ML15188A155

Supplement to License Amendment Request (LAR) 14-04, Request to Adopt ASME Code, Section Iii, 1980 Edition (No Addenda) as an Alternative to Current Code of Record

ML15188A155
Person / Time
Site:	Fort Calhoun
Issue date:	07/02/2015
From:	Cortopassi L P Omaha Public Power District
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LIC-15-0086, TAC MF4160
Download: ML15188A155 (9)

Text

Employment with Equal Opportunity 444 South 16 th Street Mall Omaha, NE 68102-2247

LIC-15-0086

July 2, 2015

U.S. Nuclear Regulatory Commission

Attn: Document Control Desk Washington, DC 20555-0001

Fort Calhoun Station, Unit No. 1 Renewed Facility Operating License No. DPR-40 NRC Docket No. 50-285

Subject:

Supplement to License Amendment Request (LAR) 14-04, Request to Adopt ASME Code, Section Ill, 1980 Edition (No Addenda) as an Alternative to Current Code of Record (TAC No. MF4160)

References:

See Page 3 This letter is providing a revision to Appendix F, Table F-1 of the Fort Calhoun Station, Unit No. 1, Updated Safety Analysis Report (USAR) as submitted by Reference 1 and revised in References 3 and 5. The Omaha Public Power District (OPPD) discussed this issue with NRC staff during a teleconference on June 17, 2015. OPPD has revised Appendix F, Table F-1 by deleting (i.e., striking out) the reference to footnote (d) from Load Combination 2 because the application of footnote (d) could be interpreted incorrectly. As currently written, the application of footnote (d) to Load Combination 2 could be construed to indicate that fluid transient loadings only need to be applied to the pressurizer relief valve piping and supports, which is incorrect. Fluid transient loadings should be applied to all piping for which a fluid transient is applicable.

Also, OPPD had proposed to reference footnote (d) in Service Level C of the new Load Combination table proposed for new footnote (e). However, that reference to footnote (d) has been removed to clarify that fluid transients must be considered, where applicable, as noted above. OPPD's Corrective Action Program will resolve the remaining references to footnote (d) in Appendix F, Table F-1.

Markup and re-typed (i.e. clean) USAR, Appendix F pages are attached. Please note that this change to USAR, Appendix F does not affect the proposed changes to USAR Section 1.2 or USAR Appendix G as provided in Reference 1.

U. S. Nuclear Regulatory Commission LIC-15-0086 Page 3

References:

1. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk), "License Amendment Request (LAR) 14-04, Revise Current Licensing Basis to Adopt American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code,Section III, 1980 Edition, (no Addenda) as an Alternative to Current Code of Record," dated May 16, 2014 (LIC-14-0043) (ML14143A370)

2. Letter from NRC (C. F. Lyon) to OPPD (L. P. Cortopassi), "Fort Calhoun Station, Unit No.1- Request for Additional Information RE: License Amendment Request to Adopt ASME Code, Section Ill, 1980 Edition (no Addenda) as an Alternative to

Current Code of Record (TAC No. MF4160)," dated September 24, 2014 (NRC-

14-0110) (ML14259A365)

3. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk), "OPPD Response to NRC Request for Additional Information Regarding License Amendment Request (LAR) 14-04, Request to Adopt ASME Code, Section Ill, 1980 Edition (no Addenda) as an Alternative to Current Code of Record (TAC No. MF4160)," dated January 9, 2015 (LIC-15-0002) (ML15009A319)

4. Letter from NRC (C. F. Lyon) to OPPD (L. P. Cortopassi), "Fort Calhoun Station, Unit No. 1 - Request for Additional Information Round 2 RE: License Amendment Request to Adopt ASME Code, Section Ill, 1980 Edition (no Addenda) as an Alternative to Current Code of Record (TAC No. MF4160)," dated February 25, 2015 (NRC-15-005) (ML15043A061)

5. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk), "OPPD Response to Second Round NRC Request for Additional Information Regarding License Amendment Request (LAR) 14-04, Request to Adopt ASME Code, Section Ill, 1980 Edition (no Addenda) as an Alternative to Current Code of Record (TAC No. MF4160)," dated March 27, 2015 (LIC-15-0043) (ML15086A545)

LIC-15-0086 Page 1 USAR Markup Pages

USAR-Appendix F Information Use Page 9 of 40 Classification of Structures and Rev. 10 Equipment and Seismic Criteria

Table F Loading Combinations and Primary Stress Limits

Primary Stress Limits

Loading Combinations Vessels Piping (e) Supports (f)

1. Design Loading + P M < S M P M < 1.2S h Working Design Earthquake Stress P B + P L < 1.5S M P B + P M < 1.2S h Anchor Bolts F.S.>4.0 (d)

2. Normal Operating P M < S D P M < S D Within Loadings + (Maximum

Yield Hypothetical Earthquake Anchor Bolts + (Fluid Transient F.S.> 2.0 (d) Loadings(d)) (g)) (b) (c)

3. Normal Operating P M < S L P M < S L Deflection of supports Loadings + (Pipe

limited to Rupture + Maximum maintain supported Hypothetical Earthquake(g)) equipment within (b) (a), (c) limits shown

USAR-Appendix F Information Use Page 10 of 40 Classification of Structures and Rev. 10 Equipment and Seismic Criteria

Table F Loading Combinations and Primary Stress Limits (Continued)

NOTES: (a) These stress criteria are not applied to a piping run within which a pipe break is considered to have occurred.

(b) Loading combinations 2 and 3, st ress limits for vessels, are also used in evaluating the effects of local loads imposed on vessels and/or piping, with the symbol P M changed to P L.

(c) The tabulated limits for piping are based on a minimum "shape fa ctor". These limits are m odified to incorporate the shape factor of the particular piping being analyzed.

(d) These load cases and limits apply only to the Pressurizer relief valve piping and supports.

(e) As an alternative to USAS B31.7, 1968, Class 1, 2, and 3, non-reactor coolant loop piping analysis may also be performed in accordance with ASME III, 1980 Edition (no Addenda). Material proper ties shall be from the original code of record (i.e., USAS B31.7, 1968). Associated stress limits shall be in accordance with ASME III, 1980 Edition (no Addenda) for Service Levels as shown below:

Load Combination Service Level A: Design Loading (Pressure, Weight, Other Mechanical Loadings, and Thermal where applicable) Service Level B: Design Loading + Design Earthquake Service Level C: Normal Operating Loadings + (Maximum Hypothetical Earthquake + (Fluid Transient Loading) (g)) Service Level D: Normal Operating Loadings + (Maximum Hypothetical Earthquake + Pipe Rupture (g))

(f) Support analysis will continue to be performed in accordance with the existing licensing basis (i.e., Seventh Edition, AISC, American Institute of Steel Construction). (g) Square-Root-Sum-of-the-Squares may be used to combine loads.

LIC-15-0086 Page 1 USAR Clean Pages USAR-Appendix F Information Use Page 9 of 40 Classification of Structures and Rev. 10 Equipment and Seismic Criteria

Table F Loading Combinations and Primary Stress Limits

Primary Stress Limits

Loading Combinations Vessels Piping (e) Supports (f)

1. Design Loading + P M < S M P M < 1.2S h Working Design Earthquake Stress P B + P L < 1.5S M P B + P M < 1.2S h Anchor Bolts F.S.>4.0 (d)

2. Normal Operating P M < S D P M < S D Within Loadings + (Maximum

Yield Hypothetical Earthquake Anchor Bolts + (Fluid Transient F.S.> 2.0 (d) Loadings)(g)) (b) (c)

3. Normal Operating P M < S L P M < S L Deflection of supports Loadings + (Pipe

limited to Rupture + Maximum maintain supported Hypothetical Earthquake(g)) equipment within (b) (a), (c) limits shown

USAR-Appendix F Information Use Page 10 of 40 Classification of Structures and Rev. 10 Equipment and Seismic Criteria

Table F Loading Combinations and Primary Stress Limits (Continued)

NOTES: (a) These stress criteria are not applied to a piping run within which a pipe break is considered to have occurred.

(b) Loading combinations 2 and 3, st ress limits for vessels, are also used in evaluating the effects of local loads imposed on vessels and/or piping, with the symbol P M changed to P L.

(c) The tabulated limits for piping are based on a minimum "shape fa ctor". These limits are m odified to incorporate the shape factor of the particula r piping being analyzed.

(d) These load cases and limits apply only to the Pressurizer relief valve piping and supports.

(e) As an alternative to USAS B31.7, 1968, Class 1, 2, and 3, non-reactor coolant loop piping analysis may also be performed in accordance with ASME III, 1980 Edition (no Addenda). Material proper ties shall be from the original code of record (i.e., USAS B31.7, 1968). Associated stress limits shall be in accordance with ASME III, 1980 Edition (no Addenda) for Service Levels as shown below:

Load Combination Service Level A: Design Loading (Pressure, Weight, Other Mechanical Loadings, and Thermal where applicable) Service Level B: Design Loading + Design Earthquake Service Level C: Normal Operating Loadings + (Maximum Hypothetical Earthquake + (Fluid Transient Loading) (g)) Service Level D: Normal Operating Loadings + (Maximum Hypothetical Earthquake + Pipe Rupture (g)) (f) Support analysis will continue to be performed in accordance with the existing licensing basis (i.e., Seventh Edition, AISC, American Institute of Steel Construction). (g) Square-Root-Sum-of-the-Squares may be used to combine loads.