ML102240513

Request for Additional Information Regarding Final Safety Analysis Report Related to Section 11

ML102240513
Person / Time
Site:	Watts Bar
Issue date:	08/19/2010
From:	Justin Poole Watts Bar Special Projects Branch
To:	Bhatnagar A Tennessee Valley Authority
Poole Justin/DORL/ 301-415-2048
References
TAC ME3945
Download: ML102240513 (4)

Text

August 19, 2010 Mr. Ashok S. Bhatnagar Senior Vice President Nuclear Generation Development and Construction Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801

SUBJECT:

WATTS BAR NUCLEAR PLANT, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING FINAL SAFETY ANALYSIS REPORT AMENDMENT RELATED TO SECTION 11 (TAC NO. ME3945)

Dear Mr. Bhatnagar:

By letter dated May 7, 2010 (Agencywide Documents Access and Management System Accession No. ML101340795), the Tennessee Valley Authority (TVA) submitted Final Safety Analysis Report (FSAR) Amendment 98 for Watts Bar Nuclear Plant, Unit 2. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by TVA in FSAR Amendment 98.

In an effort to complete the NRC staff review, enclosed is a request for additional information regarding FSAR Section 11.

A response is required within 30 days of receipt of this letter.

If you should have any questions, please contact me at 301-415-2048.

Sincerely,

/RA/

Justin C. Poole, Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391

Enclosure:

Request for Additional Information cc w/encl: Distribution via Listserv

Mr. Ashok S. Bhatnagar Senior Vice President Nuclear Generation Development and Construction Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801

SUBJECT:

WATTS BAR NUCLEAR PLANT, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING FINAL SAFETY ANALYSIS REPORT AMENDMENT RELATED TO SECTION 11 (TAC NO. ME3945)

Dear Mr. Bhatnagar:

By letter dated May 7, 2010 (Agencywide Documents Access and Management System Accession No. ML101340795), the Tennessee Valley Authority (TVA) submitted Final Safety Analysis Report (FSAR) Amendment 98 for Watts Bar Nuclear Plant, Unit 2. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by TVA in FSAR Amendment 98.

In an effort to complete the NRC staff review, enclosed is a request for additional information regarding FSAR Section 11.

A response is required within 30 days of receipt of this letter.

If you should have any questions, please contact me at 301-415-2048.

Sincerely,

/RA/

Justin C. Poole, Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391

Enclosure:

Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:

RidsOgcRp Resource RidsRgn2MailCenter Resource PUBLIC RidsNrrDorlLpwb Resource RidsNrrDirsIhpb Resource LPWB Reading File RidsNrrLABClayton Resource RidsNrrPMWattsBar2 Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr ADAMS Accession No. ML102240513 OFFICE LPWB/PM LPWB/LA IHPB/BC OGC LPWB/BC NAME JPoole BClayton UShoop DRoth SCampbell DATE 08 / 16 /10 08 / 16 /10 08 / 16 /10 08 / 17 /10 08 / 19 /10 OFFICIAL AGENCY RECORD

REQUEST FOR ADDITIONAL INFROMATION WATTS BAR NUCLEAR PLANT, UNIT 2 FINAL SAFETY ANALYSIS REPORT AMENDMENT 98 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-391

1. Table 11.2-5, Columns 6, 7, and 8.

a. Explain why these columns were added to the Final Safety Analysis Report (FSAR). Provide some detail as to their purpose, other than to match the Unit 1 FSAR.

b. Columns 7 and 8 are labeled no CD [condensate polishing demineralizer].

However, the magnitudes of the releases listed in both of these columns are closer to Column 5 (w/CD and mobile demineralizer) than they are to Column 6. Verify these are untreated releases as indicated.

c. What is the basis for the 3.6 E-5 uCI/cc limit used to calculate the steam generator blowdown (SGBD) contribution in Column 8?

d. What is the isotopic distribution of the SGBD release contributions?

e. Verify that releases consistent with Columns 7 and 8 (e.g., with SGBD releases) meet Title 10 of the Code of Federal Regulations (10 CFR) Part 20.

2. Revise Paragraph 11.2.6.5 to discuss limitations of untreated releases from the plant.

a. Table 11.2-5 does address compliance with 10 CFR Part 20. The table presents total curie release during different radiological waste configurations and compares them with the limit of RM 50-2 (5 Ci/yr limit). Table 11.2-5a (untreated) and Table 11.2-5b (treated) seem to demonstrate noncompliance and compliance, respectively, with 10 CFR Part 20.

b. Tables 11.2-5a and b do not demonstrate that releases from the plant are in accordance with the design objectives (found in FSAR Section 11.2.1), since they do not include SGBD contributions from tube leaks (objective (1)). In addition, Table 11.2-5a clearly demonstrates that liquid effluent processing is necessary to meet 10 CFR Part 20. Therefore, it is unclear how design objective (2) is demonstrated. Explain how FSAR Section 11.2.1 objectives (1) and (2) are met.

c. Statements added to paragraph 11.2.6.5 by Amendment 98 need clarification and justification.

i)

The first sentence implies that operating with releases consistent with Table 11.2-5a is acceptable, which is incorrect. These releases exceed the limits of 10 CFR Part 20.

Enclosure ii)

Also, nothing in this FSAR supports the statement that releasing untreated waste below 5E-7 uCi/cc will meet 10 CFR Part 20 Appendix B limits.

3. Table 11.3-10 (formerly 11.3-11) provided in Amendment 98 indicates the only change made is the table number. However, it appears that the entire table has been revised.

a. Provide basis for the revised dose number in Table 11.3-10.

b. It is unclear if this table is demonstrating releases within the design criteria of 10 CFR Part 50 Appendix I (e.g., per unit) or RM 50-2 (e.g., per site), as committed to in response to Question 8 of Section 11 in letter dated June 3, 2010 (ADAMS Accession Number ML101600477). Provide clarification.

c. The revised title indicates that the doses are for Unit 1 without TPC [Tritium Production Core]. If that is accurate; i) provide the estimated doses with Unit 2 operating, and ii) provide the basis for not including Unit 1 tritium production.

4. Revising section and table numbers impacts the NRCs Safety Evaluation Report.

Provide a cross-walk road map for the revised number of Chapter 11.