgrade emergency support Systems Systems 4, 19,.47(a)(8),.55a, App. E facilities 10 CFR 73.20(a),.45(e)(2)(iii),

.45(g)(4)(i),.46(e)(5),.46(f),.55(e),

(f)

NUREG-0737, II1.A.1.2 9.5.3 Lighting Systems 9.5.3 2007 NUREG-0700 None NA 9.5.4 Diesel Generator Fuel 9.5.4 Emergency Diesel 2007 10 CFR 50 App. A, GDCs 2, 4, 5, None NA WVA will use Code of Record and applicable code cases for Oil Storage and Transfer Engine Fuel Oil Storage 17 the DG support systems.

System and Transfer System RGs 1.29 R4, 1.137 R1 NUREG/CR-0660 ASME Section XI, ANSI/ANS 59.51 Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 57 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section K

[ Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s)

Status 9.5.5 Diesel Generator 9.5.5 Emergency Diesel 2007 10 CFR 50 App. A, GDCs 2, 4, 5, None NA TVA will use Code of Record and applicable code cases for Cooling Water System Engine Cooling Water 17, 44, 45, 46 the DG support systems.

System RG 1.29 R4 IEB 83-03, Check Valve Failures in Raw Water Cooling NUREG/CR-0660 Systems of DG's 9.5.6 Diesel Generator 9.5.6 Emergency Diesel 2007 10 CFR 50 App. A, GDCs 2, 4, 5, None NA TVA will use Code of Record and applicable code cases for Starting System Engine Starting System 17 the DG support systems.

RG 1.29 R4 NUREG/CR-0660 9.5.7 Diesel Generator 9.5.7 Emergency Diesel 2007 10 CFR 50 App. A, GDCs 2,4,5, None NA TVA will use Code of Record and applicable code cases for Lubrication System Engine Lubrication System 17 the DG support systems.

RG 1.29 R4 ANSI/ANS 59.52 NUREG/CR-0660 9.5.8 Diesel Generator 9.5.8 Emergency Diesel 2007 10 CFR 50 App. A, GDCs 2, 4, 5, None NA WVA will use Code of Record and applicable code cases for Combustion Air Intake and Engine Combustion Air 17 the DG support systems.

Exhaust System Intake and Exhaust RG 1.29 R4 System NUREG/CR-0660 Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 58 of 88 Revision 0 TVA Letter dated May 5, 2011 Table I - BLN Conformance with the NRC Standard Review Plan NUREG0800 (SRP)

SRP SRP Section Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s)

Status Chapter 10 - Steam and Power Conversion System 10 Steam and Power 10 Conversion System 10.1 Summary Description None 10.2 Turbine Generator 10.2 2007 10 CFR 50, App. A, GDC 4; None NA Section XI ASME Code 10.2.1 Design Bases None 10.2.2 Description None 10.2.3 Turbine Disk 10.2.3 Turbine Rotor 2007 10 CFR 50, App. A, GDC 4 None NA Integrity Integrity 10.2.4 Evaluation None 10.3 Main Steam Supply 10.3 2007 10 CFR 50, App. A, GDCs 2,4, 5, None NA System

& 34, 50.63; RGs 1.29 R4, 1.115 R1, 1.117 R1 10.3.1 Design Bases None 10.3.2 Description None 10.3.3 Evaluation None 10.3.4 Inspection and None Testing Requirements 10.3.5 Water Chemistry None 10.3.6 Steam and 10.3.6 2007 10 CFR 50,55a, App. A, GDCs 1, None NA For existing (legacy) equipment, TVA will use the following:

Feedwater System

& 35, App. B; RGs 1.37 RO, 1.50 RO, 1.71 RO Materials RGs1.37,1.50,1.71, 1.84 For newly procured/major modified equipment, TVA will use the following: RGs 1.37 R1, 1.50 R1, 1.71 Ri.

Revision of RG 1.84 will be consistent with requests to use Code Cases.

Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 59 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information R ASection Revision Acceptance Criteria Status 10.4 Other Features of None Steam and Power Conversion System 10.4.1 Main Condensers 10.4.1 2007 10 CFR 50, App. A, GDC 60 None NA 10.4.2 Main Condenser 10.4.2 2007 10 CFR 50, App. A, GDC 60 None NA Evacuation System 10.4.3 Turbine Gland 10.4.3 2007 10 CFR 50, App. A, GDCs 60 None NA Sealing System 10.4.4 Turbine Bypass 10.4.4 2007 10 CFR 50, App. A, GDCs 4 & 34 None NA System 10.4.5 Circulating Water 10.4.5 2007 10 CFR 50, App. A, GDC 4 None NA System 10.4.6 Condensate 10.4.6 2007 10 CFR 50 App. A, GDC 14; None NA Cleanup System 10.4.7 Condensate and 10.4.7 Condensate and 2007 10 CFR 50, App. A GDCs 2, 4, 5, None NA Feedwater Systems Feedwater System 44, 45, 46; RG 1.29 R4; BTP 10-2 NUREG-0927 10.4.8 Steam Generator 10.4.8 Steam Generator 2007 10 CFR 50, App. A GDCs 1, 2,13, None NA Blowdown System Blowdown System (PWR)

& 14; RG 1.143 R2 10.4.9 Auxiliary Feedwater 10.4.9 Auxiliary Feedwater 2007 10 CFR 50, App. A, GDCs 2,4,5, None NA IEB 85-01, Steam Binding of Auxiliary Feedwater Pumps System System (PWR) 19, 34, 44, 45, 46, 50.34(f), 50.62, GL 80-33, Actions Required from TMI 2 Accident 50.63 GL 81-14, Seismic Qualification of AFW BTPs 3-3, 5-4, 10-1 GL 88-03, Resolution of GSI 93, Steam Binding of Auxiliary RGs 1.29 R4, 1.102 R1, 1.117 R1, Feedwater Pumps 1.155 RO TMI Action Item - II.E.1.1, Auxiliary feedwater system.

NUREGs 0611, 0635 &

evaluation 0737,11.E.1.1 Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 60 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key issue(s)

A RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s)

StatusAdditional Information None BTP 10-1 Design NRC staff established design None NA Guidelines for Auxiliary guidelines for the auxiliary Feedwater System Pump feedwater system Drive and Power Supply Diversity for Pressurized Water Reactor Plants None BTP 10-2 Design NRC staff established design None NA Guidelines for Avoiding guidelines for avoiding water Water Hammers in Steam hammer in steam generators.

Generators Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 61 of 88 Revision 0 TVA Letter dated May 5, 2011 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria JlStatus Chapter 11 - Radioactive Waste Management 11 Radioactive Waste 11 None NA Management 11.1 Source Terms 11.1 2007 10 CFR 20.1301,.1301(e), App B, None NA 10 CFR 50.34,.34a, App. A, GDC 60 and App. I RGs 1.110 RO, 1.112 R1, 1.140 R2 NUREG-0017 ANSI/ANS 18.1-1999 11.2 Liquid Waste 11.2 Liquid Waste 2007 10 CFR 20 Sections 1301, None NA IEB 80-10, Contamination of Non-radioactive System and Management Systems Management System 1301(e), 1302 and 1406; Resulting Potential for Unmonitored, Uncontrolled Release 10 CFR 50.34, App. A, GDCs 60, of Radioactivity to Environment 61, App. I; 40 CFR 190 RGs 1.109 R1, 1.110 RO, 1.112 R1, 1.113 R1, 1.143 R2 BTP 11-6 NUREG-0017 11.2.1 Design Bases None 11.2.2 System Description None 11.2.3 Radioactive None Releases 11.2.4 BOP Interface None Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 62 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 11.3 Gaseous Waste 11.3 2007 10 CFR 20.1301,.1301(e), 1302, None NA Management Systems 1406, App. B; 10 CFR 50.34a, App. A, GDCs 3, 60, 61, App. I; 40 CFR 190 RGs 1.109 R1, 1.110 RO, 1.111 R1, 1.112 R1, 1.140 R2, 1.143 R2 BTP 11-5 NUREG-0017 11.3.1 Design Bases None 11.3.2 System Description None 11.3.3 Radioactive None Releases 11.3.4 BOP Interface None 11.4 Solid Waste 11.4 2007 10 CFR 20.1302, 1301(e), 1406, None NA Management System 2006, 2007, 2108, App B, App G 10 CFR 50. 34a, App A, GDCs 60, 61, 63, App I 40 CFR 190, 10 CFR 61,61.55 &.56, 10 CFR 71 49 CFR 171-180 RGs 1.110 RO, 1.112 R1, 1.143 R2 NUREG -0017 BTP 11-3 11.4.1 Design Bases None 11.4.2 System Description None Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 63 of 88 Revision 0 TVA Letter dated May 5, 2011 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 11.5 Process and Effluent 11.5 Process and Effluent 2007 10 CFR 20.1302, 1301, 1301(e),

None NA Radiological Monitoring and Radiological Monitoring 1406 Sampling Systems Instrumentation and 10 CFR 50.34a,.34(f),.36a, App Sampling Systems A, GDCs 60, 63 & 64, & App I RGs 1.21 R2, 1.97 R4, 4.15 R2, 1.33 R2, App A BTP 7-10 11.5.1 Design Bases None 11.5.2 System Description None 11.5.3 Effluent Monitoring None and Sampling 11.5.4 Process Monitoring None and Sampling None BTP 11-3 Design Requirements noted in Section None NA Guidance for Solid 11.4 Radioactive Waste Management Systems Installed in Light-Water-Cooled Nuclear Power Reactor Plants None BTP 11-5 Postulated Requirements noted in Section None NA Radioactive Releases Due 11.3 to a Waste Gas System Leak or Failure None BTP 11-6 Postulated Requirements noted in Section None NA Radioactive Releases Due 11.2 to Liquid-containing Tank Failures Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 64 of 88 Revision 0 TVA Letter dated May 5, 2011 Table I - BLN Conformance with the NRC Standard Review Plan T NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status Chapter 12 - Radiation Protection 12 Radiation Protection 12 12.1 Ensuring that 12.1 Assuring that 2007 10 CFR 19.12, None NA Occupational Radiation Occupational Radiation 10 CFR 20.1101, 1101(b), & 1003 Exposures Are As Low As Exposures Are As Low As RGs 1.33 R2, 1.8 R3, 8.8 R3, Is Reasonably Achievable Is Reasonably Achievable 8.10 R1, 8.27 RO NUREG 1736 12.1.1 Policy None Considerations 12.1.2 Design None Considerations 12.1.3 Operational None Considerations 12.2 Radiation Sources 12.2 2007 10 CFR 20.1201,.1202,.1203, None NA

.1204, 1206,.1207,.1301, &

.1801, App B 10 CFR 50, App A, GDCs 19 &

61.

RGs 1.4 R2, 1.7 R3, 1.112 R1, 1.183 RO NUREG 0737, ll.B.2 12.2.1 Contained Sources None 12.2.2 Airborne Radioactive None Material Sources Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 65 of 88 Revision 0 TVA Letter dated May 5, 2011 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 12.3 Radiation Protection 12.3 - 12.4 Radiation 2007 10 CFR 20 None NA For existing (legacy) equipment TVA will use RG 1.52 R1.

Design Features Protection Design 10 CFR 50.68, App A, GDCs 19, For newly procured/major modified equipment TVA will use 12.4 Dose Assessment Features 61,63 RG 1.52 R3.

RGs 1.4 R2, 1.7 R3, 1.52, 1.69 R1, 1.97 R4, 1.183 R0, 8.2 RO, 8.8 R3, 8.10 R1, 8.19 R1, 8.25 R1, 8.38 RI NUREG 0737, lI.B.2, II.F.1, NUREG 1430, NUREG/CR-3587 ANSI/ANS-HPSSC-6.8.1-1981, ANSI N13.1-1999, ANSI/ANS-6.4-1997(R004) 12.3.1 Facility Design None Features 12.3.2 Shielding None 12.3.3 Ventilation None 12.3.4 Area Radiation and None Airborne Radioactivity Monitoring Instrumentation See 12.4 above See 12.3 - 12.4 above Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 66 of 88 Revision 0 TVA Letter dated May 5, 2011 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria JlStatus 12.5 Health Physics 12.5 Operational Radiation 2007 10 CFR 19.12,.13 None NA TMI Action Item - III.D.3.3, Inplant 12 radiation Program Protection Program 10 CFR 20 monitoring 10 CFR 50.120, App A, GDC 64, App B 10 CFR 71.5 & Subparts H & G.

RGs 1.8 R3, 1.33 R2, 1.97 R4, 8.2 RO, 8.4 RO, 8.6 RO, 8.7 R2, 8.8 R3, 8.9 R1, 8.10 R1, 8.13 R3, 8.15 R1, 8.20 R1, 8.25 R1, 8.26 RO, 8.27 RO, 8.28 RO, 8.29 R1, 8.32 RO, 8.34 RO, 8.35 R1, 8.36 RO, 8.38 RI NUREGs 0041, 0731, 1736, 0737, 1l.B.3 & II1.D.3.3, NUREG/CR-3587 ANSI/ANS 3.1-1978, ANSI N13.6-1999, N42.17A-2003, N42.20-2003, N323A-1997, ANSI/HPS N13.11-2001, N1314-1994, N13.30-1994, N13.42-1997 IEEE 309-1991 12.5.1 Organization None 12.5.2 Equipment, None Instrumentation, and Facilities 12.5.3 Procedures None Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 67 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status Chapter - 13 Conduct of Operations 13 Conduct of Operations 13 13.1 Organizational None structure of Applicant 13.1.1 Management and 13.1.1 2007 10 CFR 50.40(b)

None NA TMI Action Item - I.B.1.2, Independent Safety Technical Support RG 1.8 R3 Engineering Group Organization NUREG-0694, I.B.1.2 13.1.2 Operating 13.1.2 - 13.1.3 2007 10 CFR 50.40(b),.54(j, k, I &m)

None NA TMI Action Item - I.A.1.1, Shift Technical Advisor Organization RGs 1.8 R3, 1.33 R2, 1.114 R3 TMI Action Item - I.A.1.3, Shift Manning NUREG-0694, I.B.1.2 and I.C.3 TMI Action Item - I.A.2.1, Immediate upgrade of RO & SRO NUREG-0737, I.A.1.1 and I.A.1.3 training and qualifications NUREG-1791 TMI Action Item - I.C.3, Shift supervisor responsibilities BTP SPLB 9.5-1, ANSI N18.7/ANS-3.2 13.1.3 Qualifications of None Nuclear Plant Personnel 13.2 Training None 13.2.1 Plant Staff Training 13.2.1 Reactor Operator 2007 10 CFR 50.54, i - m None NA TMI Action Item - I.G.1, Training during low-power testing Program Requalification Program; 10 CFR 55.4,.31,.41,.43,.45,.46, TMI Action Item - I.A.2.3, Administration of training Reactor Operator Training

.59, programs.

RGs 1.8 R3, 1.149 R3 TMI Action Item - I.A.3.1, Revise scope & criteria for NUREGs-0711, 1021, 1220 licensing exams.

TMI Action Item - L.B.4, Training For Mitigating Core Damage TMI Action Item - I1.K.2.2, Procedures to Control AFW Indication Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 68 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

RG 1.70 (FSAR) Section Section Revision AcceptanceKey Issue(s)

Additional Information 13.2.2 Replacement and 13.2.2, Non-Licensed 2007 10 CFR 19.12 None NA Retraining Plant Staff Training 10 CFR 26.21,.22 10 CFR 50.34(b),.40(b),.120, App.

E,Section II., and Section IV.F 10 CFR 55.4 RGs 1.8 R3, 1.149 R3 NUREGs-0711, 1220 BTP SPLB 9.5-1 13.2.3 Applicable NRC None Documents 13.3 Emergency Planning 13.3 2007 10 CFR 50.33,.34, 50.47, App. E, None NA TMI Action Item - III.A.1.1, Emergency Preparedness,

.72(a)(3),.72(a)(4),.72(c)(3)

Short Term 10 CFR 73.71 (a)

TMI Action Item - III.A.2, Emergency. Preparedness 10 CFR 100.1,.3,.10(d),.20,

.21(g) 44 CFR Parts 350, 351, 352 RGs 1.23 R1, 1.97 R4, 1.101 R5, 5.62 R1 NUREG-0737, I.D.2, ll.B.3, II.F.1, and II1.A.1.2 ICMs B.5.c, B.5.d, B.5.e of Commission Orders of 2/25/02 NUREG-0396, 0654/FEMA-REP-1, Ri, 0696, 0718, 0737, 0814, 1394, 1022 NEI 99-01 13.3.1 Preliminary Planning None 13.3.2 Emergency Plan None 13.3.3 BOP Interface None Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 69 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section

[ Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 13.4 Review and Audit 13.4 Operational None None NA Requirements are addressed in other SRP sections.

Programs 13.4.1 Onsite Review None 13.4.2 Independent Review None 13.4.3 Audit Program None 13.5 Plant Procedures None 13.5.1 Administrative 13.5.1 NA None NA Superseded by 13.5.1.1 Procedures None 13.5.1.1 Administrative 2007 10 CFR 26, 50.40(a), 50.40(b), &

None NA TMI Action Item - I.A.1.2, Shift supervisor Procedures - General 50.54(I) responsibilities 10 CFR 73.58 TMI Action Item - I.C.2, Shift & relief turnover procedures RGs 1.33 R2, 1.114 R3 TMI Action Item - I.C.4, Control room access.

NUREGs 0694, I.A.1.2, I.C.2, TMI Action Item - I.C.5, Feedback of operating experience.

I.C.3, I.C.4, 0711, 0737, I.C.5 &

TMI Action Item - I.C.6, Verify correct performance of I.C.6, 0899 operating activities.

ANSI/ANS 3.2-1982, Section 5.2, TMI Action Item - I.C.7, NSSS vendor rev of proc.

ANSI B30.2-1976, Chapters 2 & 3 None 13.5.1.2 Administrative None None NA Requirements are addressed in SRP 14.2.

Procedures - Initial Test Program 13.5.2 Operating and None Maintenance Procedures Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 70 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Ise(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status None 13.5.2.1 Operating and 2007 10 CFR 50.34(b)(6)(iv) & (v), App.

None NA TMI Action Item - I.C.1, Short-term accident & procedure Emergency Operating B, Criteria V & VI, review.

Procedures RG 1.33 R2 TMI Action Item - I.C.8, Pilot Monitoring of Emergency NUREGs-071 1, Chapter 9, Procedures Element 8, NUREG-0899, NUREG- 0737, I.C.1, Supplement 1 to NUREG-0737,1.C.1, Supplement I to NUREG-1358, ANSI/ANS 3.2-1982, Section 5.3 None 13.5.2.2 Maintenance and None None NA Requirements are addressed in other SRP sections.

Other Operating Procedures 13.6 Industrial Security 13.6 Physical Security None None NA Requirements are addressed in other SRP sections.

IEB 07-01, Security Officer Attentiveness.

13.6.1 Preliminary Planning 13.6.1 Physical Security -

2007 10 CFR 26, TVA will consider Preparing The Physical Security section is one of three security Combined License and 10 CFR 50.34(c) & (d), 54(p),

the satisfaction of position paper on elements that must be addressed by TVA for BLN. The first Operating Reactors 54(x),.54(y) the requirements security which part relates to aircraft hazards (SRP 3.5.1.6) and will 10 CFR 73, Apps. B & C,.1,.2, specified in this will include address the requirements of 10 CFR 50.44(hh) related to

.21,.22,.23,.54,.55,.56,.57, 58, section as part of physical security, threat notification and maintenance of communications

.70 an overall regarding a threat. The second part involves physical RG 5.75 RO programmatic security and requirements for it are identified in this section.

NEI-03-12, scope to address The third is Cyber Security and is addressed in Section the various 13.6.6.

aspects of Security included IEB 79-16, Vital Area Access Controls.

in the 2007 SRP.

GL 89-07, Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs.

GL 88-19, Use of Deadly Force by Licensee Guards Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 71 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Issue(s)

Status 13.6.2 Security Plan 13.6.2 Physical Security -

NA None NA Design Certification 13.6.3 NSSS Interface 13.6.3 Physical Security -

NA None NA Early Site Permit 13.6.3 BOP Interface None None 13.6.6 Cyber Security Plan 2007 10 CFR 73.54,.55,.58, App G to Cyber Security Preparing 10 CFR 73 summary RG 5.71 RO discussion on NEI- 08-09 Cyber Security.

Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 72 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status Chapter 14 - Initial Test Program 14 Initial Test Program 14 Initial Test Program and ITAAC-Design Certification 14.1 Specific Information to None NA NA NA be Included in Preliminary Safety Analysis Reports 14.1.1 Scope of Test None Program 14.1.2 Plant Design None Features that are Special, Unique, or First of a Kind 14.1.3 Regulatory Guides None 14.1.4 Utilization of Plant None Operating and Testing Experiences at Other Reactor Facilities 14.1.5 Test Program None Schedule 14.1.6 Trial Use of Plant None Operating and Emergency Procedures 14.1.7 Augmenting None Applicant's Staff During Test Program 14.1.8 NSSS Interface None 14.1.8 BOP Interface None Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 73 of 88 Revision 0 TVA Letter dated May 5, 2011 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s)

Status 14.2 Specific Information to 14.2 Initial Plant Test 2007 10 CFR 30.53(c);

None NA be Included in Final Safety Program - Design 10 CFR 50.34 (b) (6)(iii); App. B, Analysis Reports Certification and New Section Xl; App. J,Section III.A.4 License Applicants RG 1.68 R3 NUREG-0737, Item I.G.1 14.2.1 Summary of Test 14.2.1 Generic Guidelines NA NA NA Program and Objectives for Extended Power Up rate Testing Programs 14.2.2 Organization and None Staffing 14.2.3 Test Procedures None 14.2.4 Conduct of Test None Program 14.2.5 Review, Evaluation, None and Approval of Test Results 14.2.6 Test Records None 14.2.7 Conformance of Test None Programs with Regulatory Guides 14.2.8 Utilization of Reactor None Operating and Testing Experiences in Development of Test Program 14.2.9 Trial Use of Plant None Operating and Emergency Procedures 14.2.10 Initial Fuel Loading None and Initial Criticality Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 74 of 88 Revision 0 TVA Letter dated May 5, 2011 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

A RG 1.70 (FSAR) Section Section Revision AcceptanceKey Issue(s)

Additional Information 14.2.11 Test Program None Schedule 14.2.12 Individual Test None Descriptions None 14.3 Standard Plant DELETED DELETED DELETED DELETED Designs, Initial Test Program - Final Design Approval (FDA)

[DELETED]

None 14.3 Inspections, Tests, NA NA NA See 14.2 Analyses, and Acceptance Criteria None 14.3.1 [Reserved]

RESERVED RESERVED RESERVED RESERVED None 14.3.2 Structural and NA NA NA See 14.2 Systems Engineering -

Inspections, Tests, Analyses, and Acceptance Criteria None 14.3.3 Piping Systems and NA NA NA See 14.2 Components - Inspections, Tests, Analyses, and Acceptance Criteria None 14.3.4 Reactor Systems -

NA NA NA See 14.2 Inspections, Tests, Analyses, and Acceptance Criteria None 14.3.5 Instrumentation and NA NA NA See 14.2 Controls - Inspections, Tests, Analyses, and

_ Acceptance Criteria Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 75 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section K

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s)

Status None 14.3.6 Electrical Systems -

NA NA NA See 14.2.

Inspections, Tests, Analyses, and Acceptance Criteria None 14.3.7 Plant Systems -

NA NA NA See 14.2 Inspections, Tests, Analyses, and Acceptance Criteria None 14.3.8 Radiation NA NA NA See 14.2 Protection - Inspections, Tests, Analyses, and Acceptance Criteria None 14.3.9 Human Factors NA NA NA See 14.2.

Engineering - Inspections, Tests, Analyses, and Acceptance Criteria None 14.3.10 Emergency NA NA NA See 14.2 Planning - Inspections, Tests, Analyses, and Acceptance Criteria None 14.3.11 Containment NA NA NA See 14.2 Systems - Inspections, Tests, Analyses, and Acceptance Criteria 14.3.12 Physical Security NA NA NA See 14.2 Hardware - Inspections, Tests, Analyses, and Acceptance Criteria Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 76 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status Chapter 15 - Accident Analyses 15 Accident Analyses 15 Introduction - Transient None None NA and Accident Analyses None 15.0.1 Radiological 2007 10 CFR 50.49, 50.67, App. A, None NA Consequence Analyses GDC 19, App. E, IV.E.8 Using Alternative Source 10 CFR 51 Terms 10 CFR 20.1201 NUREG-0737, ll.B.2, ll.B.3, II.F.1, II1.D.1.1, II1.A.1.2, III.D.3.4 RG 1.183 RO None 15.0.2 Review of Transient 2007 10 CFR 50.34,.46, App. B & K None NA TMI Action Item - I1.K.3.30, SB LOCA methods and Accident Analysis NUREG-0737, II.K.3.30 Method None 15.0.3 Design Basis 2007 10 CFR 50.34(a)(1)

None NA Accident Radiological 10 CFR 50, App. A, GDC 19 Consequences of 10 CFR 50, App. E, IV.E.8 Analyses for Advanced 10 CFR 100, Subpart B Light Water Reactors None 15.1.1 - 15.1.4 Decrease 2007 10 CFR 50, App. A, GDCs - 10, None NA in Feedwater 13,15,20, 26 Temperature, Increase in RGs 1.53 R2, 1.105 R3 Feedwater Flow, Increase in Steam Flow, and Inadvertent Opening of a Steam Generator Relief or Safety Valve None 15.1.5 Steam System 2007 10 CFR 50, App. A, GDCs 13, 17, None NA TMI Action Item - I1.K.2.16, RCP seal damage Piping Failures Inside and 27, 28, 31,35 GL 83-10e & f, Resolution of TMI Action Item II.K.3.5 Outside of Containment NUREG 0737, I1.E.1.2, I1.K.2.16, "Automatic Trip of Reactor Coolant Pumps" (PWR)

I1.K.3.5 BTP 3-3 & 3-4 Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 77 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status None 15.1.5.A Radiological 2007 10 CFR 100, Subpart B None NA Consequences of Main RG 1.4 R2 Steam Line Failures Outside Containment of a PWR None 15.2.1 - 15.2.5 Loss of 2007 10 CFR 50, App. A, GDCs 10, 13, None NA External Load; Turbine 15, 17, & 26 Trip; Loss of Condenser RGs 1.53 R2, 1.105 R3 Vacuum; Closure of Main Steam Isolation Valve (BWR); and Steam Pressure Regulator Failure (Closed)

None 15.2.6 Loss of 2007 10 CFR 50, App. A, GDC 10, 13, None NA Nonemergency AC Power 15, 16, & 26 to the Station Auxiliaries RGs 1.53 R2, 1.105 R3 None 15.2.7 Loss of Normal 2007 10 CFR 50, App. A, GCDs 10, 13, None NA Feedwater Flow 15, 17, 26 NUREG-0737,11.E.1.1, II.E.1.2 RGs 1.53 R2, 1.105 R3 None 15.2.8 Feedwater System 2007 10 CFR 50, App. A, GDCs 13, 17, None NA Pipe Breaks Inside and 25, 27, 28, 31, 35 Outside Containment 10 CFR 100, Subpart B (PWR)

NUREG-0737, II.E.1.1, II.E.1.2, I1.K.2.16, BTPs 3-3 & 3-4 None 15.3.1 - 15.3.2 Loss of 2007 10 CFR 50, App. A, GDCs 10, 13, None NA Forced Reactor Coolant 15, 17, 20, 26 Flow Including Trip of RGs 1.53 R2, 1.105 R3 Pump Motor and Flow Controller Malfunctions Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 78 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status None 15.3.3 - 15.3.4 Reactor 2007 10 CFR 50, App. A, GDCs 17, 27, None NA Coolant Pump Rotor 28, & 31 Seizure and Reactor 10 CFR 100, Subpart B Coolant Pump Shaft Break NUREG-1465 None 15.4.1 Uncontrolled 2007 10 CFR 50, App. A, GDCs 10, 13, None NA Control Rod Assembly 17, 20, & 25 Withdrawal from a Subcritical or Low Power Startup Condition None 15.4.2 Uncontrolled 2007 10 CFR 50, App. A, GDCs 10, 13, None NA Control Rod Assembly 17, 20, & 25 Withdrawal at Power None 15.4.3 Control Rod 2007 10 CFR 50, App. A, GDCs - 10, None NA misoperation (System 13, 20, & 25 Malfunction or Operator Error)

None 15.4.4 - 15.4.5 Startup of 2007 10 CFR 50, App. A, GDCs 10, 13, None NA an Inactive Loop or 15, 20, 26, 28 Recirculation Loop at an RGs 1.53 R2, 1.105 R3 Incorrect Temperature, and Flow Controller Malfunction Causing an Increase in BWR Core Flow Rate None 15.4.6 Inadvertent 2007 10 CFR 50, App. A, GDCs - 10, None NA Decrease in Boron 13, 15, & 26 Concentration in the Reactor Coolant System (PWR)

None 15.4.7 Inadvertent Loading 2007 10 CFR 50, App. A, GDC 13 None NA and Operation of a Fuel 10 CFR 100, Subpart B Assembly in an Improper Position Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 79 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status None 15.4.8 Spectrum of Rod 2007 10 CFR 50, App. A, GDCs 13 &

None NA Ejection Accidents (PWR) 28, 50.67 10 CFR 100, Subpart B RGs 1.77 RO, 1.183 RO None 15.4.8.A Radiological 2007 10 CFR 100, Subpart B None NA Consequences of a RG 1.77 RO Control Rod Ejection Accident (PWR)

None 15.4.9 Spectrum of Rod NA - BWRs Drop Accidents (BWR)

None 15.4.9.A Radiological NA - BWRs Consequences of Control Rod Drop Accident (BWR)

None 15.5.1 - 15.5.2 Inadvertent 2007 10 CFR 50, App. A, GDCs 10, 13, None NA Operation of ECCS and 15 & 26 Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory None 15.6.1 Inadvertent 2007 10 CFR 50, App. A, GDC 10, 13, None NA Opening of a PWR 15, & 26 Pressurizer Pressure RGs 1.53 R2, 1.105 R3 Relief Valve or a BWR Pressure Relief Valve None 15.6.2 Radiological 2007 10 CFR 50, App. A, GDC 55 None NA Consequences of the 10 CFR 100, Subpart B Failure of Small Lines RG 1.11 R1 Carrying Primary Coolant Outside Containment None 15.6.3 Radiological 2007 10 CFR 100, Subpart B None NA Consequences of Steam RG 1.4 R2 Generator Tube Failure Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 80 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

RG 1.70 (FSAR) Section Section Revision AcceptanceKey Issue(s)

Additional Information None 15.6.4 Radiological NA - BWRs Consequences of Main Steam Line Failure Outside Containment (BWR)

None 15.6.5 Loss-of-Coolant 2007 10 CFR 50.46 None NA TMI Action Item - II.K.3.31, Compliance with CFR 50.46 Accidents Resulting From 10 CFR 50, App. A, GDC 13, 35 Spectrum of Postulated 10 CFR 50, App. K Piping Breaks Within the 10 CFR 100, Subpart B Reactor Coolant Pressure RG 1.157 RO Boundary NUREG-0737, II.K.3.5, II.K.3.30, II.K.3.31 None 15.6.5.A Radiological 2007 10 CFR 100, Subpart B None NA Consequences of a RG 1.4 R2 Design Basis Loss-of-Coolant Accident Including Containment Leakage Contribution None 15.6.5.B Radiological 2007 10 CFR 100, Subpart B None NA For existing (legacy) equipment TVA will use RG 1.52, R1.

Consequences of a RGs 1.4 R2, 1.7 R3, 1.52 For newly procured/major modified equipment TVA will use Design Basis Loss-of-RG 1.52, R3.

Coolant Accident: Leakage from Engineered Safety Feature Components Outside Containment None 15.6.5.D Radiological NA - BWRs Consequences of a Design Basis Loss-of-Coolant Accident: Leakage from Main Steam Isolation Valve Leakage Control System (BWR)

Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 81 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status None 15.7.3 Postulated 2007 10 CFR 20 None NA Radioactive Releases Due 10 CFR 50, App. A, GDC 60 to Liquid-Containing Tank Failures None 15.7.4 Radiological 2007 10 CFR 50, App. A, GDC 61 None NA Consequences of Fuel 10 CFR 100, Subpart B Handling Accidents RG 1.25 R0 None 15.7.5 Spent Fuel Cask 2007 10 CFR 50, App. A, GDC 61 None NA Drop Accidents 10 CFR 100, Subpart B RG 1.25 RO None 15.8 Anticipated 2007 10 CFR 50.46, 62, App. A, GDCs None NA GL 83-28, Required Actions Based on Generic Implications Transients Without Scram 12, 13, 14, 16, 35, 38, & 50 of Salem ATWS Events (Prior and future GLs, with the exception of certain discrete scopes, have been screened into the following list):

1.2 - Post Trip Review Data and Information Capability.

2.1 - Equipment Classification and Vendor Interface (Reactor Trip System Components).

2.2 - Equipment Classification and Vendor Interface (All SR Components).

3.1 - Post-Maintenance Testing (Reactor Trip System Components).

3.2 - Post-Maintenance Testing (All SR Components).

4.1 - Reactor Trip System Reliability (Vendor Related Modifications).

4.3 - Reactor Trip System Reliability (Automatic Actuation of Shunt Trip Attachment).

None 15.9 Boiling Water Reactor NA None NA NA - BWRs Stability Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 82 of 88 Revision 0 TVA Letter dated May 5, 2011 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status Chapter 16 - Technical Specifications 16 Technical Specifications 16 2007 10 CFR 50.34(b)(6)(vi), 50.36, None NA The NUREG-1430 template will need to be modified for

.36a digital safety-related instrumentation and control systems.

NUREG-1430 GL 85-10, Technical Specification for GL 83-28, Item 4.3 GL 86-13, Potential Inconsistency Between Plant Safety Analysis and Technical Specifications 16.1 Preliminary Technical 16.1 Risk-informed 2007 10 CFR 50, App. A, 50.36, 50.92 None NA Specifications Decision Making:

RGs 1.174 R1, 1.177 RO Technical Specifications 16.2 Proposed Final None Technical Specifications Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 83 of 88 Revision 0

Enclosure. 1 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision KAcceptance Criteria Status Chapter 17 - Quality Assurance 17 Quality Assurance 17 17.1 Quality Assurance 17.1 Quality Assurance 2007 10 CFR 50, App. A & B, 50.55a, Cessation of QA Forwarded TVA submitted the Quality Verification Program to NRC on During Design and During the Design and 50.55(e)

Program submittal on the 4/1/11.

Construction Construction RGs 1.8 R3, 1.26 R4, 1.29 R4, Quality IEB 83-06, Nonconforming Material Supplied by Tube-Line.

1.38 R2 Verification IEB 83-07, Apparently Fraudulent Products Sold by Ray ANSI/ANS-3.1-1978 Program to NRC Miller, Inc.

BTPs - ASB 9.5-1 on 4/1/11.

IEB 87-02, Fastener Testing to Determine Conformance with Applicable Material Specifications.

IEB 88-05, Nonconforming Materials Supplied by Piping Supplies, Inc. and West Jersey Manufacturing Company.

17.1.1 Organization None 17.1.2 Quality Assurance None Program 17.1.3 Design Control None 17.1.4 Procurement None Document Control 17.1.5 Instructions, None Procedures, and Drawings 17.1.6 Document Control None 17.1.7 Control of None Purchased Material, Equipment, and Services 17.1.8 Identification and None Control of Materials, Parts, and Components 17.1.9 Control of Special None Processes 17.1.10 Inspection None Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 84 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section 1

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria j

s Status 17.1.11, Test Control None 17.1.12 Control of None Measuring and Test Equipment 17.1.13 Handling, Storage, None and Shipping 17.1.14 Inspection, Test, None and Operating Status 17.1.15 Nonconforming None Materials, Parts, or Components 17.1.16 Corrective Action None 17.1.17 Quality Assurance None Records 17.1.18 Audits None 17.2 Quality Assurance 17.2 2007 10 CFR 50, App. B None NA During the Operations ANSI N45.2.12 Phase None 17.3 Quality Assurance 2007 10 CFR 21, None NA Program Description 10 CFR 50, App. A, Criterion 1, App. B,.54(a)(3),.55a,.55(e),

.55(f)(3)

RGs 1.26 R4, 1.29 R4, 1.36 R0, 1.143 R2 ASME Code,Section III, None 17.4 Reliability Assurance NA None NA TVA intends to complete a Level I and II PRA, as well as Program (RAP) meeting the requirements of 10CFR50.65, Maintenance Rule, and 10CFR50.69, Risk Informed Categorization of SSE's.

Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 85 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section K

Key Issue(s)

RG 1.70 (FSAR) Section Seto Revsio Key Issue(s)

Additional Information Section Revision Acceptance Criteria Status None 17.5 Quality Assurance NA None NA GL 88-18, Plant Record Storage on Optical Disks Program Description -

Design Certification, Early Site Permit and New License Applicants None 17.6 Maintenance Rule 2007 10 CFR 50.59, 50.65, None NA 50.65(a),50.69 RGs 1.160 R2, 1.182 R0, 1.187 R0 Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 86 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

RG 1.70 (FSAR) Section Section Revision Key Issue(s)

Additional Information Seto eiin Acceptance Criteria Status Chapter 18 - Human Factors Engineering None 18 Human Factors 2007 10 CFR 50. 54(i) to (m),.120 Integrated HFE Developing plan TMI Action Item - I.D.1, Control room design reviews Engineering 10 CFR 55 Plan, CRDR and and preparing to GL 89-06, TMI Action Plan Item I.D.2 - Safety Parameter RGs 1.22 RO, 1.47 R1, 1.62 R1, redesign of the discuss with NRC Display System 1.97 R4, 1.105 R3, 1.174 R1 control room NUREG-0737, I.C.5, I.D.1, I.D.2,11.E.1.2, II.E.3.1, II.F.1, II.F.2, III.A.1.2, III.D.3.3, NUREG-0696, 0700, 0711, 1342, 1764, 0835 None 18A. Crediting Manual 2007 10 CFR 50, App. B, Criteria II, III, Operator Actions in V, VI,.120 Diversity and Defense-in-BTP 7-19 Depth (D3) Analyses NUREG -0711 Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 87 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP)

SRP SRP Section Key Issue(s)

Key Issue(s)

Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status Chapter 19 - Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors None 19.0 Probabilistic Risk 2007 10 CFR 50.34(f)(1)(i), App. B, GL 88-20, Individual Plant Examination for Severe Accident Assessment and Severe 50.69 Vulnerability.

Accident Evaluation for RGs 1.174 R1, 1.200 R2 New Reactors ASME/ANS RA-Sa-2009, Addenda to ASME/ANS RA-S-2008 None 19.1 Determining the 2007 RGs 1.174 R1,1.200 R2 Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities None 19.2 Review of Risk NA - Operating plants Information Used to Support Permanent Plant-Specific Changes to the Licensing Basis: General Guidance Note: If a section number is indicated in the SRP section column, the title for the SRP section is the same as the FSAR title.

Page 88 of 88 Revision 0 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 71-01 Involves Main Steam Isolation Valves NA BWR IEB 71-02 No Title - Involves PWR Reactor Trip Circuit NA Addressed to specific plant(s).

Breakers IEB 71-03 No Title - Involves Catastrophic Failure of NA Addressed to specific plant(s).

Main Steam Line Relief Valve Headers IEB 72-01 Failed Hangers for Emergency Core Cooling NA Addressed to specific plant(s).

System Suction Header IEB 72-02 Simultaneous Actuation of a Safety Injection NA Addressed to specific plant(s).

Signal on Both Units of a Dual Unit Facility IEB 72-03 Limitorque Valve Operator Failures NA Addressed to specific plant(s).

IEB 73-01 Faulty Overcurrent Trip Delay Device in Circuit Open TVA will determine if the identified circuit breakers were procured and Breakers for Engineered Safety Systems installed in Engineered Safety Systems at BLN. If so, TVA will determine if they have similar deficiencies to those noted in the IEB and either correct the deficiency or replace the circuit breaker with a different type.

IEB 73-02 Malfunction of Containment Purge Supply Open TVA will review the design of the control circuit for the BLN containment Valve Switch ventilation system isolation valves to determine whether the failure of a single control switch could result in the simultaneous failure of the redundant supply valves or redundant exhaust valves.

IEB 73-03 Defective Hydraulic Snubbers and Restraints Open The use of Bergen-Patterson hydraulic snubbers that were the subject of IEB 73-03 will be prohibited in the BLN design and TVA will confirm that no such snubbers have been installed or procured.

IEB 73-04 Defective Bergen-Patterson Hydraulic Shock Open The use of Bergen-Patterson hydraulic snubbers that were the subject of Absorbers IEB 73-04 will be prohibited in the BLN design and TVA will confirm that no such snubbers has been installed or procured.

IEB 73-05 Manufacturing Defect in BWR Control Rods NA BWR IEB 73-06 Inadvertent Criticality in a BWR NA BWR IEB 74-01 Valve Deficiencies Open TVA will determine if similar valves to those identified in this IEB and IE Notice 93-97 were procured and installed at BLN. If so, it will be determined if they have similar operating deficiencies as noted in the IEB and IEN. If deficiencies are found, they will be corrected or the valves will be replaced with an acceptable alternative not having such issues.

IEB 74-02 Truck Strike Possibility NA Information IEB 74-03 Failure of Structural or Seismic Support Bolts NA Not applicable to BLN. The letter was addressed to all plants with current on Class I Components operating licenses and those with fuel load prior to 1/31/75.

Revision 0 Page 1 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 74-04 &

Malfunction of Target Rock Safety Relief NA BWR 4a Valves IEB 74-05 Shipment of an Improperly Shielded Source NA Does not apply to power reactors IEB 74-06 Defective Westinghouse Type W-2 Control Open TVA will determine if the identified control switches were procured and Switch Component installed at BLN. If so, TVA will determine if they have the deficiencies noted in the IEB. If deficiencies are found, TVA will either correct the deficiency or replace the control switch with a different type.

IEB 74-07 Personnel Exposure - Irradiation Facility NA Does not apply to power reactors IEB 74-08 Deficiency in the ITE Molded Case Circuit Open TVA will determine if the identified circuit breakers were procured and Breakers, Type HE-3 installed at BLN. If so, TVA will determine if they have the deficiencies noted in the IEB. If deficiencies are found, WVA will either correct them or replace the circuit breaker with a different type.

IEB 74-09 Deficiencies in GE Model 4KV Magne-Blast Complete There is no 4KV system at BLN.

Circuit Breakers IEB 74-10 Failures in 4 inch Bypass Pipe at Dresden NA BWR IEB 74-11 Improper Wiring of Safety Injection Logic at NA Westinghouse Zion 1 & 2 IEB 74-12 Incorrect Coils in W Type SG Relays at Trojan Open WVA will determine if the identified relay coils were procured and installed at BLN. If so, WVA will determine if they have deficiencies noted in the IEB.

If deficiencies are found, WVA will either correct them or replace the relay coils with a different type.

IEB 74-13 Improper Factory Wiring on GE Motor Control Complete There are no GE motor control centers at BLN.

Centers at Fort Calhoun IEB 74-14 BWR Relief Valve Discharge to Suppression NA BWR Pool IEB 74-15 Misapplication of Cutler-Hammer Three Open TVA will determine if model 10250T switches are currently installed at Position Maintained Switch Model No. 10250T BLN. If they are, these switches will be replaced with the series A3 switches.

IEB 74-16 Improper Machining of Pistons in Colt NA The Diesel Generators at BLN are Model DSRV-16-4 manufactured by Industries (Fairbanks-Morse) Diesel Transamerica DeLaval Company (TDI). Since Fairbanks Morse is not the Generators manufacturer of the DGs, IEB 74-16 is not applicable to BLN.

IEB 75-01 Through-Wall Cracks in Core Spray Piping at NA BWR Dresden-2 IEB 75-02 Defective Radionics Radiograph Exposure NA Does not apply to power reactors Devices and Source Changes Revision 0 Page 2 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 75-03 Incorrect Lower Disc Spring and Clearance Open WVA will replace ASCO solenoid valves with new and more reliable Dimension in Series 8300 and 8302 ASCO valves.

Solenoid Valves IEB 75-04 Cable Fire at BFNPP Open Implementation of the Fire Protection program will result in compliance with the guidance contained in R.G. 1.189 and with the issues addressed in this bulletin.

IEB 75-05 Operability of Category I Hydraulic Shock and Open WVA response is contained in letters dated 6/16/75 and 7/2/75. As stated in Sway Suppressors the WVA letters, the testing and maintenance programs for plants not yet in operation will be consistent with those listed in the letters, section 1.c.

IEB 75-06 Defective W Type OT-2 Control Switches Closed TVA stated in a 7/31/75 letter that no OT-2 switches are planned for use at BLN and NRC closed the IEB in IR 438/439/75-7.

IEB 75-07 Exothermic Reaction in Radwaste Shipment NA Does not apply to power reactors IEB 75-08 PWR Pressure Instrumentation Open The capability to continuously record reactor coolant system temperature and pressure during heatup and cooldown, as well as during power operation, will be included as a functional requirement for the Plant Integrated Computer System.

IEB 76-01 BWR Isolation Condenser Tube Failure NA BWR IEB 76-02 Relay Coil Failures Open A WVA letter to NRC dated 5/17/76 states, "Relays of the type described in IEB Nos. 76-02 and 76-03 are planned for use in Class 1 E service at this facility (BLN). The relays will be inspected for this condition before installation at the site." The relays in question will be replaced or refurbished, and WVA will complete inspections to verify the same.

IEB 76-03 Relay Malfunctions - GE Type STD Relays Open See response to IEB 76-02.

IEB 76-04 Cracks in Cold Water Piping at BWRs NA BWR IEB 76-05 Relay Failures Closed WVA letter dated 6/7/76 stated that the relays in question were not used in safety related circuits at BLN. NRC closed this IEB in their letter dated 8/18/76.

IEB 76-06 Diaphragm Failures in Air Operated Auxiliary Open WVA will determine if valves of the type described in the Bulletin are to be Actuators for Safety/Relief Valves used at BLN, and if so, that installation procedures are developed and periodic inspections conducted to avoid the failures discussed.

IEB 76-07 Crane Hoist Control Circuit Modifications Complete WVA stated in a letter dated 10/29/76 that due to differences in brake design, no action was required at BLN.

IEB 76-08 Teletherapy Units NA Does not apply to power reactors IEB 77-01 Pneumatic Time Delay Relay Setpoint Drift Complete WVA letter dated 7/1/77 states that BLN does not use these relays.

Revision 0 Page 3 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 77-02 Potential Failure Mechanism in Certain WAR Complete TVA letter dated 11/11/77 stated that "no relays of the type identified as a Relays with Latch Attachments potential problem have been used or are planned for use in safety related circuits at BLN."

IEB 77-03 On-Line Testing of the W Solid State NA Applies to Westinghouse units only.

Protection System IEB 77-04 Calculation Error Affecting Performance of a Open TVA letter, dated 1/23/78, stated that sodium hydroxide will be utilized at System for Controlling pH of Containment BLN for post-LOCA containment emergency sump water pH control.

Sump Water Following a LOCA Conservative calculations show that the minimum design specified volume of 22 weight percent sodium hydroxide will ensure attainment of a sump water pH in excess of 7.0. Limits of the sodium hydroxide volume and weight percent will be incorporated into the plant technical specifications.

TVA will confirm that the calculations remain valid.

IEB 77-05 Electrical Connector Assemblies Open TVA letter dated 1/17/78 indicated that the subject electrical connector assemblies were scheduled to be installed in BLN. TVA will confirm that, if used, the connector assemblies will be fully qualified for the environments to which they will be subjected.

IEB 77-06 Potential Problems with Containment NA OL @ time Electrical Penetration Assemblies IEB 77-07 Containment Electrical Penetration Open TVA letter dated 1/20/78 included BLN and was negative on all potential Assemblies at Nuclear Power Plants under issues. TVA will evaluate the containment electrical penetration assembly Construction failures described in the bulletin and ensure they are adequately addressed for BLN.

IEB 77-08 Assurance of Safety and Safeguards During Open.

TVA letter dated 3/1/78 stated that 1) BLN will have facilities for prompt an Emergency - Locking Systems emergency ingress into electrically locked safety-related areas by essential employees, 2) is providing reliable and uninterruptible auxiliary power to electrical locking systems, 3) is providing operational electrical locking devices, 4) is providing means to periodically test all electrical locking systems to confirm their operability and to periodically test the capability to switch to auxiliary power, and 5) emergency plans and procedures will allow emergency ingress and unimpeded egress for any postulated occurrence. TVA will confirm that action items identified in the letter are still in effect and, if not, identify new actions that address the issues described in the Bulletin.

IEB 78-01 Flammable Contact - Arm Retainers in GE Complete TVA letter dated 3/20/78 states that none of the relays of the type CR120A Relays described in the bulletin are installed or scheduled to be installed at BLN.

Revision 0 Page 4 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 78-02 Terminal Block Qualification Complete TVA letter of 3/1/78 stated that BLN did not use, or plan to use, unprotected terminal blocks in systems which must function in a post accident environment.

IEB 78-03 Potential Gas Mixture Accumulations NA BWR Associated with BWR Offgas System Operations IEB 78-04 Environmental Qualification of Certain Stem Open Limit switches, including those identified in this bulletin, will be replaced at Mounted Limit Switches Inside Reactor BLN.

Containment IEB 78-05 Malfunctioning of Circuit Breaker Auxiliary Complete TVA letter dated 6/12/78 stated that TVA "neither uses nor do we plan to Contact Mechanism use circuit breaker auxiliary contact mechanisms of the type described by IEB 78-01 in Class 1 E circuits of the subject plants." The subject plants include BLN.

IEB 78-06 Defective Cutler-Hammer Type M Relays and Complete TVA letter dated 7/31/78 stated that "TVA does not now use or plan to use DC Coils the C-H D23 MRD relays in safety related systems for BLN."

IEB 78-07 Protection Afforded by Air-Line Respirators NA OL @ time and Supplied-Air Hoods IEB 78-08 Radiation Levels from Fuel Element Transfer NA OL @ time Tubes IEB 78-09 BWR Drywell Leakage Paths Associated with NA BWR Inadequate Drywell Closures IEB 78-10 Bergen-Patterson Hydraulic Shock Open The use of Bergen-Patterson hydraulic snubbers that were the subject of Suppressor Accumulator Spring Coils IEB 78-10 will be prohibited in the BLN design and TVA will confirm that no such snubbers have been used or procured.

IEB 78-11 Examination of Mark I Containment Torus NA BWR Welds IEB 78-12 Atypical Weld Material in Reactor Pressure Complete B&W submitted a generic report entitled "Records Investigation Report Vessel Welds Related to Off-Chemistry Welds in Material Surveillance Specimens and Responses to Bulletin 78-12 and 78-12a Supplement" (see letter from James Taylor - B&W to G. Reinauth - NRC dated 3/13/1979). The letter states that off-chemistry conditions were discovered in a reactor vessel surveillance specimen for the CR-3 plant, but it is very unlikely that other similar conditions exist in any reactor pressure vessel welds. By letter to the NRC dated 5/29/79, WVA endorsed these conclusions relative to the BLN reactor pressure vessels. No further action is required.

Revision 0 Page 5 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB.78-13 Failures in Source Heads Kay Ray Gauge NA Does not apply to power reactors Models 7050, 7050B, 7051, 7051B, 7060, 7060B, 7061 and 7061B IEB 78-14 Deterioration of Buna-N Components in ASCO NA BWR Solenoids IEB 79-01 Environmental Qualification of Class 1E Open Implementation of the EQ Program will address this Bulletin.

Equipment IEB 79-02*

Pipe Support Base Plate Designs Using Open Implementation of a piping and support design and analysis program will Concrete Expansion Anchor Bolts address this bulletin.

IEB 79-03 Longitudinal Weld Defects in ASME SA-312 Closed No SA-312 or A-312 Type 300 Series fusion weld piping was used at BLN, Type 304 SS Pipe Spools Fabricated by as stated in the 07/02/81 TVA letter. NRC closed this IEB in IR 438/439/80-Youngstown Welding & Engineering 2.

IEB 79-04 Incorrect Weights for Swing Check Valves Closed Per TVA response to IEB 79-04 (5/31/79), no 3, 4, or 6 inch Velan check Manufactured by Velan Engineering valves are installed at BLN nor were they scheduled for installation in any seismic Category 1 piping system. NRC closed this IEB in IR 438/439/80-2.

IEB 79-05 Nuclear Incident at TMI Open TVA will review the TMI event to assess the adequacy of BLN's safety systems to sustain cold shutdown. BLN operating, maintenance and test procedures will address items presented in the IEB based upon procedures and guidelines developed for B&W plants post-TMI. Also, see I _TMI II.K.1.

IEB 79-06 Review of Operational Errors and System NA Not addressed to B&W plants.

Misalignments Identified During the Three Mile Island Incident IEB 79-07 Seismic Stress Analysis of Safety-Related Closed Per the TVA response to IEB 79-07 in 5/31/79 letter, the seismic analysis Piping performed for BLN was free from the deficiencies summarized in this IEB.

NRC closed this IEB in IR 438/439/79-20.

IEB 79-08 Events Relevant to BWRs Identified During NA BWR TMI Incident Revision 0 Page 6 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 79-09 Failure of GE Type AK-2 Circuit Breaker in Open TVA letter dated 6/20/79 indicated that the subject circuit breakers were Safety Related Systems used in the CRD Control System and outlined a preventative maintenance program consistent with the IEB requirements. NRC closed this item in IR 438/439/79-20 dated 8/31/79. If these circuit breakers are still intended for use at BLN, TVA will confirm that the maintenance program addresses the requirements of IEB 79-09, that the recommendations of IEC 81-12 regarding surveillance test procedures are incorporated, and that any additional actions required in IEB 83-04 are addressed.

IEB 79-10 Requalification Training Program Statistics NA Applicable only to operating plants.

IEB 79-11 Faulty Overcurrent Trip Device in Circuit Closed TVA letter dated 7/20/79 stated that "none of the DB 50 and DB 75 circuit Breakers for Engineering Safety Systems breakers with over-current trip devices have been used or are planned for use at BLN. NRC closed this item in IR 438/439/79-20 dated 8/31/79.

IEB 79-12 Short Period Scrams at BWR Facilities NA BWR IEB 79-13*

Cracking in Feedwater Piping Open TVA will determine if potential for feedwater pipe cracking exists based on the BLN configuration and, if so, perform appropriate inspections.

IEB 79-14 Seismic Analysis for As-Built Safety-Related Open See IEB 79-02.

Piping Systems IEB 79-15 Deep Draft Pump Deficiencies Open TVA letters dated 9/10/79 and 1/24/92 respond to this IEB. Action items 1-3 were addressed describing the deep draft pumps at BLN. Items 4-6 applied to plants in operation regarding observation, inspection, testing, and preventative maintenance information. In order to respond to the parts of Item 4 that will be applicable to BLN and to have the appropriate information available for inspection at the site, TVA will:

1) Develop appropriate design specifications for BLN's ERCW deep draft pumps

2) Develop appropriate Operational, Maintenance and Testing procedures to ensure and verify these pumps can reliably continue to meet their safety related functions

3) Ensure the information required by this bulletin is being maintained and is readily available for inspection by NRC

4) Validate through operation and testing that required design specifications for these pumps will continue to be met.

IEB 79-16 Vital Area Access Controls Open Will be addressed by site security plan.

Revision 0 Page 7 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 79-17 Pipe Cracks in Stagnant Borated Water NA OL @ time Systems at PWR Plants IEB 79-18 Audibility Problems Encountered on NA OL @ time Evacuation of Personnel from High-Noise Areas IEB 79-19 Packaging of Low-Level Radioactive Waste NA OL @ time.

for Transport and Burial IEB 79-20 Packaging, Transport and Burial of Low-Level NA OL @ time Radioactive Waste IEB 79-21 Temperature Effects on Level Measurements Open TVA will evaluate the impact of accident temperatures on liquid level measuring systems in containment to ensure all safety and control setpoints derived from level signals initiate the actions required. Corrective actions, if required, may include insulating the measuring system reference legs or crediting other protection system features in the applicable analyses.

IEB 79-22 Possible Leakage of Tubes of Tritium Gas NA Does not apply to power reactors.

Used in Time Pieces for Luminosity IEB 79-23 Potential Failure of Emergency Diesel Open TVA response dated 10/29/79 for BLN satisfactorily addressed this IEB.

Generator Field Exciter Transformer NRC acceptance for closeout of the IEB is dated 01/17/90.TVA will confirm that neither a direct connection nor a connection through a common ground exists between the excitation power transformer neutral and the generator neutral on the diesel generator. Also, preoperational test procedures will address sustained full load testing.

IEB 79-24*

Frozen Lines Open Safety-related instrument sensing lines and sample lines will be evaluated for heat tracing following routing and installation.

IEB 79-25 Failures of W BFD Relays in Safety Related Closed In a letter from TVA to NRC dated 1/4/80, it was stated that "TVA's Systems investigation revealed that none of the Westinghouse BFD or NBFD relays are in use, or are planned for use, in safety-related systems at BLN." NRC closed this bulletin in IR 438,439/80-02 dated 2/6/80.

IEB 79-26 &

Boron Loss from BWR Control Blades NA BWR R1 Revision 0 Page 8 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 79-27 Loss of Non-Class 1E I & C Power System Open TVA will create shutdown logic diagrams to reach cold shutdown (includes Bus During Operation functions, actions and systems required). Alarms and indications for loss of bus power will be documented. TVA will develop electrical load lists or single line drawings for buses that include lists of loads by equipment tag number, and will develop Abnormal Operating Procedures to reach cold shutdown, including loss of buses supplying power to I&C systems, including IEB items 2a-2c.

IEB 79-28 Possible Malfunction of NAMCO Model EA180 Closed TVA stated in a 3/28/80 letter that no NAMCO switches with the referenced Limit Switches at Elevated Temperatures date code were identified in safety related components at BLN. NRC closed this IEB in IR 438/439/80-08.

IEB 80-01 Operability of ADS Valve Pneumatic Supply NA BWR IEB 80-02 Inadequate QA for Nuclear Supplied NA BWR Equipment IEB 80-03*

Loss of Charcoal from Standard Type II, 2 Open TVA letter to NRC dated 3/21/80 stated that none of the adsorber beds Inch Tray Adsorber Cells were found to be defective. NRC inspection dated 5/28/80 confirmed the same.TVA will verify through visual inspection that adsorber beds to be used in the ESF filtration systems and normal ventilation exhaust filtration systems in which radioactive removal efficiency is used in determining compliance with 10CFR50 Appendix I will perform their intended functions.

IEB 80-04 Analysis of a PWR Main Steam Line Rupture Open BLN incorporates safety grade MFW and main steam isolation. The with Continued Feedwater Addition ESFAS system also includes Feed Only Good Generator (FOGG) logic to prevent feeding a failed SG during accident conditions. The logic prevents excessive overcooling and excessive mass and energy releases. The new digital ESFAS will include this feature.

IEB 80-05*

Vacuum Condition Resulting in Damage to Open For BLN, tanks which may experience vacuum conditions will be supplied Chemical Volume Control System Holdup with both a relief valve and a vacuum breaker to preclude tank Tanks overpressure or tank collapse. The valves will be included in the plant surveillance program.

IEB 80-06 Engineered Safety Features Reset Control Open The design of BLN component controls will reflect the requirement that deliberate operator action will be necessary to reposition ESF components after reset of the actuation signal and completion of protective actions.

IEB 80-07 BWR Jet Pump Assembly Failure NA BWR IEB 80-08*

Examination of Containment Liner Penetration Open TVA will review response for BLN in TVA 7/8/80 letter and confirm it is still Welds valid, and ensure that all identified welds have been inspected, radiographed or ultrasonically examined, and repaired, if needed.

Revision 0 Page 9 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 80-09 Hydramotor Actuator Deficiencies Closed TVA determined that BLN had the subject actuators and subsequently satisfactorily responded to the IEB required actions. NRC letter dated 7/11/89 (NUREG/CR-5291) confirms the item as closed.

IEB 80-10*

Contamination of Non-radioactive System and Open TVA will confirm that the systems and designs used for BLN have Resulting Potential for Unmonitored, considered the types of problems identified in the IEB and have Uncontrolled Release of Radioactivity to implemented the necessary measures to preclude or detect the problems, Environment should they arise.

IEB 80-11 Masonry Wall Design Open TVA will complete response to bulletin and identify and evaluate all masonry walls whose failure could affect piping or equipment in safety related systems.

IEB 80-12 Decay Heat Removal System Operability Open TVA will assure that all reasonable means have been taken to preclude the loss of DHR capability due to common mode failure during all modes of operation, and develop operating and maintenance procedures that assure system availability and avoid cross-train outages.

IEB 80-13 Cracking in Core Spray Spargers NA BWR IEB 80-14 Degradation of Scram Discharge Volume NA BWR Capability IEB 80-15 Possible Loss of Emergency Notification Open The BLN ENS will be designed to meet the applicable requirements for System with Loss of Offsite Power power redundancy.

IEB 80-16 Potential Misapplication of Rosemount Models Closed TVA letter dated 8/29/80 stated that no situation existed wherein the 1151 and 1152 Pressure Transmitters With anomalous output could occur at BLN. NRC IR 50-438/81-06 and 50-Either "A" or "D" Output Codes 439/81-06 dated 3/6/81 closed this bulletin.

IEB 80-17 Failure of 76 of 185 Control Rods to Fully NA BWR Insert During a Scram at a BWR IEB 80-18" Maintenance of Adequate Minimum Flow Thru Open TVA will review the requirements of IEB 80-18 and if changes to the Centrifugal Charging Pumps Following a system design, instrumentation and/or procedures are required, they will Secondary Side High Energy Rupture be incorporated in the BLN design.

IEB 80-19 &

Mercury-Wetted Matrix Relay in Reactor Closed NUREG/CR-4933 stated that BLN did not use subject relays and bulletin R1 Protective Systems was closed for BLN. Additionally, the new Areva digital architecture will replace the original RPS systems and the new RPS equipment will not utilize mercury wetted relays.

IEB 80-20 Failure of W Type W-2 Spring Return to Open TVA will determine the present status of the BLN W-2 switches and ensure Neutral Control Switches that the W-2 switches are modified or replaced as outlined in TVA's letter to NRC dated 11/9/81.

Revision 0 Page 10 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 80-21 Valve Yokes Supplied by Malcolm Foundry Closed TVA stated in a letter dated 5/6/81 that no valve parts made by Malcolm Co.

Foundry were used or planned for use at BLN. NRC closed this IEB in IR 438/439/81-23 IEB 80-22 Automation Industries, Model 200-520-008 NA Does not apply to power reactors Sealed-Source Connectors IEB 80-23 Failures of Solenoid Valves Manufactured by Closed TVA stated in a letter dated 3/31/81 that BLN does not have the Valcor Valcor Eng. Corp valves with the subject P/Ns. NRC closed this IEB in IR 438/439/81-15.

IEB 80-24 Prevention of Damage Due to Water Leakage Open TVA will evaluate all open cooling water systems present inside Inside Containment containment, and ensure the design and associated instrumentation and procedures are in place to detect and prevent water leakage inside containment.

IEB 80-25 Operating Problems with Target Rock SR NA BWR Valves at BWRs IEB 81-01 Surveillance of Mechanical Snubbers NA BLN is not listed among plants to provide response to this IEB.

IEB 81-02 &

Failure of Gate Type Valves to Close Against Complete TVA response letter dated 4/13/82 addressed this IEB for BLN.

$1 Differential Pressure IEB 81-03 Flow Blockage to Cooling Water by Asiatic Open WVA provided information to NRC in letters dated 7/8/81, 02/17/83 and Clams and Mussels 7/23/84 and stated that TVA would continue to inspect HPFP and ERCW systems for evidence of clam infestation during the construction phase and evaluate the clam impact on the ERCW system, if it had not been in service for more than 30 days. Due to at least parts of the raw water systems being filled with water and/or not in service for several years, clam infestation could be or become a problem at BLN. Based on this, BLN will conduct inspections, flushing, and testing, as required, and develop and implement a chlorination program for BLN which addresses the I

requirements of this IEB and TVA Corporate procedures.

IEB 82-01 Alterations of Radiographs of Welds in Piping NA Not applicable to BLN per absence of BLN in Table 1 of IEB 82-01.

Subassemblies IEB 82-02 Degradation of Threaded Fasteners in the Open TVA will implement a program at BLN to minimize fastener degradation, Reactor Coolant Pressure Boundary of PWR incorporating industry best practices for bolting procedures to prevent Plants leakage, non-use of lubricants containing molybdenum sulfide, and a walkdown of borated water systems during each refueling outage. During planned walkdowns TVA will identify fasteners fabricated of susceptible I

I_

materials and consider replacement with less susceptible material types.

Revision 0 Page 11 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 82-03 Stress Corrosion Cracking in Thick-Wall, NA BWR Large Diameter, Stainless Steel, Recirculation System Piping at BWR Plants IEB 82-04 Deficiencies in Primary Containment Electrical Closed TVA letter to the NRC, dated 01/24/1983, reported that no TVA plants, Penetration Assemblies including BLN, had purchased or used any Bunker Ramo Company electrical penetration assemblies. NRC closed this bulletin in IR 50-438/83-08 and 50-439/83-08 dated 4/14/83.

IEB 83-01 Failure of Trip Breakers (Westinghouse DB-Complete The BLN designwill not utilize Westinghouse DB-50 Reactor Trip Breakers

50) to Open on Automatic Trip Signal in its RPS.

IEB 83-02 Stress Corrosion Cracking in Large-Diameter NA BWR Stainless Steel Recirculation System Piping at BWR Plants IEB 83-03 Check Valve Failures in Raw Water Cooling Open Will be addressed by IST program.

Systems of Diesel Generators IEB 83-04 Failure of the Undervoltage Trip Function of Open See response to IEB 79-09.

Reactor Trip Breakers IEB 83-05 ASME Nuclear Code Pumps and Spare Parts Open TVA letter dated 9/7/83 stated that no HTPC pumps had been procured for Manufactured by Hayward Tyler Pump Co use in BLN, however, six sets of wear rings were purchased for use on both units 1 and 2 CCW pumps. The wear rings will either be replaced or the actions required in IEB 83-05 will be accomplished.

IEB 83-06 Nonconforming Material Supplied by Tube-Closed Final TVA response on 2/2/84 stated that all corrective action, including Line removal and replacement of suspect fittings, will be completed by December 1984. NRC Inspection report 84-22, dated 10/31/84 stated that NRC closed this IE Bulletin after reviewing supporting documentation and observing representative samples of work to verify that the actions identified in the TVA letter had been completed.

IEB 83-07 Apparently Fraudulent Products Sold by Ray Closed IE Bulletin 83-07 was closed in NRC Inspection report (IR) 438,439/84-22 Miller, Inc based on WVA letter dated 3/22/84, review of supporting documentation, and observing representative samples of work to verify that the actions identified in the letter had been completed.

IEB 83-08 Electrical Circuit Breakers With Undervoltage Closed TVA letter dated 03/29/1984 informed NRC that the required actions for Trip in Safety Related Applications other than BLN were complete. The letter stated that breakers with an undervoltage the Reactor Trip System trip attachment feature have not been specified for use on safety-related systems exclusive of the reactor trip system. The NRC addressed closure I

I_ of this bulletin in Inspection Report 438/439 86-04.

Revision 0 Page 12 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 84-01 Cracks in BWR Mark 1 Containment Vent NA BWR Headers IEB 84-02 Failure of GE Type HFA Relays In Use In Closed IVA letter dated 07/10/1984 informed NRC that the actions for BLN had Class 1 E Safety Systems been completed. The letter stated that per B&W letter D-4791 dated 10/6/83, no GE type HFA relays have been supplied or specified by B&W for use in any of the NSSS 1 E safety systems supplied to BLN. The NRC addressed closure of this bulletin in Inspection Report 438/439 86-04.

IEB 84-03*

Refueling Cavity Water Seal Open In a response to the NRC dated 12/26/1984, TVA documented the results of an evaluation of the potential for and consequences of a refueling cavity water seal failure for BLN. The potential for gross seal failure was concluded to be very small and expected leak rates were well within make-up capabilities. When gross failure of the seal was assumed, TVA's conclusion was that it could be tolerated based in part on specific operator actions. TVA will ensure that the final refueling cavity water seal design is consistent with this conclusion (if any changes are made), and ensure that any necessary operator actions are incorporated into written refueling procedures as stated in the referenced response.

IEB 85-01" Steam Binding of Auxiliary Feedwater Pumps Open In its10/16/86 and 6/3/88 letters, TVA stated that auxiliary feedwater (AFW) pump discharge temperature would be monitored at BLN and the modifications and/or procedural requirements necessary to accomplish this would be incorporated into the BLN design. This IEB is linked to GL 88-03 which the NRC closed in NUREG/CR 5298. TVA will confirm that the equipment, instrumentation and procedures required to prevent AFW pump steam binding remain valid and are incorporated into the BLN design.

IEB 85-02 Undervoltage Trip Attachment of W DB-50 Open The BLN design will not utilize Westinghouse DB-50 Reactor Trip Breakers Type Reactor Trip Breakers in its RPS. WVA will ensure that any breakers that are used will be equipped with automatic shunt trips prior to startup.

IEB 85-03 Motor Operated Valve Common Mode Closed GL 89-10 supersedes the recommendations of this IEB and its Failures During Plant Transients due to Supplement. TVA withdrew prior commitments made in responses to this Improper Switch Settings bulletin and committed to respond to GL 89-10 should construction activities resume. See GL 89-10.

IEB 86-01 Minimum Flow Logic Problems That Could NA BWR Disable RHR Pumps IEB 86-02 Static "0" Ring Differential Pressure Switches Complete WVA response on 11/20/86 stated that no such switches are installed or currently planned for installation at BLN. Therefore, no additional actions are required.

Revision 0 Page 13 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 86-03 Potential Failure of Multiple ECCS Pumps Due Closed TVA response on 11/14/86 states "In summary, the single failure to Single Failure of Air-Operated Valve in vulnerability discussed in the subject bulletin does not exist at BLN." NRC Minimum Flow Recirculation Line closed this IEB in IR 438/439/86-09.

IEB 86-04 Defective Teletherapy Timer That May Not NA Does not apply to power reactors Terminate Treatment Dose IEB 87-01 Thinning of Pipe Walls in Nuclear Power Closed Closed by GL 89-08.

Plants IEB 87-02 Fastener Testing to Determine Conformance Open In a letter dated August 18, 1989, the NRC stated that, "We conclude that with Applicable Material Specifications you have satisfactorily addressed the requirements for responding to NRC Bulletin 87-02. This closes out our review of your responses to the Bulletin." No follow up requirements or additional field inspections were required by the NRC inspector.

Although the NRC closed this bulletin, based on a review and the amount of time since this issue was addressed, a re-evaluation of previous actions taken needs to be performed to ensure that BLN is presently complying with IEB 87-02. Any necessary additional actions will be identified and implemented to ensure compliance.

IEB 88-01" Defects in W Circuit Breakers Open TVA will include the inspections required by IEB 88-01 in the plan for refurbishment of all applicable Class 1 E Westinghouse type DS/DSL circuit breakers. Alternately, the pole shafts may be replaced as part of the breaker refurbishment.

IEB 88-02 Rapidly Propagating Fatigue Cracks in Steam NA NA for B&W plants. Applicable to Westinghouse SGs and information only Generator Tubes for CE plants.

IEB 88-03 Inadequate Latch Engagement in HFA Type Complete TVA letter dated 7/6/88 states that "BLN does not have GE HFA-type Latching Relays Manufactured by General latching relays" as described in this IEB. Also, see response to IEB 84-02.

Electric (GE) Company IEB 88-04*

Potential Safety-Related Pump Loss Open TVA will ensure that the BLN design incorporates mechanisms that I

I Iminimize safety-related pump loss due to pump to pump interaction.

Revision 0 Page 14 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 88-05 Nonconforming Materials Supplied by Piping Open TVA will:

Supplies, Inc. and West Jersey Manufacturing

1) Review purchasing records to determine if any ASME Code or ASTM Company materials (flanges and fittings only) were supplied to BLN by PSI, WJM, or CLM (see IEB 88-05 Supplement 2) and, if so,

2) Ensure compliance with appropriate requirements by document verification, replacement of components or in-situ testing, and maintain documentation of the specific actions taken.

3) Quarantine non-conforming materials.

4) Report results of the records review, testing, and analysis to NRC prior to fuel load.

IEB 88-06 Actions to be Taken for the Transfer of Model NA Does not apply to power reactors No. SPEC 2-T Radiographic Exposure Device IEB 88-07 Power Oscillations in BWRs NA BWR IEB 88-08*

Thermal Stresses in Piping Connected to Open TVA will review systems connected to the RCS to determine whether Reactor Cooling Systems unisolable sections of piping can be subjected to stresses from temperature stratification that were not evaluated in the design of the piping. TVA will perform NDE and evaluations of critical areas of these sections, as specified in the bulletin, and plan and implement a program to provide continuing assurance that such sections of all piping connected to the RCS will not be subjected to stresses that could cause fatigue failure during the remaining life of the unit.

IEB 88-09 Thimble Tube Thinning in Westinghouse NA Not applicable to B&W plants.

Reactors IEB 88-10 Nonconforming Molded-Case Circuit Breakers Open TVA will ensure that all molded case circuit breakers used in safety related applications meet the 10 CFR 50 App. B requirements or have an acceptable dedication process with verifiable traceability back to the circuit breaker manufacturer.

IEB 88-11" Pressurizer Surge Line Thermal Stratification Open WVA will review the analysis of the pressurizer surge line to ensure that the stresses associated with thermal stratification are properly considered and that the BLN design meets the applicable design codes and regulatory standards.

IEB 89-01 Failure of Westinghouse Steam Generator Complete BLN steam generators are being replaced, and Alloy 600TT material is no Tube Mechanical Plugs I

longer used for tube plugs.

Revision 0 Page 15 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 89-02 Stress Corrosion Cracking of High-Hardness Open TVA will determine during walkdowns if any Anchor Darling Model S350W Type 410 Stainless Steel Preloaded Bolting in Swing Check Valves or valves of similar design and material are installed Anchor Darling Model S350W Swing Check at BLN. If so, TVA will disassemble and replace internal bolting with Valves or Valves of Similar Nature material of hardness specified in the IEB or, alternatively, identify the valves for replacement.

IEB 89-03 Potential Loss of Required Shutdown Margin Open TVA will assure that intermediate fuel assembly configurations during During Refueling Operations refueling operations are identified and evaluated to maintain sufficient boron concentration that results in a minimum shutdown margin of approximately 5%. Fuel loading procedures that allow only those intermediate fuel configurations that do not violate the minimum allowable shutdown margin will be developed, and the refueling operations staff will receive training on these procedures.

IEB 90-01 Loss of Fill-Oil in Transmitters Manufactured Open TVA will replace transmitters in BLN and confirm that all new transmitters by Rosemount to be installed were manufactured after 7/11/89.

IEB 90-02 Loss of Thermal Margin Caused by Channel NA BWR Box Bow IEB 91-01 Reporting Loss of Criticality Safety Controls NA Does not apply to power reactor IEB 92-01 Failure of Thermo-Lag 330 Fire Barrier Open Thermo-Lag electrical raceway and component fire barrier systems for System To Maintain Cabling in Wide Cable separating safe-shutdown functions within the same fire area will be tested Trays and Small Conduits Free from Fire and qualified in accordance with the guidance contained in R.G. 1.189.

Damage & to Perform its Specified Fire Also, see response to GL 92-08.

Endurance Function IEB 92-02 Safety Concerns Related to "End of Life" of NA Does not apply to power reactors Aging Theratronics Teletherapy Units IEB 92-03 Release of Patients after Brachytherapy NA Does not apply to power reactors IEB 93-01 Release of Patients After Brachytherapy NA Does not apply to power reactors Treatment With Remote Afterloading Devices IEB 93-02 Debris Plugging of Emergency Core Cooling NA BWR Suction Strainers IEB 93-03 Resolution of Issues Related to Reactor NA BWR Vessel Water Level Instrumentation in BWRs IEB 94-01 Potential Fuel Pool Draindown Caused by NA Addressed to holders of licenses for power reactors that are permanently I Inadequate Maintenance Practices at Dresden I shut down with spent fuel in the pool.

Revision 0 Page 16 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 94-02 Corrosion Problems in Certain Stainless Steel NA Does not apply to power reactors Packagings Used to Transport Uranium Hexafluoride IEB 95-01 Quality Assurance Program for Transportation NA Does not apply to power reactors of Radioactive Material IEB 95-02 Unexpected Clogging of a Residual Heat NA BWR Removal (RHR) Pump Strainer While Operating In Suppression Pool Cooling Mode IEB 96-01 Control Rod Insertion Problems (PWR)

NA For information only for B&W and CE plants.

IEB 96-02 Movement of Heavy Loads over Spent Fuel, Open The BLN design requirements for the Reactor Building Polar and the Spent over Fuel in the Reactor, or over Safety-Fuel Building cranes will incorporate the requirements of NUREG-0612 Related Equipment and NUREG-0554.

IEB 96-03 Potential Plugging of ECCS Suction Strainers NA BWR by Debris in BWRs IEB 96-04 Chemical, Galvanic or Other Reactions in NA Information Spent Fuel Storage and Transportation Casks IEB 97-01 Potential for Erroneous Calibration, Dose NA Does not apply to power reactors Rate, or Radiation Exposure Measurements with Certain Victoreen Model 530 and 531SI Electrometers, Dose Meters IEB 97-02 Puncture Testing of Shipping Packages Under NA Does not apply to power reactors 10 CFR Part 71 IEB 01-01 Circumferential Cracking of Reactor Pressure Open The BLN project plans to mitigate all Alloy 600 locations. The completion Vessel (RPV) Head Penetration Nozzles of the BLN Alloy 600 mitigation program in combination with the plants inspection and testing program for RVH penetrations will demonstrate that RVH integrity is maintained. TVA will confirm that the BLN Alloy 600 mitigation program and inspection/testing programs address the concerns discussed in the bulletin.

IEB 02-01 RPV Head Degradation and Reactor Coolant Open See IEB 01-01. TVA will confirm that the completion of the Alloy 600 Pressure Boundary Integrity program, including an inspection and testing program for susceptible I_

locations, will demonstrate that RCPB integrity is maintained.

IEB 02-02 RPV Head and Vessel Head Penetration Open See IEB 01-01 Nozzle Inspection Program IEB 03-01 Potential Impact of Debris Blockage on Closed See USI A-43, Containment Emergency Sump Performance.

Emergency Sump Recirculation Revision 0 Page 17 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 03-02 Leakage from RPV Lower Head Penetrations Open The mitigation strategy for RPV lower head penetrations will be determined and Reactor Coolant Pressure Boundary and implemented as part of the Alloy 600 program. The appropriate in-Integrity service inspection program will be defined considering the mitigation strategy that is implemented and the resulting susceptibility to PWSCC. At a minimum BLN-1 will perform a bare metal VT-2 examination of the RPV lower head penetrations during the first refueling outage and subsequent outages until a change to the ASME Code or a regulatory action justifies a change in frequency.

IEB 03-03 Potentially Deficient 1-inch Valves for Uranium NA Does not apply to power reactors Hexaflouride Cylinders IEB 03-04 Rebaselining of Data in the Nuclear NA No special nuclear material is currently on site nor will there be any on site Management and Safeguards System for several years.

IEB 04-01 Inspection of Alloy 82/182/600 Materials Used Open The BLN project will describe the configuration of and materials used in in the Fabrication of Pressurizer Penetrations pressurizer penetrations and steam space piping connections at BLN. The and Steam Space Piping Connections at inspection program planned for BLN and potential corrective actions will PWRs also be described.

IEB 05-01 Material Control and Accounting of Reactors NA NA for CP holder.

and Spent Fuel Storage Facilities IEB 05-02 Emergency Preparedness and Response NA BLN will not have an OL for several years.

Actions for Security Based Events IEB 07-01 Security Officer Attentiveness Open The BLN Security Plan will address the actions requested in IEB 07-01 concerning Security Officer Attentiveness.

CR 76-01 Crane Hoist Control Circuit Complete See TVA response, 10/29/1976 and IEB 76-07.

CR 76-02 Relay Failures - Westinghouse BF (ac) and Complete The subject Westinghouse relays were not used in BLN Class IE circuits.

BFD (dc) Relays See TVA response, 11/22/1976.

CR 76-03 Radiation Exposures in Reactor Cavities NA Information CR 76-04 Neutron Monitor and Flow Bypass Switch NA BWR Malfunctions CR 76-05 Hydraulic Shock and Sway Suppressors -

Complete No Grinnell shock suppressors or sway braces have been or will be Maintenance of Bleed and Lock-up Velocities installed at BLN. See TVA response, 1/7/1977 on ITT Grinnell Models...

CR 76-06 Stress Corrosion Cracks in Stagnant, Low NA OL at time Pressure Stainless Piping Containing Boric Acid Solution at PWRs Revision 0 Page 18 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure CR 76-07 Inadequate Performance by Reactor NA OL at time Operating and Support Staff Members CR 77-01 Malfunctions of Limitorque Valve Operators NA Information CR 77-02 Potential Heavy Spring Flooding (OL)

NA OL at time CR 77-02a Potential Heavy Spring Flooding (CP)

NA Information CR 77-03 Fire Inside a Motor Control Center NA Information CR 77-04 Inadequate Lock Assemblies NA Information CR 77-05 Fluid Entrapment in Valve Bonnets NA Information CR 77-06 Effects of Hydraulic Fluid on Electrical Cables NA Information CR 77-07 Short Period During Reactor Startup NA BWR CR 77-08 Failure of Feedwater Sample Probe NA OL at time CR 77-09 Improper Fuse Coordination in BWR Standby NA BWR Liquid Control System Control Circuits CR 77-10 Vacuum Conditions Resulting in Damage to NA OL at time Liquid Process Tanks CR 77-11 Leakage of Containment Isolation Valves with NA Information Resilient Seats CR 77-12 Dropped Fuel Assemblies at BWR Facilities NA BWR CR 77-13 Reactor Safety Signals Negated During NA Information Testing CR 77-14 Separation of Contaminated Water Systems NA Information from Noncontaminated Plant Systems CR 77-15 Degradation of Fuel Oil Flow to the NA Information Emergency Diesel Generator CR 77-16 Emergency Diesel Generator Electrical Trip NA Information Lock-Out Features CR 78-01 Loss of Well Logging Source NA Does not apply to power reactors CR 78-02 Proper Lubricating Oil for Terry Turbines NA Information CR 78-03 Packaging Greater than Type A Quantities of NA Does not apply to power reactors Low Specific Activity Radioactive Material for Transport CR 78-04 Installation Errors That Could Prevent Closing NA Information of Fire Doors CR 78-05 Inadvertent Safety Injection During Cooldown NA Information Revision 0 Page 19 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure CR 78-06 Potential Common Mode Flooding of ECCS NA Information Equipment Rooms at BWR Facilities CR 78-07 Damaged Components of a Bergen-Paterson NA Information Series 25000 Hydraulic Test Stand CR 78-08 Environmental Qualification of Safety-Related NA Information Electrical Equipment at Nuclear Power Plants CR 78-09 Arcing of General Electric Company Size 2 NA Information Contactors CR 78-10 Control of Sealed Sources in Radiation NA Does not apply to power reactors Therapy CR 78-11 Recirculation MG Set Overspeed Stops NA BWR CR 78-12 HPCI Turbine Control Valve Lift Rod Bending NA BWR CR 78-13 Inoperability of Service Water Pumps NA Information CR 78-14 HPCI Turbine Reversing Chamber Hold Down NA BWR Bolting CR 78-15 Tilting Disc Check Valves Fail to Close with NA Information Gravity in Vertical Position CR 78-16 Limitorque Valve Actuators NA Information CR 78-17 Inadequate Guard Training/Qualification and NA Information Falsified Training Records CR 78-18 UL Fire Test NA Information CR 78-19 Manual Override (Bypass) of Safety System NA Information Actuation Signals CR 79-01 Administration of Unauthorized Byproduct NA Does not apply to power reactors Material to Humans CR 79-02 Failure of 120 Volt Vital AC Power Supplies NA Information CR 79-03 Inadequate Guard Training-Qualification and NA Information Falsified Training Records CR 79-04 Loose Locking Nut on Limitorque Valve NA Information Operators CR 79-05 Moisture Leakage in Stranded Wire NA Information Conductors CR 79-06 Failure to Use Syringe and Bottle Shields in NA Does not apply to power reactors Nuclear Medicine Revision 0 Page 20 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure CR 79-07 Unexpected Speed Increase of Reactor NA BWR Recirculation MG Set Resulted in Reactor Power Increase CR 79-08 Attempted Extortion - Low Enriched Uranium NA Fuel facilities and operating reactors at the time the item was issued CR 79-09 Occurrences of Split or Punctured Regulator NA Information Diaphragms in Certain Self Contained Breathing Apparatus CR 79-10 Pipefittings Manufactured from Unacceptable NA Information Material CR 79-11 Design/Construction Interface Problem NA Information CR 79-12 Potential Diesel Generator Turbocharger NA Information Problem CR 79-13 Replacement of Diesel Fire Pump Starting NA Information Contactors CR 79-14 Unauthorized Procurement and Distribution of NA Does not apply to power reactors XE-1 33 CR 79-15 Bursting of High Pressure Hose and NA OL at time Malfunction of Relief Valve O-Ring in Certain Self-Contained Breathing Apparatus CR 79-16 Excessive Radiation Exposures to Members NA Does not apply to power reactors of the General Public and a Radiographer CR 79-17 Contact Problem in SB-12 Switches on NA Information General Electric Company Metalclad Circuit Breakers CR 79-18 Proper Installation of Target Rock Safety-NA BWR Relief Valves CR 79-19 Loose Locking Devices on Ingersoll-Rand NA Information Pumps CR 79-20 Failure of GTE Sylvania Relay Type PM NA Information Bulletin 7305 Catalog 5U12-11-AC with a 120V AC Coil CR 79-21 Prevention of Unplanned Releases of NA Information Radioactivity CR 79-22 Stroke Times for Power Operated Relief NA Information Valves Revision 0 Page 21 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure CR 79-23 Motor Starters and Contactors Failed to Complete Gould replaced carrier assemblies on starters at Bellefonte on 11/26/1979.

Operate The starters with replaced carriers are acceptable.

CR 79-24 Proper Installation and Calibration of Core NA BWR Spray Pipe Break Detection Equipment on BWRs CR 79-25 Shock Arrestor Strut Assembly Interference NA Information CR 80-01 Service Advice for GE Induction Disc Relays NA Information CR 80-02 Nuclear Power Plant Staff Work Hours NA Information CR 80-03 Protection from Toxic Gas Hazards Information CR 80-04 Securing of Threaded Locking Devices on NA Information Safety-Related Equipment CR 80-05 Emergency Diesel-Generator Lubricating Oil NA Information Addition and Onsite Supply CR 80-06 Control and Accountability Systems for NA Does not apply to power reactors Implant Therapy Sources CR 80-07 Problems with HPCI Turbine Oil System NA BWR CR 80-08 BWR Technical Specification Inconsistency -

NA BWR RPS Response Time CR 80-09 Problems with Plant Internal Communications NA Information Systems CR 80-10 Failure to Maintain Environmental NA Qualification of Equipment CR 80-11 Emergency Diesel Generator Lube Oil Cooler NA Information Failures CR 80-12 Valve-Shaft-to-Actuator Key May Fall Out of NA Information Place when Mounted Below Horizontal Axis CR 80-13 Grid Strap Damage in Westinghouse Fuel NA Information Assemblies CR 80-14 Radioactive Contamination of Plant NA Information Demineralized Water System and Resultant Internal Contamination of Personnel CR 80-15 Loss of Reactor Coolant Pump Cooling and NA Information Natural Circulation Cooldown Revision 0 Page 22 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure CR 80-16 Operational Deficiencies in Rosemount Model NA Information 510DU Trip Units and Model 1152 Pressure Transmitters CR 80-17 Fuel Pin Damage Due to Water Jet from Baffle NA Information Plate Corner CR 80-18 10 CFR 50.59 Safety Evaluations for Changes NA Information to Radioactive Waste Treatment Systems CR 80-19 Noncompliance with License Requirements for NA Does not apply to power reactors Medical Licensees CR 80-20 Changes in Safe-Slab Tank Dimensions NA Information CR 80-21 Regulation of Refueling Crews NA Information CR 80-22 Confirmation of Employee Qualifications NA Information CR 80-23 Potential Defects in Beloit Power Systems NA Information Emergency Generators CR 80-24 AECL Teletherapy Unit Malfunction NA Does not apply to power reactors CR 80-25 Case Histories of Radiography Events NA Does not apply to power reactors CR 81-01 Design Problems Involving Indicating NA Information Pushbutton Switches Manufactured by Honeywell Incorporated CR 81-02 Performance of NRC-Licensed Individuals NA OL at time while on Duty CR 81-03 Inoperable Seismic Monitoring Instrumentation NA Information CR 81-04 The Role of Shift Technical Advisors and NA Information Importance of Reporting Operational Events CR 81-05 Self-Aligning Rod End Bushings for Pipe NA Information Supports CR 81-06 Potential Deficiency Affecting Certain Foxboro NA Information 10 to 50 Milliampere Transmitters CR 81-07 Control of Radioactively Contaminated NA Information Material CR 81-08 Foundation Materials NA Information CR 81-09 Containment Effluent Water that Bypasses NA Information Radioactivity Monitor CR 81-10 Steam Voiding in the Reactor Coolant System NA OL at time During Decay Heat Removal Cooldown Revision 0 Page 23 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure CR 81-11 Inadequate Decay Heat Removal During NA BWR Reactor Shutdown CR 81-12 Inadequate Periodic Test Procedure of PWR NA Information Reactor Protection System CR 81-13 Torque Switch Electrical Bypass Circuit for NA Information Safeguard Service Valve Motors CR 81-14 Main Steam Isolation Valve Failures to Close NA Information CR 81-15 Unnecessary Radiation Exposures to the NA Information Public and Workers During Events Involving Thickness and Level Measuring Devices GL 77-01 Intrusion Detection Systems Handbook NA Information GL 77-02 Fire Protection Functional Responsibilities NA Information GL 77-03 Transmittal of NUREG-0321, "A Study of the NA Information Nuclear Regulatory Commission Quality Assurance Program" GL 77-04 Shipments of Contaminated Components NA Information From NRC Licensed Nuclear Power Facilities to Vendors & Service Companies GL 77-05 Nonconformity of Addresses of Items Directed NA Information to the Office of Nuclear Reactor Regulation GL 77-06 Questionnaire Related to Steam Generators NA OL @ time GL 77-07 Reliability of Standby Diesel Generator Units NA OL ( time GL 77-08 Revised Intrusion Detection Systems NA Information Handbook and Entry Control Systems Handbook GL 78-01 Correction To Letter Of 12/15/77 NA Information GL 78-02 Asymmetric Loads Background and Revised Open The issues in this Generic Letter were addressed by NUREG 0609, which Request for Additional Information identified an acceptable basis for performing and reviewing plant analyses addressing asymmetric loads. TVA plans to perform analyses and request approval to eliminate postulated large bore pipe ruptures from the design basis for BLN-1. Analyses of the remaining piping will be performed in accordance with applicable requirements and with approved methods to demonstrate that the systems are acceptable for asymmetric blowdown loads. See also the response to USI A-2.

Revision 0 Page 24 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 78-03 Request for Information on Cavity Annulus NA OL @ time Seal Ring GL 78-04 Steam Generator Operating History NA OL @ time GL 78-05 Internal Distribution Of Correspondence -

NA Information Asking For Comments On Mass Mailing System GL 78-06 This Generic Letter Was Never Issued NA GL 78-07 This Generic Letter Was Never Issued NA GL 78-08 Enclosing NUREG-0408 RE Mark I NA BWR Containments, And Granting Exemption From GDC 50 And Enclosing Sample Notice GL 78-09 Multiple Subsequent Actuations of Safety NA BWR Relief Valves Following an Isolated Event GL 78-10 Guidance On Radiological Environmental NA Information Monitoring GL 78-11 Guidance on Spent Fuel Pool Modifications NA Information GL 78-12 Notice Of Meeting Regarding "Implementation NA Information of 10 CFR 73.55 Requirements And Status Of Research..."

GL 78-13 Forwarding of NUREG-0219 (Draft 2)

NA Information GL 78-14 Transmittal Of Draft NUREG-0219 For NA Information Comment GL 78-15 Request for Information on Control of Heavy NA See GL 81-07 Loads Near Spent Fuel GL 78-16 Request For Information On Control Of Heavy NA Superseded by GL 78-17 Loads Near Spent Fuel Pools GL 78-17 Corrected Letter On Heavy Loads Over Spent NA Information Fuel GL 78-18 Corrected Letter On Heavy Loads Over Spent NA Duplicate of GL 78-17 Fuel GL 78-19 Enclosing Sandia Report SAND 77-0777, NA Information "Barrier Technology Handbook' GL 78-20 Enclosing - "A Systematic Approach To The NA Information Conceptual Design Of Physical Protection Systems For Nuclear Facilities" Revision 0 Page 25 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 78-21 Transmitting NUREG/CR-0181 Concerning NA Information Barrier & Penetration Data Needed For Physical Security System Assessment GL 78-22 Revision To Intrusion Detection Systems And NA Information Entry Control Handbooks And Nuclear Safeguards Technology Handbook GL 78-23 Manpower Requirements For Operating NA Information Reactors GL 78-24 Model Appendix I Technical Specifications NA BWR And Submittal Schedule For BWRs GL 78-25 This Generic Letter Was Never Issued NA GL 78-26 Excessive Control Rod Guide Tube Wear Open For BLN -1, TVA plans are to use all AIC vs. B4C as absorber material, hardcoat the CRA rod OD and provide a wear protection in the FA guide tubes. Full scale prototype testing is planned of the entire control rod drive line to verify performance.

GL 78-27 Forwarding of NUREG-0181 NA Information GL 78-28 Forwarding pages omitted from 07/11/78 letter NA BWR GL 78-29 Notice of PWR steam generator conference NA Information GL 78-30 Forwarding of NUREG-0219 NA Information GL 78-31 Notice of Steam Generator Conference NA Information Agenda GL 78-32 Reactor Protection System Power Supplies NA BWR GL 78-33 Meeting Schedule And Locations For NA Information Upgraded Guard Qualification GL 78-34 Reactor Vessel Atypical Weld Material Closed See IEB 78-12 GL 78-35 Regional Meetings To Discuss Upgraded NA Information Guard Qualifications GL 78-36 Cessation of Plutonium Shipments By Air NA Does not apply to power reactor Except In NRC Approved Containers GL 78-37 Revised Meeting Schedule & Locations For NA Information Upgraded Guard Qualifications GL 78-38 Forwarding Of 2 Tables Of Appendix I, Draft NA OL @ time Radiological Effluent Technical Specifications, PWR, and NUREG-0133 Revision 0 Page 26 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 78-39 Forwarding of 2 Tables of Appendix I, Draft NA BWR Radiological Effluent Technical Specifications, BWR, And NUREG-0133 GL 78-40 Training & Qualification Program Workshops NA Information GL 78-41 Mark II Generic Acceptance Criteria For Lead NA BWR Plants GL 78-42 Training and Qualification Program NA Information Workshops GL 79-01 Interservice Procedures for Instructional NA Information Systems Development - TRADOC GL 79-02 Transmitting Rev. to Entry Control Systems NA Information Handbook, Intrusion Detection Handbook, and Barrier Penetration Database GL 79-03 Offsite Dose Calculation Manual NA Information.

GL 79-04 Referencing 4/14/78 Letter - Modifications to NA Information NRC Guidance "Review and Acceptance of Spent Fuel Pool Storage and Handling" GL 79-05 Information Relating to Categorization of NA Information Recent Regulatory Guides by the Regulatory Requirements Review Committee GL 79-06 Contents of the Offsite Dose Calculation NA Information Manual GL 79-07 Seismic (SSE) and LOCA Responses NA Information (NUREG-0484)

GL 79-08 Amendment to 10 CFR 73.55 NA Information GL 79-09 Staff Evaluation of Interim Multiple-NA BWR Consecutive Safety-Relief Valve Actuations GL 79-10 Transmitting Regulatory Guide 2.6 for NA Does not apply to power reactors Comment GL 79-11 Transmitting "Summary of Operating NA Information Experience with Recalculating Steam Generators, January 1979" NUREG-0523 GL 79-12 ATWS - Enclosing Letter to GE, with NUREG-NA Information 0460, Vol. 3 Revision 0 Page 27 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 79-13 Schedule for Implementation and Resolution NA Information of Mark I Containment Long Term Program GL 79-14 Pipe Crack Study Group - Enclosing NUREG-NA Information 0531 and Notice GL 79-15 Steam Generators-Enclosing Summary of NA Information Operating Experience with Recirculating Steam Generators, NUREG-0523 GL 79-16 Meeting Re Implementation Of Physical NA Information Security Requirements GL 79-17 Reliability of Onsite Diesel Generators at Light NA Information Water Reactors GL 79-18 Westinghouse Two-Loop NSSS NA Addressed to specific plants GL 79-19 NRC Staff Review of Responses to I&E NA Addressed to specific plantsBulletins 79-06 and 79-06a GL 79-20 Cracking in Feedwater Lines Closed See IEB 79-13.

GL 79-21 Enclosing NUREG/CR 0660, "Enhancement NA Information of on Site Emergency Diesel Generator Reliability" GL 79-22 Enclosing NUREG-0560, "Staff Report on the NA Information Generic Assessment of Feedwater Transients in PWRs Designed by B&W GL 79-23 NRC Staff Review of Responses to I&E NA BWR Bulletin 79-08 GL 79-24 Multiple Equipment Failures in Safety Related NA OL @ time Systems GL 79-25 Information Required to Review Corporate NA Information Capabilities GL 79-26 Upgraded Standard Technical Specification NA Information Bases Program GL 79-27 Operability Testing of Relief and Safety Relief NA BWR Valves GL 79-28 Evaluation of Semi-Scale Small Break NA Information Experiment GL 79-29 Transmitting NUREG-0473, Revision 2, Draft NA Information Radiological Effluent Technical Specifications Revision 0 Page 28 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 79-30 Transmitting NUREG-0472, Revision 2, Draft NA Information Radiological Technical Specifications GL 79-31 Submittal of Copies of Response to 6/29/79 NA Information NRC Request GL 79-32 Transmitting NUREG-0578, "TMI-2 Lessons NA Information Learned" GL 79-33 Transmitting NUREG-0576 - Security Training NA Information and Qualification Plans GL 79-34 New Physical Security Plans (FR 43280-285)

NA Does not apply to power reactors GL 79-35 Regional Meetings to Discuss Impacts on NA Information Emergency Planning GL 79-36 Adequacy of Station Electric Distribution Open TVA will confirm that the electric power system design at BLN adequately Systems Voltages addresses the issues raised in GL 79-36, and that all supporting calculations and test results will be available for review.

GL 79-37 Amendment to 10 CFR 73.55 Deferral from NA Information 8/1/79 to 11/1/79 GL 79-38 BWR Off-Gas Systems - Enclosing NA BWR NUREG/CR-0727 GL 79-39 Transmitting Division 5 Draft Regulatory Guide NA Does not apply to power reactor and Value Impact Statement GL 79-40 Follow-up Actions Resulting from the NRC NA OL @ time Staff Reviews Regarding the TMI-2 Accident GL 79-41 Compliance with 40 CFR 190, EPA Uranium NA Information Fuel Cycle Standard GL 79-42 Potentially Unreviewed Safety Question on NA OL @ time Interaction Between Non-Safety Grade Systems and Safety Grade Systems GL 79-43 Reactor Cavity Seal Ring Generic Issue NA Addressed to specific plants GL 79-44 Referencing 6/29/79 Letter Re Multiple NA OL @ time Equipment Failures GL 79-45 Transmittal of Reports Regarding Foreign NA Information Reactor Operating Experiences GL 79-46 Containment Purge and Venting During Open TVA will confirm that the BLN purge and vent valves are qualified to meet Normal Operation their intended function assuming the worst case dynamic loading resulting I

_from the design basis LOCA.

Revision 0 Page 29 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 79-47 Radiation Training NA Information GL 79-48 Confirmatory Requirements Relating to NA BWR Condensation Oscillation Loads for the Mark I Containment Long Term Program GL 79-49 Summary Of Meetings Held On September NA Information 18-20, 1979 To Discuss A Potential Unreviewed Safety Question On Interaction Between Non-Safety Grade Systems And NSSS Supplied Safety Grade Systems GL 79-50 Emergency Plans Submittal Dates NA Information GL 79-51 Follow-up Actions Resulting from the NRC NA Information Staff Reviews Regarding the TMI-2 Accident GL 79-52 Radioactive Release at No. Anna Unit 1 and NA OL @ time.

Lessons Learned GL 79-53 ATWS NA Information GL 79-54 Containment Purging and Venting During NA Addressed to specific plants Normal Operation GL 79-55 Summary of Meeting Held on October 12, NA Information 1979 to Discuss Responses to IE Bulletins79-05C and 79-06C and HPI Termination Criteria GL 79-56 Discussion of Lessons Learned Short Term NA OL @ time Requirements GL 79-57 Acceptance Criteria for Mark I Long Term NA BWR Program GL 79-58 ECCS Calculations on Fuel Cladding NA OL @ time.

GL 79-59 None NA GL 79-60 Discussion of Lessons Learned Short Term NA Information Requirements GL 79-61 Discussion of Lessons Learned Short Term NA Information Requirements GL 79-62 ECCS Calculations on Fuel Cladding NA Duplicate of GL 79-58.

GL 79-63 Upgraded Emergency Plans NA See TVA letter dated 7/29/08 for WBN2 GL 79-64 Suspension of All Operating Licenses NA Information Revision 0 Page 30 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 79-65 Radiological Environmental Monitoring NA Information Program Requirements - Enclosing Branch Technical Position, Revision 1 GL 79-66 Additional Information Re 11/09/79 Letter on NA Information ECCS Calculations GL 79-67 Estimates for Evacuation of Various Areas NA Information Around Nuclear Power Reactors GL 79-68 Audit of Small Break LOCA Guidelines NA Information GL 79-69 Cladding Rupture, Swelling, and Coolant NA Information Blockage as a Result of a Reactor Accident GL 79-70 Environmental Monitoring for Direct Radiation NA Information GL 80-01 NUREG-0630 " Cladding, Swelling And NA Information Rupture - Models For LOCA Analysis" GL 80-02 QA Requirements Regarding Diesel NA Information Generator Fuel Oil GL 80-03 BWR Control Rod Failures NA BWR GL 80-04 IEB 80-01 Operability Of ADS Valve NA BWR Pneumatic Supply GL 80-05 IEB 79-01b Environmental Qualification Of NA Information Class 1E Equipment GL 80-06 Issuance Of Nureg-0313, Rev. 1, "Technical NA BWR Report On Material Selection And Processing Guidelines For Bwr Coolant Pressure Boundary Piping" GL 80-07 Information Regarding The Program For NA This GL was never issued.

Environmental Qualification Of Safety-Related Electrical Equipment GL 80-08 IEB 80-02 Inadequate Quality Assurance For NA BWR Nuclear Supplied Equipment GL 80-09 Low Level Radioactive Waste Disposal NA OL @ time GL 80-10 Issuance Of NUREG-0588, "Interim Staff NA Information Position On Equipment Qualifications Of Safety-Related Electrical Equipment GL 80-11 IEB 80-03 Loss Of Charcoal From Standard NA Information Type II, 2 Inch, Tray Absorber Cells I

I Revision 0 Page 31 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 80-12 IEB 80-04 Analysis Of A PWR Main Steam NA Information Line Break With Continued Feedwater Addition GL 80-13 Qualification of Safety Related Electrical NA OL @ time Equipment GL 80-14 LWR Primary Coolant System Pressure Open TVA will evaluate the valve configurations that connect high pressure Isolation Valves systems (Reactor Coolant System) to low pressure systems in light of the WASH 1400 Event V results, and take appropriate design and/or administrative actions to minimize the core melt frequency associated with intersystem loss-of-coolant accidents.

GL 80-15 Request For Additional Management And NA Information Technical Resources Information GL 80-16 IEB 79-01b Environmental Qualification Of NA Information I Class 1E Equipment GL 80-17 Modifications To Boiling Water Reactor NA BWR Control Rod Drive Systems GL 80-18 Crystal River 3 Reactor Trip From Open TVA will expand its review of the actions taken in response to IEB 79-27 to Approximately 100% Full Power include a specific review of the CR 3 event, and incorporate any design or administrative changes indicated.

GL 80-19 Resolution Of Enhanced Fission Gas Release NA Information Concern GL 80-20 Actions Required From OL Applicants Of NA Information NSSS Designs By W and CE Resulting From NRC B&O Task Force Review Of TMI2 Accident GL 80-21 Vacuum Condition Resulting in Damage to Closed See IEB 80-05.

Chemical Volume Control System Holdup Tanks GL 80-22 Transmittal Of NUREG-0654 "Criteria For NA Information Preparation And Evaluation Of Radiological Emergency Response Plans And Prepared GL 80-23 Change Of Submittal Date For Evaluation NA Information Time Estimates GL 80-24 Transmittal Of Information On NRC "Nuclear NA Information Data Link Specifications" Revision 0 Page 32 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 80-25 IEB 80-06 Engineering Safety Feature (ESF)

NA Information Reset Controls GL 80-26 Qualifications Of Reactor Operators NA Information GL 80-27 IEB 80-07 BWR Jet Pump Assembly Failure NA BWR GL 80-28 IE3 80-08 Examination Of Containment Liner NA Information Penetration Welds GL 80-29 Modifications To Boiling Water Reactor NA BWR Control Rod Drive Systems GL 80-30 Clarification Of The Term "Operable" As It NA OL @ time Applies To Single Failure Criterion For Safety Systems Required By TS GL 80-31 IEB 80-09 Hydramotor Actuator Deficiencies NA Information GL 80-32 Information Request on Category I Masonry NA Addressed by IEB 80-11.

Walls Employed by Plants Under CP and OL Review GL 80-33 Actions Req. From OL Applicants Of B&W Open TVA intends to meet the requirements of TMI Item II.E.1.1 which Designed NSSS Resulting From NRC B&O addresses the GL 80-33 actions including the performance of an AFW Task Force Review Of TMI2 Accident reliability analysis, an AFW review against the requirements of SRP 10.4.9 and BTP ASB 10-1 and a re-evaluation of AFW flowrate design bases and criteria.

GL 80-34 Clarification of NRC Requirements for NA Information Emergency Response Facilities at Each Site GL 80-35 Effect Of A DC Power Supply Failure On NA BWR ECCS Performances GL 80-36 THIS GENERIC LETTER IS A COVER NA Information LETTER FOR BULLETIN NO. 80-10 GL 80-37 Five Additional TMI-2 Related Requirements NA OL @ time To Operating Reactors GL 80-38 Summary of Certain Non-Power Reactor NA Does not apply to power reactors Physical Protection Requirements GL 80-39 IEB 80-11 Masonry Wall Design NA Information GL 80-40 Cover Letter for NUREGs-0645 & NUREG-NA Information 0626 Revision 0 Page 33 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 80-41 Summary Of Meetings Held On April 22 &23, NA Information 1980 With Representatives Of The Mark I Owners Group GL 80-42 IE13 80-12 Decay Heat Removal System NA Information Operability GL 80-43 IEB 80-13 Cracking In Core Spray Spargers NA BWR GL 80-44 Reorganization Of Functions And NA Information Assignments Within ONRR/SSPB GL 80-45 Fire Protection Rule NA OL (E time GL 80-46/47 A-12, Fracture Toughness and Additional Closed No response was required for this GL. NUREG-0577 resolved the laminar Guidance on Potential for Low Fracture tearing issue, and further stated that for plants under review the fracture Toughness and Laminar Tearing on PWR toughness issue was resolved.

Steam Generator Coolant Pump Supports GL 80-48 Revision To 5/19/80 Letter On Fire Protection NA OL @ time GL 80-49 Nuclear Safeguards Problems NA Information GL 80-50 Generic Activity A-10 BWR Cracks NA BWR GL 80-51 On-Site Storage Of Low-Level Waste NA OL @ time GL 80-52 Five Additional TMI-2 Related Requirements -

NA OL @ time Erata Sheets To 5/7/80 Letter GL 80-53 Decay Heat Removal Capability NA OL @c time GL 80-54 lE[3 80-14 Degradation Of Scram Discharge NA BWR Volume Capability GL 80-55 lEB 80-15 Possible Loss Of Hotline With Loss NA Information Of Off-Site Power GL 80-56 Commission Memorandum And Order On NA Information Equipment Qualification GL 80-57 Further Commission Guidance For Power NA Information Reactor Operating Licenses NUREG-0660 And NUREG-0694 GL 80-58 IE8 80-16 Potential Misapplication Of NA Information Rosemount Inc. Models 1151/1152 Pressure Transmitters With "A" Or "D" Output Codes GL 80-59 Transmittal Of Federal Register Notice RE NA Information Regional Meetings To Discuss Environmental Qualification Of Elec. Equipment Revision 0 Page 34 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 80-60 Request for Information Regarding Evaluation NA Information Times GL 80-61 TMI-2 Lessons Learned NA Information GL 80-62 TMI-2 Lessons Learned NA BWR GL 80-63 IEB 80-17 Failure Of Control Rods To Insert NA BWR During A Scram At A BWR GL 80-64 Scram Discharge Volume Designs NA BWR GL 80-65 Request For Estimated Construction NA Information Completion And Fuel Load Schedules GL 80-66 IEB 80-17 Supplement 1 Failure Of Control NA BWR Rods To Insert During A Scram At A BWR GL 80-67 Scram Discharge Volume NA BWR GL 80-68 IEB 80-17 Supplement 2 Failures Revealed NA Information By Testing Subsequent To Failure Of Control Rods To Insert During A Scram At A GL 80-69 IEB 80-18 Maintenance Of Adequate NA Information Minimum Flow Through Centrifugal Charging Pumps Following Secondary Side Helb GL 80-70 IEB 80-19 Failures Of Mercury-Wetted Matrix NA Information Relays In RPS Of Operating Nuclear Power Plants Designed By GE GL 80-71 IEB 80-20 Failures Of Westinghouse Type W-NA Information 2 Spring Return To Neutral Control Switches GL 80-72 Interim Criteria For Shift Staffing NA Information GL 80-73 "Functional Criteria For Emergency Response NA Information Facilities", NUREG-0696 GL 80-74 Forthcoming Meeting With Representatives Of NA Information The Electric Power Research Institute To Discuss Program For Resolution Of USI A-12 Fracture Toughness Issue GL 80-75 Lessons Learned Tech Specs NA OL @ time.

GL 80-76 Notice Of Forthcoming Meeting With GE To NA Information Discussed Proposed BWR Feedwater Nozzle I Leakage Detection System Revision 0 Page 35 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 80-77 Refueling Water Level - Technical NA Westinghouse plants only Specifications Changes GL 80-78 Mark I Containment Long-Term Program NA BWR GL 80-79 This generic letter is a cover letter for bulletin NA Information no. 80-17, supplement 3 GL 80-80 Preliminary Clarification Of TMI Action Plan NA Information Requirements GL 80-81 Preliminary Clarification Of TMI Action Plan NA Information Requirements - Addendum To 9/5/80 Letter GL 80-82 IEB 79-01b Supplement 2 Environmental NA Information Qualification Of Class 1 E Equipment GL 80-83 Environmental Qualification Of Safety-Related NA Information Equipment GL 80-84 BWR Scram System NA BWR GL 80-85 Implementation of Guidance From Unresolved NA Information Safety Issue A-12, "Potential For Low Fracture Toughness and Lamellar Tearing on Component Supports" GL 80-86 Notice Of Meeting To Discuss Final NA Information Resolution Of USI A-12 GL 80-87 Notice Of Meeting To Discuss Status Of EPRI-NA Information Proposed Resolution Of The USI A-12 Fracture Toughness Issue GL 80-88 Seismic Qualification Of Auxiliary Feedwater NA OL @ time Systems GL 80-89 IEB 79-01b Supplement 3 Environmental NA Information Qualification Of Class 1 E Equipment GL 80-90 NUREG-0737, TMI (Prior and future GLs, with Closed The requirements of Supplement 1 to NUREG 0737 are addressed in the the exception of certain discrete scopes, have applicable TMI Items below.

been screened into the NUREG 0737 list for items applicable to BLN)

GL 80-91 Odyn Code Calculation NA BWR GL 80-92 IEB 80-21 Valve Yokes Supplied By Malcolm NA Information Foundry Company, Inc.

GL 80-93 Emergency Preparedness NA Does not apply to power reactors Revision 0 Page 36 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 80-94 Emergency Plan NA Information GL 80-95 A-10, NUREG-0619, "BWR Feedwater Nozzle NA BWR and Control Rod Drive Return Line Cracking" GL 80-96 Fire Protection NA Addressed to specific plants GL 80-97 IEB 80-23 Failures Of Solenoid Valves NA Information Manufactured By Valcor Engineering Corporation GL 80-98 IEB 80-24 Prevention Of Damage Due To NA Information Water Leakage Inside Containment GL 80-99 Technical Specification Revisions For NA Information Snubber Surveillance GL 80-100 Appendix R to 10 CFR 50 Regarding Fire NA OL @ time Protection-Federal Register Notice GL 80-101 Inservice Inspection Programs NA Addressed to specific plants.

GL 80-102 Commission Memorandum And Order Of May NA Information 23, 1980 GL 80-103 Fire Protection - Revised Federal Register NA Information Notice GL 80-104 Orders On Environmental Qualification Of NA Information Safety Related Electrical Equipment GL 80-105 Implementation Of Guidance For USI A-12, NA Information Potential For Low Fracture Toughness And Lamellar Tearing On Component Supports GL 80-106 Report On ECCS Cladding Models, NUREG-NA Information 0630 GL 80-107 BWR Scram Discharge System NA BWR GL 80-108 Emergency Planning NA Information GL 80-109 Guidelines For SEP Soil Structure Interaction NA Information Reviews GL 80-110 Periodic Updating Of FSARS NA OL @ time GL 80-111 IEB 80-17 Supplement 4, Failure Of Control NA BWR Rods To Insert During A Scram At A BWR GL 80-112 IEB 80-25 Operating Problems With Target NA Information Rock Safety Relief Valves I

I GL 80-113 Control of Heavy Loads Closed Superseded by GL 81-07 Revision 0 Page 37 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 81-01 Qualification of Inspection, Examination, NA Information Testing and Audit Personnel GL 81-02 Analysis, Conclusions and Recommendations NA Information Concerning Operator Licensing GL 81-03 NUREG-0313, Technical Report on Material NA BWR Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping GL 81-04 Emergency Procedures and Training for Closed Subsumed by Station Blackout Station Blackout GL 81-05 Information Regarding The Program For Open This GL is addressed by the BLN EQ Program.

Environmental Qualification Of Safety-Related Electrical Equipment GL 81-06 Periodic Updating of Final Safety Analysis NA Information Reports (FSARS)

GL 81-07 Control of Heavy Loads Open TVA will ensure that BLN Heavy Loads Program is in compliance with NUREG-0612, IEB 96-02, and this GL.

GL 81-08 Odyn Code NA BWR GL 81-09 BWR Scram Discharge System NA BWR GL 81-10 Post-TMI Requirements For The Emergency NA Information Operations Facility GL 81-11 BWR Feedwater Nozzle and Control Rod NA BWR Drive Return Line Nozzle Cracking (NUREG-0619)

GL 81-12 Fire Protection Rule (and prior related GLs)

NA OL @ time GL 81-13 SER For GEXL Correlation For 8X8R Fuel NA BWR Reload Applications For Appendix D Submittals of The GE Topical Report GL 81-14 Seismic Qualification of Auxiliary Feedwater Open The applicable BLN design requirements for the Auxiliary FW system will Systems incorporate the requirements of the Standard Review Plan, NUREG-0800, Section 10.4.9.

GL 81-15 Environmental Qualification of Class 1E NA Information Electrical Equipment-Clarification of Staffs Handling of Proprietary Information GL 81-16 NUREG-0737 Item I.C.1 SER on Abnormal NA See NUREG list in this table Transient Operating Guidelines (ATOG)

Revision 0 Page 38 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 81-17 Functional Criteria for Emergency Response NA Information Facilities GL 81-18 BWR Scram Discharge System-Clarification of NA BWR Diverse Instrumentation Requirements GL 81-19 Thermal Shock to Reactor Pressure Vessels NA OL @ time GL 81-20 Safety Concerns Associated With Pipe Breaks NA BWR in The BWR Scram System GL 81-21 Natural Circulation Cooldown Open TVA will develop specific calculations for BLN demonstrating adequate natural circulation capability and a sufficient source of condensate-grade auxiliary feedwater. The operator training program will address natural circulation cooldown.

GL 81-22 Engineering Evaluation of The H.B. Robinson NA Information Reactor Coolant System Leak on 1/29/81 GL 81-23 INPO Plant Specific Evaluation Reports NA Information GL 81-24 Multi-Plant Issue B-56 Control Rods Fail To NA BWR Fully Insert GL 81-25 Change in Implementing Schedule For NA Information Submission and Evaluation of Upgraded Emergency Plans GL 81-26 Licensing Requirements for Pending NA Addressed to applicants with pending construction permits Construction Permit and Manufacturing License Applications GL 81-27 Privacy and Proprietary Material in Emergency NA Information Plans GL 81-28 Steam Generator Overfill NA Information GL 81-29 Simulator Examinations NA Information GL 81-30 Safety Concerns Associated With Pipe Breaks NA BWR in the BWR Scram System GL 81-31 Small Break LOCA Confirmatory Integral NA This GL was never issued.

Systems Experiments for B&W Designed Plants GL 81-32 NUREG-0737, Item II.K.3.44-Evaluation of NA BWR Anticipated Transients Combined With Single I Failure Revision 0 Page 39 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 81-33 Technical Specification for Station Batteries NA This GL was never issued Multi-plant Action GL 81-34 & -

Safety Concerns Associated With Pipe Breaks NA BWR 35 in the BWR Scram System GL 81-36 Revised Schedule for Completion of TMI NA Information Action Plan Item ll.D.1, Relief and Safety Valve Testing GL 81-37 ODYN Code Reanalysis Requirements NA BWR GL 81-38 Storage of Low Level Radioactive Wastes at NA Information Power Reactor Sites GL 81-39 NRC Volume Reduction Policy NA Information GL 81-40 Qualifications of Reactor Operators NA Information GL 82-01 New Applications Survey NA Information GL 82-02 Commission Policy on Overtime NA Information GL 82-03 High Burnup MAPLHGR Limits NA BWR GL 82-04 Use of INPO See-in Program NA Information GL 82-05 Post-TMI Requirements NA OL (E time GL 82-06 This Generic Letter Was Never Issued NA GL 82-07 Transmittal of NUREG-0909 Relative to the NA Information Ginna Tube Rupture GL 82-08 Transmittal of NUREG-0909 Relative to the NA Information Ginna Tube Rupture GL 82-09 Environmental Qualification of Safety Related Open This GL is addressed by the BLN EQ Program.

Electrical Equipment GL 82-10 Post-TMI Requirements NA OL @ time GL 82-11 Transmittal of NUREG-0916 Relative to the NA Information Restart of R.E. Ginna Nuclear Power Plant GL 82-12 Nuclear Power Plant Staff Working Hours NA Information GL 82-13 Reactor Operator and Senior Reactor NA Information Operator Examinations GL 82-14 Submittal of Documents to the NRC NA Information GL 82-15 This Generic Letter Was Never Issued NA GL 82-16 NUREG-0737 Technical Specifications NA OL @ time GL 82-17 Inconsistency of Requirements Between NA Information 50.54(t) and 50.15 Revision 0 Page 40 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 82-18 Reactor Operator and Senior Reactor NA Information Operator Requalification Examinations GL 82-19 Submittal of Copies of Documentation to NA Information NRC-Copy Requirements for Emergency Plans and Physical Security Plans GL 82-20 Guidance for Implementing the Standard NA Information Review Plan Rule GL 82-21 Fire Protection Audits NA Information GL 82-22 Congressional Request for Information NA OL @ time Concerning Steam Generator Tube Integrity GL 82-23 Inconsistency Between Requirements Of 10 NA Information CFR 73.40(d) And Standard Technical Specifications For Performing Audits Of Safeguards Contingency Plans GL 82-24 Safety Relief Valve Quencher Loads: BWR NA BWR MARK II and III Containments GL 82-25 Integrated IAEA Exercise for Physical NA OL @ time Inventory at LWRS GL 82-26 NUREG-0744, REV. 1 - Pressure Vessel NA OL @ time Material Fracture Toughness GL 82-27 Transmittal of NUREG-0763 - Guidelines For NA BWR Confirmatory In-Plant Tests of Safety-Relief Valve Discharge for BWR Plants GL 82-28*

Inadequate Core Cooling Instrumentation Open GL 82-28 applies to CE and Westinghouse plants. However, the BLN System design will address inadequate core cooling instrumentation.

GL 82-29 This Generic Letter Was Never Issued NA This GL was never issued GL 82-30 Filings Related to 10 CFR 50 Production and NA Information Utilization Facilities GL 82-31 This Generic Letter Was Never Issued NA This GL was never issued GL 82-32 Draft Steam Generator Report (SAI)

NA OL @ time GL 82-33 Supplement to NUREG-0737, Requirements Closed The requirements of Supplement 1 to NUREG 0737 are addressed in the for Emergency Response Capability applicable TMI Items below.

GL 82-34 This Generic Letter Was Never Issued NA GL 82-35 This Generic Letter Was Never Issued NA GL 82-36 This Generic Letter Was Never Issued NA Revision 0 Page 41 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 82-37 This Generic Letter Was Never Issued NA GL 82-38 Meeting to Discuss Developments for NA Information Operator Licensing Examinations GL 82-39 Problems With Submittals of Subsequent NA Information Information of CURT 73.21 For Licensing Reviews GL 83-01 Operator Licensing Examination Site Visit NA Information GL 83-02 NUREG-0737 Technical Specifications NA BWR GL 83-03 This GL was never used NA GL 83-04 Regional Workshops Regarding Supplement 1 NA Information to NUREG-0737, Requirements For Emergency Response Capability GL 83-05 Safety Evaluation of "Emergency Procedure NA BWR Guidelines, Revision 2," June 1982 GL 83-06 Certificates and Revised Format For Reactor NA Information.

Operator and Senior Reactor Operator Licenses GL 83-07 The Nuclear Waste Policy Act of 1982 NA Information GL 83-08 Modification of Vacuum Breakers on Mark I NA BWR Containments GL 83-09 Review of Combustion Engineering Owners' NA Applies only to CE designed plants Group Emergency Procedures Guideline Program GL 83-10a, Resolution of TMI Action Item II.K.3.5 NA Applicable only to Westinghouse and CE plants b, c, & d "Automatic Trip of Reactor Coolant Pumps" GL 83-10e & Resolution of TMI Action Item I1.K.3.5 Closed See TMI Item II.K.3.

f "Automatic Trip of Reactor Coolant Pumps" GL 83-11 Licensee Qualification for Performing Safety NA OL @ time Analyses in Support of Licensing Actions GL 83-12 Issuance of NRC FORM 398 - Personal NA Information Qualifications Statement - Licensee GL 83-13 Clarification of Surveillance Requirements for Information HEPA Filters and Charcoal Absorber Units In I STD. Tech Specs on ESF Cleanup Systems I

Revision 0 Page 42 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 83-14 Definition of "Key Maintenance Personnel,"

NA Information (Clarification of Generic Letter 82-12)

GL 83-15 Implement. of Reg. Guide 1.150, "Ultrasonic NA Information Testing of RX Vessel Welds During Preservice

& Inservice Examinations, Rev.1 GL 83-16 Transmittal of NUREG-0977 Relative to the NA Information ATWS Events at Salem Generating Station, Unit NO. 1 GL 83-17 Integrity of Requalification Examinations for NA Information Renewal of Reactor Operator and Senior Reactor Operator Licenses GL 83-18 NRC Staff Review of the BWR Owners' Group NA BWR (BWROG) Control Room Survey Program GL 83-19 New Procedures for Providing Public Notice NA OL @ time Concerning Issuance of Amendments To Operating Licenses GL 83-20 Integrated Scheduling for Implementation of NA Information Plant Modifications GL 83-21 Clarification of Access Control Procedures for NA Information Law Enforcement Visits GL 83-22 Safety Evaluation of "Emergency Response NA Applies to Westinghouse PWRs only Guidelines" GL 83-23 Safety Evaluation of "Emergency Procedure NA Applies to CE PWRs only Guidelines" GL 83-24 TMI Task Action Plan Item I.G.1, "Special Low NA BWR Power Testing and Training,"

Recommendations for BWRs GL 83-25 This GL was never issued NA GL 83-26 Clarification Of Surveillance Requirements For NA Information Diesel Fuel Impurity Level Tests Revision 0 Page 43 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 83-27 Surveillance Intervals in Standard Technical NA Information Specifications GL 83-28*

Required Actions Based on Generic Implications of Salem ATWS Events (Prior and future GLs, with the exception of certain discrete scopes, have been screened into the following list):

1.2 - Post Trip Review Data and Information Capability 2.1 - Equipment Classification and Vendor Interface (Reactor Trip System Components) 2.2 - Equipment Classification and Vendor Interface (All SR Components) 3.1 - Post-Maintenance Testing (Reactor Trip System Components) 3.2 - Post-Maintenance Testing (All SR Components) 4.1 - Reactor Trip System Reliability (Vendor Related Modifications) 4.3 - Reactor Trip System Reliability (Automatic Actuation of Shunt Trip Attachment)

Open TVA will review all correspondence.on GL 83-28, including NRC SER's dated 9/25/86 and 3/9/87 which approved BLN responses to a number of actions required by GL 83-28, to ensure they remain applicable.

As required by 10CFR50.62, the capability to automatically initiate the AFW system and initiate a turbine trip under conditions indicative of an ATWS with equipment from sensor output to final actuation device diverse from the reactor trip system, will be met by incorporating ATWS mitigating system actuation circuitry (AMSAC). In addition, a diverse scram system, from the sensor output to interruption of power to the control rods, will be provided by the Diverse Scram System (DSS).

Re. 1.2, the design of the Sequence of Events Recorder and Integrated Plant Computer systems will address functional requirements for data collection capability to assure that the causes for unscheduled reactor shutdowns, as well as the response of safety related equipment, can be evaluated and fully understood prior to plant restart. In addition, a systematic methodology to assess unscheduled reactor shutdowns will be implemented as discussed in TVA letter dated 9/6/83.

Re. 2.1, TVA will confirm that QA programs and procedures are in place to ensure that all components necessary for accomplishing required safety functions are properly identified in documents, procedures and information handling systems that are used to control safety related activities as discussed in previous correspondence and partially accepted in NRC SER dated 3/9/87. TVA will confirm that procedures are in place and maintained to ensure that vendor information for safety related I&C components is complete.

Re. 2.2, see response to item 2.1 above.

Re. 3.1 and 3.2, TVA will confirm that Functional Requirements Specifications ensure testing capability and features are provided for post maintenance operability testing of Reactor Trip System components and all safety related components as discussed in previous correspondence and partially accepted in NRC SER dated 3/9/87.

Re. 4.1, TVA will ensure that vendor recommended reactor trip breaker modifications and associated reactor protection system changes are

.1. ___________________________________

L _________________________

L Revision 0 Page 44 of 67 Revision 0 Page 44 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure completed for BLN, and that a comprehensive program of preventive maintenance and surveillance testing is developed for the reactor trip breakers as discussed in previous correspondence and partially accepted in NRC SER dated 3/9/87.

Re. 4.3, TVA will confirm that its approach to automatic actuation of the breaker shunt trip attachment, accepted in NRC SER dated 3/9/87, remains applicable.

GL 83-29 This Generic Communication was not issued NA GL 83-30 Deletion of STD. Tech Spec Surveillance NA Information Requirement 4.8.1.1.2.d.6 For Diesel Generator Testing GL 83-31 Safety Evaluation of "Abnormal Transient NA Information.

Operating Guidelines" GL 83-32 NRC Staff Recommendations Regarding NA Information Operator Action for Reactor Trip and ATWS GL 83-33 NRC Positions on Certain Requirements of NA Information Appendix R to 10 CFR 50 GL 83-34 GL was never issued NA GL 83-35 Clarification of TMI Action Plan Item I1.K.3.31 NA Information GL 83-36 NUREG-0737 Technical Specifications NA BWR GL 83-37 NUREG-0737 Technical Specifications NA OL @ time GL 83-38 NUREG-0965, "NRC Inventory of Dams" NA Information GL 83-39 Voluntary Survey of Licensed Operators NA Information GL 83-40 Operator Licensing Examination NA Information GL 83-41 Fast Cold Starts of Diesel Generators NA OL @ time.

GL 83-42 Clarification to GL 81-07 Regarding Response NA Information to NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants" GL 83-43 Reporting Requirements of 10 CFR 50, NA Information Sections 50.72 and 50.73, and Standard Technical Specifications GL 83-44 Availability of NUREG-1021, "Operator NA Information Licensing Examiner Standards" GL 84-01 NRC Use Of The Terms "Important To Safety" NA Information and "Safety Related" I

Revision 0 Page 45 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 84-02 Notice of Meeting Regarding Facility Staffing NA Information GL 84-03 Availability of NUREG-0933, "A Prioritization NA Information of Generic Safety Issues" GL 84-04 Safety Evaluation of Westinghouse Topical NA Information Reports Dealing with Elimination of Postulated Pipe Breaks in PWR Primary Main Loops (Generic Letter 84-04)

GL 84-05 Change to NUREG-1021, "Operator Licensing NA Information Examiner Standards" GL 84-06 Operator and Senior Operator License NA Does not apply to power reactor Examination Criteria for Passing Grade GL 84-07 Procedural Guidance for Pipe Replacement at NA BWR BWRs GL 84-08 Interim Procedures for NRC Management of NA Information Plant-Specific Backfitting GL 84-09 Recombiner Capability Requirements of 10 NA BWR CFR 50.44(c)(3)(ii)

GL 84-10 Administration of Operating Tests Prior to NA Information Initial Criticality GL 84-11 Inspection of BWR Stainless Steel Piping NA BWR GL 84-12 Compliance W 10CFR61 and Implementation NA Information of Rad Effluent Tech Specs, Attendant Process Control Program GL 84-13 Technical Specification for Snubbers NA Information GL 84-14 Replacement and Requalification Training NA Information Program GL 84-15 Proposed Staff Actions to Improve and NA Information Maintain Diesel Generator Reliability GL 84-16 Adequacy of On-Shift Operating Experience NA Information for Near Term Operating License Applicants GL 84-17 Annual Meeting to Discuss Recent NA Information Developments Regarding Operator Training, Qualifications, and Examinations GL 84-18 Filing of Applications for Licenses and NA Does not apply to power reactors Amendments II Revision 0 Page 46 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 84-19 Availability of Supplement 1 to NUREG-0933, NA Information "A Prioritization of Generic Safety Issues" GL 84-20 Scheduling Guidance for Licensee Submittals NA Information of Reloads That Involve Unreviewed Safety Questions GL 84-21 Long Term Low Power Operation in NA Information Pressurized Water Reactors GL 84-22 GL was never issued NA GL 84-23 Reactor Vessel Water Level Instrumentation in NA BWR BWRs GL 84-24 Certification of Compliance to 10 CFR 50.49 NA Implementation of the EQ Program will address 10 CFR 50.49 requirements.

GL 85-01 Fire Protection Policy Steering Committee NA Issued as draft Report GL 85-02 Recommended Actions Stemming From NRC Open TVA letter dated 6/17/85 addresses BLN. Later GL's address SG tubes.

Integrated Program for the Resolution of BLN will consider this and other GL's for its SG inspection program.

Unresolved Safety Issues Regarding Steam Generator Tube Integrity GL 85-03 Clarification of Equivalent Control Capacity for NA BWR Standby Liquid Control Systems GL 85-04 Operating Licensing Examinations NA Information.

GL 85-05 Inadvertent Boron Dilution Events NA OL @ time GL 85-06 Quality Assurance Guidance for ATWS NA Information Equipment That Is Not Safety-Related GL 85-07 Implementation of Integrated Schedules for NA OL @ time Plant Modifications GL 85-08 10 CFR 20.408 Termination Reports - Format NA Information GL 85-09 Technical Specifications For Generic Letter NA Information 83-28, Item 4.3 GL 85-10 Technical Specification For Generic Letter 83-Open This issue will be addressed by current STS and creation of BLN TSs 28, Items 4.3 and 4.4 based on NUREG-1430, Rev. 3, June, 2004.

GL 85-11 Completion of Phase II of "Control of Heavy Closed See GL 81-07 Loads at Nuclear Power Plants" GL 85-12 Implementation of TMI Item II.K.3.5 NA Applicable to Westinghouse plants only Revision 0 Page 47 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 85-13 Transmittal Of NUREG-1 154 Regarding The NA Information Davis-Besse Loss Of Main And Auxiliary Feedwater Event GL 85-14 Commercial Storage At Power Reactor Sites NA OL @ time Of Low Level Radioactive Waste Not Generated By The Utility GL 85-15 Information On Deadlines For 10CFR50.49, NA OL @ time "EQ Of Electric Equipment Important To Safety At NPPS" GL 85-16 High Boron Concentrations NA Information GL 85-17 Availability Of Supplements 2 and 3 To NA Information NUREG-0933, "A Prioritization Of Generic Safety Issues" GL 85-18 Operator Licensing Examinations NA Information GL 85-19 Reporting Requirements On Primary Coolant NA Information Iodine Spikes GL 85-20 Resolution Of Generic Issue 69: High Open TVA will investigate the BLN design to determine if it is the same as the Pressure Injection/Make-up Nozzle Cracking 177FA design which experienced in-service cracking. If so, the In Babcock And Wilcox Plants recommendations of the B&WOG Safe-End Task Force as summarized in GL 85-20 will be implemented.

GL 85-21 This Generic Communication was not issued NA GL 85-22 Potential For Loss Of Post-LOCA NA Information Recirculation Capability Due To Insulation Debris Blockage GL 86-01 Safety Concerns Associated With Pipe Breaks NA BWR In The BWR Scram System GL 86-02 Technical Resolution of Generic Issue B NA BWR Thermal Hydraulic Stability GL 86-03 Applications For License Amendments NA Information GL 86-04 Policy Statement On Engineering Expertise NA Information On Shift GL 86-05 Implementation of TMI Item II.K.3.5 Closed See response to TMI Item II.K.3.

GL 86-06 Implementation of TMI Item II.K.3.5 NA CE plants only Revision 0 Page 48 of 67 ITVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 86-07 Transmittal of NUREG-1190 Regarding The NA Information San Onofre Unit 1 Loss of Power And Water Hammer Event GL 86-08 Availability of Supplement 4 to NUREG-0933, NA Information "A Prioritization of Generic Safety Issues" GL 86-09 Technical Resolution of Generic Issue B-59, NA Information (n-1) Loop Operation in BWRs and PWRs GL 86-10 Implementation of Fire Protection NA Information Requirements GL 86-11 Distribution of Products Irradiated in Research NA Does not apply to power reactors Reactors GL 86-12 Criteria for Unique Purpose Exemption From NA Does not apply to power reactors Conversion From The Use of HEU Fuel GL 86-13 Potential Inconsistency Between Plant Safety Open Issue to be addressed by current STS and creation of BLN TSs based on Analyses and Technical Specifications NUREG-1430, Rev. 3, June 2004.

GL 86-14 Operator Licensing Examinations NA Information GL 86-15 Information Relating To Compliance With 10 NA Information CFR 50.49, "Environmental Qualification Of Electric Equipment Important To Safety For Nuclear Power Plants", (Generic Letter 86-15)

GL 86-16 Westinghouse ECCS Evaluation Models NA Information GL 86-17 Availability of NUREG-1169, "Technical NA BWR Findings Related to Generic Issue C-8, BWR MSIC Leakage And Treatment Methods" GL 87-01 Public Availability Of The NRC Operator NA Information Licensing Examination Question Bank GL 87-02 &

Verification of Seismic Adequacy of NA OL @ time 03 Mechanical and Electrical Equipment in Operating Reactors, USI A-46 GL 87-04 Temporary Exemption From Provisions Of NA OL @ time The FBI Criminal History Rule For Temporary I Workers Revision 0 Page 49 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 87-05 Request for Additional Information on NA BWR Assessment of License Measures to Mitigate and/or Identify Potential Degradation of Mark I Drywells GL 87-06 Periodic Verification of Leak Tight Integrity of NA OL @ time Pressure Isolation Valves GL 87-07 Information Transmittal of Final Rulemaking NA Information For Revisions To Operator Licensing - 10 CFR 55 And Confirming Amendments GL 87-08 Implementation of 10 CFR 73.55 NA OL @ time Miscellaneous Amendments and Search Requirements GL 87-09 Sections 3.0 And 4.0 of Standard Tech Specs NA Information on Limiting Conditions For Operation And Surveillance Requirements GL 87-10 Implementation of 10 CFR 73.57, NA OL @ time Requirements For FBI Criminal History Checks GL 87-11 Relaxation in Arbitrary Intermediate Pipe NA Information I Rupture Requirements I

GL 87-12 Loss of Residual Heat Removal While The Closed Superseded by GL 88-17 Reactor Coolant System is Partially Filled GL 87-13 Integrity of Requalification Examinations At NA Does not apply to power reactors Non-Power Reactors GL 87-14 Operator Licensing Examinations NA Information GL 87-15 Policy Statement On Deferred Plants NA Information GL 87-16 Transmittal of NUREG-1262, "Answers To NA Information Questions On Implementation Of 10 CFR 55 On Operators' Licenses" GL 88-01 NRC Position on IGSCC in BWR Austenitic NA BWR Stainless Steel Piping GL 88-02 Integrated Safety Assessment Program II NA OL @ time (ISAP II)

GL 88-03 Resolution of GSI 93, Steam Binding of Open See response to IEB 85-01.

Auxiliary Feedwater Pumps Revision 0 Page 50 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 88-04 Distribution of Gems Irradiated in Research NA Does not apply to power reactors Reactors GL 88-05*

Boric Acid Corrosion of Carbon Steel Reactor Open As stated in TVA's response dated 6/1/88, TVA will implement a program Pressure Boundary Components in PWR at BLN to address the potential for boric acid corrosion of the reactor plants coolant pressure boundary in accordance with GL 88-05 prior to initial fuel load.

GL 88-06 Removal of Organization Charts from NA Information Technical Specification Administrative Control Requirements GL 88-07 Modified Enforcement Policy Relating to 10 NA This GL deals with enforcement policy and TVA understands that those CFR 50.49, EQ of Electrical Equipment policies apply to BLN.

Important to Safety for Nuclear Power Plants GL 88-08 Mail Sent or Delivered to the Office of Nuclear NA Information Reactor Regulation GL 88-09 Pilot Testing of Fundamentals Examination NA BWR GL 88-10 Purchase of GSA Approved Security NA Information Containers GL 88-11 NRC Position on Radiation Embrittlement of Open TVA will ensure that the methodology used to predict the effect of neutron Reactor Vessel Material and its Impact on radiation on reactor vessel materials will be consistent with Rev 2 to RG Plant Operations 1.99 or justify the use of different methods. TVA will submit the results of this technical analysis prior to completion of design analysis for BLN. If this evaluation results in a modification of the pressure-temperature limits contained in Technical Specifications in order to satisfy the requirements of Sec. V of 10 CFR Part 50, Appendix G, TVA will also submit a schedule for whatever actions we propose to take at the same time, and ensure that these actions are complete prior to fuel load.

GL 88-12 Removal of Fire Protection Requirements from NA Information Technical Specification GL 88-13 Operator Licensing Examinations NA Information GL 88-14*

Instrument Air Supply System Problems Open TVA will review NUREG1275 Volume 2 and perform a design and Affecting Safety-Related Equipment operations review of the instrument air system. The results of these reviews will be factored into the BLN design and procedures and ensure that equipment important to safety will perform their required functions.

GL 88-15 Electric Power Systems - Inadequate Control NA Information Over Design Process Revision 0 Page 51 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 88-16 Removal of Cycle-Specific Parameter Limits NA Information from Technical Specifications GL 88-17*

Loss of Decay Heat Removal Open TVA will review GL 88-17 and incorporate any design or administrative actions required.

GL 88-18*

Plant Record Storage on Optical Disks Complete Information. Additionally, in a letter dated 10/23/97, TVA provided NRC with its plans for control of plant record storage on optical disks.

GL 88-19 Use of Deadly Force by Licensee Guards to Open Will be addressed in the BLN Site Security Plan Prevent Theft of Special Nuclear Material GL 88-20*

Individual Plant Examination for Severe Open TVA will develop a plant specific PRA for BLN.

Accident Vulnerability GL 89-01 Implementation of Programmatic and NA Information Procedural Controls for Radiological Effluent Technical Specifications GL 89-02 Actions to Improve the Detection of NA Information Counterfeit and Fraudulently Marketed Products GL 89-03 Operator Licensing Examination Schedule NA Information GL 89-04*

Guidelines on Developing Acceptable Open TVA will develop an IST Program that addresses the issues discussed in Inservice Testing Programs GL 89-04 and GL 89-04, Supplement 1.

GL 89-05 Pilot Testing of the Fundamentals NA Information Examination GL 89-06 TMI Action Plan Item I.D.2 - Safety Parameter Closed See response to TMI Item I.D.2 Display System GL 89-07 Power Reactor Safeguards Contingency Open TVA will address GL 89-07 in the BLN Site Security Plan.

Planning for Surface Vehicle Bombs I

Revision 0 Page 52 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 89-08*

Erosion/Corrosion-Induced Pipe Wall. Thinning Open TVA will:

1) Review all plant piping systems (piping, tanks, vessels, and equipment) to determine their susceptibility to FAC, utilizing the susceptibility criteria in EPRI NSAC 202L

2) Mark up design drawings to show identified piping segments found to be susceptible

3) Develop the BLN onsite FAC Program based on TVA FAC requirements

4) Conduct initial baseline examinations of equipment identified to be susceptible to FAC and load them into appropriate site FAC databases

5) Determine if any piping or equipment needs to be repaired or replaced prior to system operation based on industry experience and initial examination results.

GL 89-09 ASME Section III Component Replacements NA OL a time GL 89-10*

Safety-Related Motor-Operated Valve Testing Open TVA will implement the requirements of GL 89-10, including description of and Surveillance the BLN MOV program.

GL 89-11 Resolution of Generic Issue 101 "Boiling NA BWR Water Reactor Water Level Redundancy" GL 89-12 Operator Licensing Examination NA Information.

GL 89-13*

Service Water System Problems Affecting Open TVA will implement the actions specified in GL 89-13,including SWS Safety Related Equipment inspection, maintenance, testing, operation, training and chemical treatment.

GL 89-14 Line-Item Improvements in Technical NA Information Specifications - Removal of 3.25 Limit on Extending Surveillance Intervals GL 89-15 Emergency Response Data System NA Information GL 89-16 Installation of a Hardened Wetwell Vent NA BWR GL 89-17 Planned Administrative Changes to the NRC NA Information Operator Licensing Written Examination Process GL 89-18 Resolution of Unresolved Safety Issues A-17, NA Information "Systems Interactions in Nuclear Power Plants" I

Revision 0 Page 53 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 89-19 Request for Actions Related to Resolution of Open The BLN design will incorporate automatic steam generator overfill Unresolved Safety Issue A-47 "Safety protection to mitigate MFW system overfeed events. Also, refer to USI A-Implication of Control Systems in LWR 47.

Nuclear Power Plants" Pursuant to 10 CFR 50.54(f)

GL 89-20 Protected Area Long Term Housekeeping NA Does not apply to power reactors GL 89-21 Request for Information Concerning Status of Open See USI Section of this submittal (Table 3).

Implementation of Unresolved Safety Issue (USI) Requirements GL 89-22 Potential For Increased Roof Load Due to NA No response required.

Changes in Maximum Precipitation GL 89-23 NRC Staff Responses to Questions Pertaining NA Information to Implementation of 10 CFR Part 26 GL 90-01 Request for Voluntary Participation in NRC NA Information Regulatory Impact Survey GL 90-02 Alternative Requirements for Fuel Assemblies NA Information in the Design Features Section of Technical Specifications GL 90-03 Relaxation of Staff Position in Generic Letter NA Information 83-28, Item 2.2 Part 2 '"Vendor Interface for Safety-Related Components" GL 90-04 Request for Information on the Status of Open TVA will provide status with submittal of the construction reactivation letter.

Licensee Implementation of GSls Resolved with Imposition of Requirements or CAs GL 90-05 Guidance for Performing Temporary Non-NA Information Code Repair of ASME Code Class 1, 2, and 3 Piping GL 90-06*

Resolution of Generic Issues 70, "PORV and Open TVA will implement the applicable improvements in PORV maintenance Block Valve Reliability," and 94, "Additional and testing programs in Enclosure A of the GL (which is applicable to B&W LTOP Protection for PWRs" designed plants). Generic Issue 94 is not applicable to B&W plants (and therefore not applicable to BLN) as stated in the GL.

GL 90-07 Operator Licensing National Examination NA Information Schedule 1

GL 90-08 Simulation Facility Exemptions NA Information Revision 0 Page 54 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 90-09 Alternative Requirements for Snubber Visual NA Information Inspection Intervals and Corrective Actions GL 91-01 Removal of the Schedule for the Withdrawal of NA Information Reactor Vessel Material Specimens from Technical Specifications GL 91-02 Reporting Mishaps Involving LLW Forms NA OL @ time Prepared for Disposal GL 91-03 Reporting of Safeguards Events NA Information GL 91-04 Changes in Technical Specification NA Information Surveillance Intervals to Accommodate a 24-Month Fuel Cycle GL 91-05 Licensee Commercial-Grade Procurement NA Information and Dedication Programs GL 91-06 Resolution of Generic Issue A-30, "Adequacy NA OL @ time of Safety Related DC Power Supplies" GL 91-07 GI-23, "Reactor Coolant Pump Seal Failures" NA Information and Its Possible Effect on Station Blackout GL 91-08 Removal of Component Lists from Technical NA Information Specifications GL 91-09 Modification of Surveillance Interval for the NA Information Electrical Protective Assemblies in Power Supplies for the Reactor Protection System GL 91-10 Explosives Searches at Protected Area NA Does not apply to power reactors Portals GL 91-11 Resolution of Generic Issues A-48, "LCOs for NA OL @ time Class 1E Vital Instrument Buses", and 49, "Interlocks and LCOs for 1 E Tie Breakers" GL 91-12 Operator Licensing National Examination NA Information Schedule GL 91-13 Request for Information Related to Resolution NA Addressed to specific plants of Generic Issue 130, "Essential Service Water System Failures @ Multi-Unit Sites" GL 91-14 Emergency Telecommunications NA Information Revision 0 Page 55 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 91-15 Operating Experience Feedback Report, NA Information Solenoid-Operated Valve Problems at U.S.

Reactors GL 91-16 Licensed Operators' and Other Nuclear NA Information Facility Personnel Fitness for Duty GL 91-17 Generic Safety Issue 29, "Bolting Degradation NA Information or Failure in Nuclear Power Plants" GL 91-18 Information to Licensees Regarding Two NRC NA GL 91-18 has been superseded by RIS 2005-20 Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability]

GL 91-19 Information to Addressees Regarding New NA Information Telephone Numbers for NRC Offices Located in One White Flint North GL 92-01 Reactor Vessel Structural Integrity Open For BLN, TVA will adopt a reactor vessel surveillance program meeting the guidelines of Appendix H to 10 CFR Part 50. Reactor Vessel material data requested by the GL will be provided to the NRC in accordance with the GL requirements if applicable. Also see response to IEB 01-01.

GL 92-02 Resolution of Generic Issue 79, "Unanalyzed NA Information Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown" GL 92-03 Compilation of the Current Licensing Basis:

NA Information Request for Voluntary Participation in Pilot Program GL 92-04 Resolution of Issues Related to Reactor NA BWR Vessel Water Level Instrumentation in BWRs GL 92-05 Licensee Commercial-Grade Procurement NA Information and Dedication Programs GL 92-06 Operator Licensing National Examination NA Information Schedule GL 92-07 Office Of Nuclear Reactor Regulation NA Information Reorganization GL 92-08 Thermo-Lag 330-1 Fire Barriers Open Thermo-Lag electrical raceway and component fire barrier systems for separating safe-shutdown functions within the same fire area will be tested and qualified in accordance with the guidance contained in R.G. 1.189.

Revision 0 Page 56 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 92-09 Limited Participation by NRC in the IAEA NA Information International Nuclear Event Scale GL 93-01 Emergency Response Data System Test NA Addressed to specific plants Program GL 93-02 NRC Public Workshop on Commercial Grade NA Information Procurement and Dedication GL 93-03 Verification of Plant Records NA Information GL 93-04 Rod Control System Failure and Withdrawal of Open The BLN rod control system will be modified to a digital based system and Rod Control Cluster Assemblies, 10 CFR will be reviewed for applicability of this issue.

50.54(f)

GL 93-05 Line-Item Technical Specifications NA Information Improvements to Reduce Surveillance Requirements for Testing During Power Operation GL 93-06 Research Results on Generic Safety Issue NA Information 106, "Piping and the Use of Highly Combustible Gases in Vital Areas" GL 93-07 Modification of the Technical Specification NA OL @ time Administrative Control Requirements for Emergency and Security Plans GL 93-08 Relocation of Technical Specification Tables NA OL @ time of Instrument Response Time Limits GL 94-01 Removal of Accelerated Testing and Special NA OL @ time Reporting Requirements for Emergency Diesel Generators GL 94-02 Long Term Solutions and Upgrade of Interim NA BWR Operating Recommendations for Thermal/Hydraulic Instabilities in BWRs GL 94-03 IGSCC of Core Shrouds in BWRs NA BWR GL 94-04 Voluntary Reporting of Additional NA Information Occupational Radiation Exposure Data GL 95-01 NRC Staff Technical Position on Fire NA Does not apply to power reactors Protection for Fuel Cycle Facilities Revision 0 Page 57 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 95-02 Use of NUMARC/EPRI Report TR-1 02348, NA Information "Guideline on Licensing Digital Upgrades," in Determining the Acceptability of Performing Analog-to-Digital Replacements under 10 CFR 50.59 GL 95-03 Circumferential cracking of Steam Generator Open TVA will follow current industry guidelines (e.g., NEI 97-06) for steam (SG) Tubes generator tube integrity, which have been endorsed by the NRC. These guidelines specify inspection requirements for locations in steam generator tubes deemed susceptible to circumferential cracking. As stated in TVA letter to the NRC dated 6/27/1995, BLN will provide a complete response to the GL prior to initial fuel loading for BLN.

GL 95-04 Final Disposition of the Systematic Evaluation NA Information Program Lessons-Learned Issues GL 95-05 Voltage Based Repair Criteria for W SG NA This GL requires no specific action or written response.

• Tubes Affected by Outside Diameter Stress Corrosion Cracking GL 95-06 Changes in the Operator Licensing Program NA Information GL 95-07 Pressure Locking and Thermal Binding of Open TVA will evaluate pressure locking and thermal binding of safety related Safety-Related Power-Operated Gate Valves power-operated gate valves and take corrective actions for those valves identified as being susceptible.

GL 95-08 10 CFR 50.54(p) Process for Changes to NA Information Security Plans Without Prior NRC Approval GL 95-09 Monitoring and Training of Shippers and NA Information Carriers of Radioactive Materials GL 95-10 Relocation of Selected Technical NA Information Specifications Requirements Related to Instrumentation GL 96-01 Testing of Safety-Related Circuits Open TVA will ensure that the BLN design and surveillance procedures allow complete testing of safety related logic circuits.

GL 96-02 Reconsideration of Nuclear Power Plant NA Information Security Requirements Associated with an Internal Threat Revision 0 Page 58 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 96-03*

Relocation of the Pressure Temperature Limit Open BLN will be using the Improved Standard Technical Specification format Curves and Low Temperature Overpressure which relocates this information to a licensee-controlled document. This Protection System Limits item and others will be part of the implementation of the Tech Specs and associated process and procedures for control of these limits.

GL 96-04 Boraflex Degradation in Spent Fuel Pool NA OL @ time.

Storage Racks GL 96-05*

Periodic Verification of Design-Basis Open See response to GL 89-10. The MOV program will include the Capability of Safety-Related Motor-Operated requirements contained in GL 96-05.

Valves GL 96-06

• Assurance of Equipment Operability and Open BLN systems supporting heat removal and accident mitigation were Containment Integrity During Design-Basis designed to mitigate potential water hammer and two phase conditions that Accident Conditions could lead to water hammer. These calculations will be updated. Any system vulnerabilities will be identified and design changes will be implemented as needed.

GL 96-07 Interim Guidance on Transportation of Steam NA OL @ time.

Generators GL 97-01*

Degradation of Control Rod Drive Mechanism Open TVA letter dated 4/30/97 committed to submit a report for BLN addressing Nozzle and Other Vessel Closure Head this issue prior to fuel load. This will be included in the overall program to Penetrations address Alloy 600.

GL 97-02 Revised Contents of the Monthly Operating NA OL @ time Report GL 97-03 Annual Financial Update of Surety NA Does not apply to power reactors Requirements for Uranium Recovery Licensees GL 97-04 Assurance of Sufficient Net Positive Suction Open TVA will review the system analysis for the subject pumps used to Head for Emergency Core Cooling and determine the available NPSH. The reviews will include the factors Containment Heat Removal Pumps discussed in GL 97-04, and any design changes indicated will be

_ implemented. The analysis will be available for review.

Revision 0 Page 59 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 97-05 SG Tube Inspection Techniques Open TVA will commit to following current industry guidelines (e.g., NEI 97-06) for steam generator tube integrity, which have been endorsed by the NRC.

These guidelines ensure that the examination methods chosen are qualified and appropriate for the steam generator design and expected tube degradation based on industry experience and best practices. TVA will provide a formal response to this Generic Letter supplying the requested information and demonstrating how the BLN's steam generator ISI program ensures compliance with 10 CFR Appendix B and the plant technical specifications.

GL 97-06 Degradation of SG Internals Open TVA will ensure that the ROTSG design and plant operating procedures mitigate the possibility for the types of degradation identified in this Generic Letter.

GL 98-01 Year 2000 Readiness of Computer Systems at NA OL @ time Nuclear Power Plants GL 98-02 Loss of Reactor Coolant Inventory and Open WVA will assess the design of the BLN emergency core cooling systems to Associated Potential for Loss of Emergency identify design features, such as a common pump suction header, which Mitigation Functions While in a Shutdown could render the systems susceptible to common cause failure such as Condition experienced at Wolf Creek in 1994. Any system vulnerabilities will be identified and addressed in the BLN design.

GL 98-03 NRC Generic Letter 98-03: NMSS Licensees' NA Does not apply to power reactors and Certificate Holders' Year 2000 Readiness Programs GL 98-04 Potential for Degradation of the ECCS and the Open TVA will evaluate the protective coatings to be used inside containment at Containment Spray System After a LOCA BLN addressing the action items of GL 98-04 including the procurement, Because of Construction and Protective application, maintenance and qualification of protective coatings. In Coating Deficiencies and Foreign Material in addition, WVA will provide the information required by GL 98-04 on the Containment assessment of coatings, the use of unqualified coatings and any commercial grade dedication program that may be used for coatings used inside containment.

GL 98-05 BWR Licensees Use of the BWRVIP-05 NA BWR Report to Request Relief from Augmented Examination Requirements on RPV Circumferential Shell Welds GL 99-01 NRC Generic Letter 99-01: Recent Nuclear NA Information Material Safety and Safeguards Decision on Bundling Exempt Quantities Revision 0 Page 60 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 99-02 Laboratory Testing of Nuclear Grade Activated NA OL @ time Charcoal GL 03-01 Control Room Habitability Open TVA will ensure that the control room meets the applicable habitability regulatory requirements and that it meets the facility's design and licensing bases, including the requirement of unfiltered in leakage into the control room enclosure being below the limits of the plant's design basis radiological analyses.

GL 04-01 Requirements for SG Tube Inspection Open See response to GL 97-05 GL 04-02 Potential Impact of Debris Blockage on Closed See response to USI A-43.

Emergency Recirculation during Design Basis Accidents at PWRs GL 06-01 SG Tube Integrity and Associated Technical Open TVA will submit a plan consistent with TSTF-449, "Steam Generator Tube Specifications Integrity", to incorporate requirements for maintaining SG tube integrity into Technical Specifications.

GL 06-02*

Grid Reliability and the Impact on Plant Risk Open TVA intends to meet the regulations sited in this GL on offsite power and the Operability of Offsite Power reliability, station blackout and recovery, as well as the latest revision of the Regulatory Guides specified. In addition, TVA will answer each question in this GL in the areas of 1) use of protocols between TVA and its transmission system operator (TSO), 2) use of TVA/TSO protocols and analysis tools used to assist TVA in monitoring grid conditions, 3) offsite power restoration procedures, and 4) losses of offsite power caused by grid failures at a frequency equal to or greater than once in 20 site -years.

GL 06-03*

Potentially Nonconforming Hemyc and MT Complete Hemyc and MT Fire Barrier materials addressed in this Generic Letter will Fire Barrier Configurations not be utilized for separating safe-shutdown functions within the same fire area.

GL 07-01" Inaccessible or Underground Power Cable Open TVA will provide a description of the inspection, testing and monitoring Failures that Disable Accident Mitigation programs it intends to implement to detect the degradation of inaccessible Systems or Cause Plant Transients or underground power cables that support systems within the scope of 1 OCFR50.65.

GL 08-01 Managing Gas Accumulation in Emergency Open TVA will review applicable systems for adequate venting design, and Core Cooling, Decay Heat Removal, and where indicated, implement changes to mitigate gas accumulation.

Containment Spray Systems Procedures will be developed to address proper maintenance and operability checks for these systems.

Revision 0 Page 61 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure NUREG-Control of Heavy Loads at Nuclear Power Open The BLN design requirements for the Reactor Building Polar and the Spent 0612 Plants Fuel Building cranes will incorporate the applicable requirements of NUREG-0612 and requirements found in NUREG-0554.

NUREG-Clarification of TMI Action Plan Requirements 0737:

I.A.1.1*

Shift technical advisor Open TVA will provide an on shift technical advisor to the shift supervisor.

I.A.1.2*

Shift supervisor responsibilities Open TVA system wide approach approved for other sites will be used for BLN, and will address the non-safety related duties of the Shift Supervisor.

I.A.1.3*

Shift Manning Open BLN minimum shift staffing will be defined in the Technical Specifications.

I.A.2.1 Immediate upgrade of RO & SRO training and Open All TVA sites employ an approved licensed operator training program and qualifications TVA will implement this program at BLN. The minimum requirements for ROs and SROs will be documented.

I.A.2.3 Administration of training programs Open TVA will implement the same approach as approved at other TVA nuclear facilities.

I.A.3.1 Revise scope & criteria for licensing exams Open TVA program meets the requirements of NUREG-1021 and 10 CFR Part 55 and this program will be implemented at BLN.

I.B.1.2*

Independent Safety Engineering Group Open TVA will implement independent onsite safety oversight consistent with the requirements of this TMI item, and similar to those oversight organizations approved at other TVA nuclear facilities.

I.C.1*

Short-term accident & procedure review Open TVA has updated emergency operating procedures at its three other nuclear facilities and will implement the same or similar procedures at BLN.

B&W specific accident mitigation measures will be incorporated.

I.C.2*

Shift & relief turnover procedures Open Shift turnover procedures will be based upon those in place for other TVA nuclear facilities adjusted for any BLN plant specific requirements.

I.C.3*

Shift supervisor responsibilities Open BLN Shift Supervisor responsibilities will be established and documented similar to other TVA nuclear facilities.

I.C.4*

Control room access Open BLN Control Room access will be similar to the other TVA nuclear facilities.

Control Room access procedures will be established and documented.

I.C.5*

Feedback of operating experience Open BLN procedures for feedback of operating, design and construction experience will be based on the procedures in place at other TVA nuclear facilities.

I.C.6*

Verify correct performance of operating Open BLN procedures for verifying correct performance of operating activities will activities be based on the procedures utilized at TVA's other nuclear facilities.

I.C.7 NSSS vendor review of procedures Open Areva will review the BLN low power tests as well as the power ascension tests and revise the emergency procedures as appropriate.

Revision 0 Page 62 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure I.C.8 Pilot monitoring of selected emergency Open EOPs will be developed consistent with the requirements of SRP Chapter procedures for NTOLs 13 and the other WVA nuclear facilities, and submitted to the NRC for approval.

I.D.1 Control room design reviews Open WVA will perform a Control Room Design Review that meets the requirements of 10CFR50.34 and NUREG 0737, Supplement 1, Section 5 as indicated in TVA letter dated 6/11/82.

I.D.2*

Plant-safety-parameter display console Open The BLN design requirements for the SPDS will fully incorporate the requirements of NUREG 0737, Supplement 1, Section 4, as well as taking into account the information provided in NUREG 1342 and NUREG 0696.

I.G.1*

Training during low-power testing Open TVA will develop the BLN low power testing and training program consistent with its other nuclear facilities, and the direction provided by NRC in its letter dated 6/18/81.

ll.B.1 Reactor-coolant-system vents Open As noted in TVA letter dated 12/24/81, the BLN design will include RCS high point vents on the top of each hot leg, on the top of the pressurizer and on the top of the reactor head, as well as a system to measure RCS level.

ll.B.2*

Plant shielding Open TVA will perform a design review of the BLN plant shielding to ensure post accident access to vital areas. In addition, an equipment qualification review of equipment located in spaces/systems which may be used in post accident operations will be conducted.

ll.B.3*

Post-accident sampling Open TVA will review the current BLN PASS design to ensure that it meets the requirements specified in item ll.B.3, and will assess any necessary design changes based upon recent industry experience.

11.B.4 Training for mitigating core damage Open TVA will develop a training program on the use of installed equipment and systems to control or mitigate accidents in which the core is severely I

damaged.

ll.D.1*

Relief and safety-valve test requirements Open TVA will provide evidence, supported by test, of reactor coolant system safety and relief valve functionality and block/isolation valve functionality for expected operating and accident conditions.

ll.D.3*

Valve position indication Open The BLN design will incorporate features that provide control room operators with unambiguous indication of reactor coolant system relief and safety valve position. Such features will include PORV stem mounted position indication in the MCR, high temperature alarms in SV downstream piping, pressurizer relief tank temperature, pressure and level indication, as well as the use of acoustic monitors.

Revision 0 Page 63 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure II.E.1.1" Auxiliary feedwater system evaluation Open TVA will 1) perform an AFW reliability analysis using event and fault tree logic techniques, 2) perform a deterministic review of the AFW system using the acceptance criteria of SRP 10.4.9 and BTP ASB 10-1 and 3) reevaluate the AFW system flowrate design bases and criteria..

II.E.1.2*

Auxiliary feedwater system initiation and flow Open The BLN Auxiliary Feedwater System (AFW) design will incorporate automatic and manual AFW initiation and AFW flow indication in the control room.

II.E.3.1*

Emergency power for Pressurizer heaters Open TVA will confirm that the BLN design incorporates two independent and redundant emergency powered pressurizer heater groups, each of which is capable of maintaining RCS conditions conducive to natural circulation.

The emergency heater groups will be provided with Class 1 E power and controls and BLN operators will receive training on their use.

II.E.4.1 Dedicated hydrogen penetrations Open TVA will confirm that all BLN containment penetrations used for purge and postaccident combustible gas control are dedicated to that service only.

II.E.4.2*

Containment isolation dependability Open The BLN Containment Isolation System will be designed to:

(a) ensure all non-essential systems are automatically isolated by the Containment Isolation System, (b) incorporate two isolation barriers in series for each non-essential penetration (except instrument lines),

(c) incorporate features that prevent reopening of the containment isolation valves upon reset of the isolation signal, (d) utilize a containment pressure setpoint for initiation of containment isolation that is as low as is compatible with normal plant operations, (e) incorporate automatic isolation of all pathways to the environs in the event of a high radiation signal.

II.F.1*

Accident-monitoring instrumentation:

Open The BLN design will incorporate instrumentation required to measure and A. Noble Gas record containment pressure, containment water level, containment B. Iodine/Particulate Sampling hydrogen concentration, containment radiation intensity and noble gas C. Containment High Range Monitoring effluents at all potential accident release points. These parameters will be D. Containment Pressure displayed in the control room. In addition, the BLN design will allow E. Containment Water Level continuous sampling of radioactive iodines and particulates in gaseous F. Containment Hydrogen effluents from all potential accident release points, and the ability to I

I_

I_

Ianalyze and measure these samples onsite.

II.F.2*

Instrumentation for detection of inadequate Open The BLN design will incorporate instrumentation that provides an I

core-cooling I

unambiguous indication of inadequate core cooling in the control room.

Revision 0 Page 64 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure II.G.1*

Power supplies for pressurizer relief valves, Open TVA will confirm that the power supply for the pressurizer relief and block block valves, & level indicators valves and the pressurizer level indicators meet the requirements specified in item IIlG.1.

II.K.1 IE Bulletins Open Re. item 5, the required valve positions for ESF and AFW systems will be

5. Review ESF valves-IEB 79-05A reviewed during procedure development to ensure that specified valve positions and administrative controls support proper operation of the ESF

10. Operability status - IEB 79-05A and AFW systems.

20. Prompt manual reactor trip - IEB 79-Re. item 10, TVA will review and modify as necessary maintenance and 05B test procedures to ensure that the requirements of IEB 79-05A are met.

21. Auto SG anticipatory reactor trip - IEB Re. item 20, TVA will develop procedures and train operating personnel to 79-05B initiate a prompt manual trip of the reactor for symptoms indicating an uncontrolled RCS pressure increase.

Re. item 21, IEB 79-05B requires incorporation of a safety grade automatic anticipatory reactor scram in the event of loss of feedwater, turbine trip or significant reduction in steam generator level. TVA will review the actions previously taken and ensure that this requirement is incorporated in the BLN design.

II.K.2 Orders on B&W plants:

Open Re. Item 2, Procedures and training will be in place to allow initiation and

2. Procedures to control AFW ind of ICS control of auxiliary feedwater independent of the ICS.

9. FEMA on ICS Re. item 9, the BLN ICS will be replaced by a digital control system. TVA

10. Safety-grade trip will perform a FEMA on the upgraded ICS.

13. Thermal mechanical report Re. item 10, see response to I I.K.1.

14. Lift frequency of PORVs and SVs Re. item 13, TVA will perform a detailed analysis of the thermal-

15. Effects of slug flow on OTSGS mechanical conditions in the RV during recovery from small breaks with an

16. RCP seal damage extended loss of all feedwater to demonstrate that sufficient mixing of the HPI water with the reactor coolant would occur so that significant thermal shock effects to the reactor vessel are precluded.

Re. item 14, PORV and RPS trip setpoints will be determined for BLN based upon the assumptions applied to the operating B&W fleet per NUREG 0565 and the Safety Performance Improvement Program to address the issue of reducing challenges to the PORVs and SVs.

Re. item 15, TVA will reconfirm its original evaluation and conclusions regarding the ability of steam generator tubes to withstand the mechanical loading caused by the effects of slug flow.

Re. item 16, TVA will confirm that any RCP seal damage due to loss of cooling is considered in the BLN design.

Revision 0 Page 65 of 67 TVA Letter dated May 5, 2011

.Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure II.K.3 Final recommendations, B&O task force:

Open Re. item 1, The BLN design incorporates a system that uses the PORV

1. Auto PORV block valve to protect against small break LOCA accidents. This system

a. Design automatically causes the block valve to close when the reactor coolant

b. Test/install system pressure decays after the PORV has opened. This design and

2. Report on PORV failures possible alternatives will be evaluated and the best alternative will be

3. Reporting SV and RV failures and implemented.

challenges Re. item 2, TVA will submit a report documenting actions taken to

5. Auto trip of RCPs decrease the probability of a small-break LOCA caused by a stuck open

7. Evaluation of PORV opening PORV. Vendor failure rates will be included in the report.

probability Re. item 3, TVA will develop a plan for data collection on Safety Valve and

17. ECC system outages Relief Valve failures similar to that in place at other TVA nuclear facilities.

30. SB LOCA methods Re. item 5, the BWOG justified manual RCP trip provided certain

a. Schedule outline conditions are met. Other B&W plants, such as CR3, are incorporating

b. Model automatic RCP trip on loss of subcooling margin and reactor trip. The

c. New Analysis preferred BLN design is automatic RCP trip. TVA will confirm that

31. Compliance with CFR 50.46 automatic RCP trip remains the preferred design and will incorporate it into the BLN design accordingly.

Re. item 7, TVA will perform an evaluation of PORV opening probability during overpressure transients.

Re. item 17, TVA will develop a plan on ECCS outages similar to that in place at other TVA nuclear facilities.

Re. items 30 and 31, as noted in NRC letter dated 6/28/85, the methods used for small break LOCA analysis for BLN were determined to be acceptable. However, any required updates to the small break LOCA Topical Reports or new NRC concerns in the area will be addressed.

III.A.1.1 Emergency preparedness, short-term Open TVA will develop BLN emergency plans, procedures and facilities that meet the requirements of the applicable regulations and guidance including the performance of an integrated assessment of offsite and onsite emergency preparedness.

III.A.1.2*

Upgrade emergency support facilities Open The BLN design will include emergency response facilities that meet the I_ requirements of this item.

III.A.2 Emergency preparedness Open TVA will confirm that the BLN radiological emergency response plans meet I

I_

the requirements of this item.

Revision 0 Page 66 of 67 TVA Letter dated May 5, 2011 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure III.D.1.1*

Primary coolant outside containment Open BLN will implement a program to reduce leakage from systems outside containment that could contain primary coolant or other highly radioactive fluids or gases.

III.D.3.3*

Inplant 12 radiation monitoring Open The BLN Radiation Monitoring System will provide a mechanism to detect the presence of and accurately measure radioiodine.

III.D.3.4*

Control room habitability Open See response to GL 03-01.

Note: An asterisk in Table 2 following the item number is used to denote instances where the item is included in the 2007 NRC Standard Review Plan and therefore will be addressed in the Operating License application update process.

Revision 0 Page 67 of 67 TVA Letter date May 5, 2011 Table 3: Unresolved Safety Issues - Applicability and Status for Bellefonte Units 1 & 2 USI Status Comment Item A-i: Water Open NUREG-0927 (March 1984) resolves this issue. The Hammer replacement steam generator design incorporates a high-external header. TVA will conduct a preoperational vibration dynamic effects test program in accordance with Section III of the ASME code for Class 1 and 2 piping systems and piping restraints.

Item A-2: Asymmetric Open This USI was resolved with the publication of NUREG-Blowdown Loads on 0609 which affected all operating and future PWRs.

Reactor Primary Coolant TVA plans to perform analyses and request NRC Systems approval to eliminate postulated large bore pipe ruptures from the design basis for BLN. Analyses of the remaining piping will be performed in accordance with applicable requirements and with approved methods to demonstrate that the systems are acceptable for asymmetric blowdown loads.

Item A-3: Westinghouse NA NA for B&W Steam Generator Tube Integrity Item A-4: CE Steam NA NA for B&W Generator Tube Integrity Item A-5: B&W Steam Open The original steam generators at Bellefonte will be Generator Tube Integrity replaced prior to startup. The design of the replacement steam generators reflects prior industry experience by incorporating design features and materials to address known tube damage mechanisms in operating steam generators of similar design. TVA will follow current industry guidelines (e.g., NEI 97-06) to demonstrate that the steam generator tubes will adequately satisfy their design requirements during normal operations and postulated accident conditions.

See also GL 85-02.

Item A-6: Mark I Short-NA BWR only Term Program Item A-7/D-01: Mark I NA BWR only Long-Term Program Item A-8: Mark II NA BWR only Containment Pool Dynamic Loads Item A-9: ATWS Open See response to GL 83-28.

Item A-10/MPA B-25:

NA BWR only BWR Feedwater Cracking Revision 0 Page 1 of 4 TVA Letter date May 5, 2011 Table 3: Unresolved Safety Issues - Applicability and Status for Bellefonte Units 1 & 2 1USI Status Comment Item A-11: Reactor Open TVA is committed to meeting the requirements of Vessel Materials Appendix G to 10 CFR 50, including the upper shelf Toughness energy level requirements; consequently no impact of USI A-1 1 is anticipated. In addition, BLN will adopt a reactor vessel surveillance program meeting the guidelines of Appendix H to 10 CFR Part 50. Reactor Vessel material data requested by GL 92-01 will be provided to the NRC in accordance with the GL requirements as applicable.

Item A-12: Fracture Complete This issue was resolved by GL 80-46/47 - Generic Toughness of Steam Technical Activity A-12, "Fracture Toughness and Generator and Reactor Additional Guidance on Potential for Low Fracture Coolant Pump Supports Toughness and Laminar Tearing on PWR Steam Generator Coolant Pump Supports." No response was required for this GL, and NUREG-0577, "Potential for Low Fracture Toughness and Lamellar Tearing on PWR Steam Generator and Reactor Coolant Pump Supports,"

states that the lamellar tearing aspect of this issue was resolved by the NUREG. Further, the NUREG states that for plants under review, the fracture toughness issue was resolved.

Items A-13 NA NA Dropped or Resolved Item A-17: Systems Complete GL 89-18 resolved this issue and required no Interactions in Nuclear licensee action.

Power Plants Items A-18 NA NA Dropped or Resolved Item A-24: Qualification Open For the BLN equipment qualification program, and as of Class 1 E Safety-agreed by NRC in their letter dated 10/9/91, equipment Related Equipment procured by TVA prior to 8/31/91 will be qualified to at least the standards of NUREG 0588, Category II and IEEE 323-1971. Equipment procured after 8/31/91 will be qualified to the standards of NUREG 0588, Category I and IEEE 323-1974 unless "sound reasons to the contrary" (as defined in RG 1.89) exist. Where "sound reasons to the contrary" exist, qualification will be to at least the standards of NUREG 0588, Category II and IEEE 323-1971.

Item A Dropped or NA NA Resolved Item A-26: Reactor Open TVA will meet requirements of SRP Section 5.2, as Vessel Pressure specified in the Regulatory Framework and respond to Transient Protection GL 88-11.

Items A-27 NA NA Dropped or Resolved Revision 0 Page 2 of 4 TVA Letter date May 5, 2011 Table 3: Unresolved Safety Issues - Applicability and Status for Bellefonte Units 1 & 2 USI Status Comment Item A-31: RHR Open In accordance with NUREG 0933, this USI was resolved Shutdown Requirements with the issuance of NUREG 0800, SRP Section 5.4.7.

Resolution of this issue will be accomplished by satisfying the requirements of the 2007 revision of SRP Section 5.4.7.

Items A-32 NA NA Dropped or Resolved Item A-36: Control of Open This USI was resolved with the issuance of GL 80-Heavy Loads Near 113. GL 80-113 was superseded by GL 81-07, Spent Fuel "Control of Heavy Loads." GL 81-07 is open, with a required action to be in compliance with NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants."

Items A-37 NA NA Dropped or Resolved Item A-39:

NA BWR only Determination of SRV Pool Dynamic Loads and Pressure Transients Item A-40: Seismic Open Seismic reanalysis, which will follow the requirements of Design Criteria the 2007 SRP, will address this USI.

Item A Dropped or NA NA Resolved Item A-42/MPA B-05 NA BWR only Pipe Cracks in Boiling Water Reactors Item A-43: Containment Open TVA will install large surface area ECCS sump strainers.

Emergency Sump The strainers will be qualified by testing in accordance Performance with the NRC approved methodologies and guidance to address GSI 191. TVA will also perform containment debris source inventory walkdowns and applicable analysis (e.g., debris generation, debris transport, chemical effects and downstream effects analysis) for BLN.

Item A-44: Station Open TVA will address the Station Blackout (SBO) issue by Blackout meeting the requirements outlined in 10CFR50.63 and in the 2007 revision of NUREG 0800, SRP Chapter 8.4.

Specifically, TVA will perform a BLN specific analysis that includes, among other things, evaluation of EDG capacity and reliability, offsite power configuration, alternate AC power sources, SBO duration and required electrical loads.

Revision 0 Page 3 of 4 TVA Letter date May 5, 2011 Table 3: Unresolved Safety Issues - Applicability and Status for Bellefonte Units 1 & 2 USI Status Comment Item A-45: Shutdown Open SECY 88-260 stated that resolution of this issue would Decay Heat Removal be through plant specific analysis under the Individual Requirements Plant Examination (IPE) for Severe Accident Vulnerabilities. For BLN, GL 88-20, which requires a plant specific IPE, is open with an action to perform the plant specific IPE. The scope of the BLN PRA

_encompasses the IPE requirements.

Item A-46: Seismic Closed The scope of Task A-46 is limited to dealing with the Qualification of seismic qualification of equipment in currently operating Equipment in Operating plants and plants holding an operating license prior to Plants 1977.

Item A-47: Safety Open See response to GL 89-19 which states that the BLN Implications of Control design will incorporate automatic steam generator Systems overfill protection to mitigate main feedwater system overfeed events.

Item A-48: Hydrogen Open TVA intends to demonstrate that BLN is designed such Control Measures and that containment hydrogen concentration cannot be Effects of Hydrogen greater than 10 percent (by volume) assuming hydrogen Burns on Safety generation equivalent to a 100 percent fuel clad-coolant Equipment reaction; that it has the capability to ensure a mixed atmosphere during design basis and significant beyond design basis accidents; and that equipment to monitor hydrogen in the containment is functional, reliable and capable of continuously measuring the concentration of hydrogen in the containment atmosphere following a significant beyond design basis accident. TVA will assess any design changes necessary in the area of measuring, mixing and otherwise mitigating the effects of hydrogen generation considering recent industry experience.

Item A-49: Pressurized Open Consistent with the conclusion statement on this USI in Thermal Shock NUREG-0933, TVA will comply with the requirements of SRP paragraph 5.3.2, including the relevant requirements of 10 CFR 50.61 and RG 1.154 to demonstrate that the reactor vessel materials are adequate for this condition. Related actions will also be taken in response to Generic Letters 88-11 and 92-01.

Specifically, TVA will perform the necessary technical analysis using the methodology provided in Regulatory Guide 1.99 revision 2 for BLN as requested in GL 88-11.

In addition, BLN will adopt a reactor vessel surveillance program meeting the guidelines of Appendix H to 10 CFR Part 50. Reactor Vessel material data requested by the GL will be provided to the NRC in accordance with the GL requirements as applicable.

Revision 0 Page 4 of 4 TVA Letter dated May 5, 2011 List of TVA Commitments

1. TVA will take actions necessary to complete the items identified as "Open" in Tables 2 (Generic Communications) and 3 (Unresolved Safety Issues) of to this letter for BLN Unit 1.

2. TVA will provide periodic updates of the BLN Regulatory Framework tables as actions are completed.