Letter Sequence Draft RAI |
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Results
Other: CNL-14-077, Responses to Degraded Voltage Issue Requests for Additional Information, ML102290358, ML102290360, ML102290361, ML102290362, ML102290363, ML102290364, ML102290365, ML102290366, ML102290367, ML102290368, ML102290383, ML102290384, ML102290385, ML102290386, ML102290387, ML102290388, ML102290389, ML102290390, ML102290391, ML102290392, ML102290403, ML102290404, ML102290405, ML102290406, ML102290407, ML102290408, ML102290409, ML102290410, ML102290411, ML102290414, ML102290439, ML102290440, ML102290441, ML102290442, ML102290443, ML102290444, ML102290445, ML102290446, ML102290447, ML102290448, ML102290458, ML102290459, ML102290460, ML102290461, ML102290462, ML102290463, ML102290464, ML102290465, ML102290466... further results
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MONTHYEARML1005500072010-03-11011 March 2010 Request for Additional Information Related to Licensee'S Final Safety Analysis Report Amendment 95 Related to Section 4.2.2, Reactor Vessel Internal Components Project stage: RAI ML1010405732010-04-0909 April 2010 Response to NRC Request for Additional Information Regarding Licensee'S Final Safety Analysis Report (FSAR) Amendment Related to Section 4.2.2, Reactor Vessel Internal Components. Project stage: Response to RAI ML1011303512010-05-0505 May 2010 Request for Withholding Information from Public Disclosure (Tac No. ME2731) Project stage: Withholding Request Acceptance ML1014500842010-06-23023 June 2010 Request for Additional Information Regarding Licensee'S Final Safety Analysis Report Amendment Related to Reactor Systems, Nuclear Performance and Code Review, Ansd Plant Systems Project stage: RAI ML1015402502010-06-24024 June 2010 Request for Additional Information Regarding Licensee'S Final Safety Analysis Report Amendment Related to Nuclear Performance and Code Review, Plant Systems, and Testing (Tac Nos. ME2731 and ME3091) Project stage: RAI ML1017903992010-06-28028 June 2010 Request for Additional Information (RAI) Regarding Licensee'S Final Safety Analysis Report Amendment Related to Section 4.2.2, Reactor Vessel Internal Components Project stage: Request ML1016200062010-06-29029 June 2010 Request for Additional Information Regarding Licensee'S Final Safety Analysis Report Amendment Related to Nuclear Performance and Code Review (Tac No. ME2731) Project stage: RAI ML1015304742010-07-0202 July 2010 Request for Additional Information Regarding Licensee'S Final Safety Analysis Report Amendment Related to Mechanical and Civil Engineering Systems Project stage: RAI ML1016000262010-07-0808 July 2010 Request for Additional Information Regarding Licensee'S Final Safety Analysis Report, Amendment Related to Quality and Vendor Branch Review Project stage: RAI ML1015303542010-07-12012 July 2010 Request for Additional Information Regarding Licensee'S Final Safety Analysis Report Amendment Related to Electrical Engineering Systems Project stage: RAI ML1018001562010-07-15015 July 2010 Request for Additional Information Regarding Licensee'S Final Safety Analysis Report Amendment Related to Chapter 8, Electric Power Project stage: RAI ML1023003272010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-4A (Dwg No. 1-47W845-5, R38) Project stage: Other ML1022904642010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-1 (Dwg No. 1-47W845-1, R56) Project stage: Other ML1023003282010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-4B (Dwg No. 1-47W845-7, R14) Project stage: Other ML1023003292010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-5 (Dwg No. 1-47W611-67-1, R8) Project stage: Other ML1023003302010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-6 (Dwg No. 1-47W611-67-2, R5) Project stage: Other ML1023003312010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-8 (Dwg No. 1-47W611-67-4, R5) Project stage: Other ML1023003322010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-9 (Dwg No. 1-47W611-67-5, R10) Project stage: Other ML1023003332010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-10 (Dwg No. 1-47W610-67-1, R27) Project stage: Other ML1023003342010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-10 Sh a (Dwg No. 1-47W610-67-1A, R16) Project stage: Other ML1023003352010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-11 (Dwg No. 1-47W610-67-2, R15) Project stage: Other ML1023003432010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-12 Sh a (Dwg No. 1-47W610-67-3A, R7) Project stage: Other ML1023003442010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-13 (Dwg No. 1-47W610-67-4, R17) Project stage: Other ML1023003452010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-11 Sh a (Dwg No. 1-47W610-67-2A, R8) Project stage: Other ML1023003462010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-12 (Dwg No. 1-47W610-67-3, R12) Project stage: Other ML1023003472010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-14 (Dwg No. 1-47W610-67-5, R14) Project stage: Other ML1023003482010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-14 (Dwg No. 1-47W610-67-5A, R2) Project stage: Other ML1023003492010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-16 (Dwg No. 1-47W859-4, R23) Project stage: Other ML1023003502010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-17 (Dwg No. 1-47W859-3, R18) Project stage: Other ML1023003512010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-18 (Dwg No. 1-47W859-2, R36) Project stage: Other ML1023003522010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-19 (Dwg No. 1-47W859-1, R47) Project stage: Other ML1023003602010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-23 (Dwg No. 1-47W611-70-1, R9) Project stage: Other ML1023003612010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-20 (Dwg No. 1-47W610-70-1, R23) Project stage: Other ML1023003622010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-21 (Dwg No. 1-47W610-70-2, R29) Project stage: Other ML1023003632010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-21A (Dwg No. 1-47W610-70-2A, R15) Project stage: Other ML1023003642010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-22 (Dwg No. 1-47W610-70-3, R17) Project stage: Other ML1023003652010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-24 (Dwg No. 1-47W611-70-2, R11) Project stage: Other ML1023003672010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-25 (Dwg No. 1-47W611-70-3, R4) Project stage: Other ML1023003682010-08-0505 August 2010 Final Safety Analysis Report Figure 9.2-25A (Dwg No. 1-47W611-70-4, R4) Project stage: Other ML1023003692010-08-0505 August 2010 Final Safety Analysis Report Figure 9.3-1 (Dwg No. 1-47W610-32-1, R15) Project stage: Other ML1023003962010-08-0505 August 2010 Final Safety Analysis Report Figure 9.5-25 (Dwg No. 1-47W610-82-1, R18) Project stage: Other ML1022903582010-08-0505 August 2010 Final Safety Analysis Report Figure 8.1.2 (Dwg No. 1-15E500-1, R31) Project stage: Other ML1022903602010-08-0505 August 2010 Final Safety Analysis Report Figure 8.1-2A (Dwg No. 1-15E500-2, R39) Project stage: Other ML1022903612010-08-0505 August 2010 Final Safety Analysis Report Figure 8.1-2B (Dwg No. 1-15E500-3, R19) Project stage: Other ML1022903622010-08-0505 August 2010 Final Safety Analysis Report Figure 8.1-3 (Dwg No. 1-45W700-1, R28) Project stage: Other ML1022903632010-08-0505 August 2010 Final Safety Analysis Report Figure 8.2-1 (Dwg No. 1-75W500, R18) Project stage: Other ML1022903642010-08-0505 August 2010 Final Safety Analysis Report Figure 8.3-6 (Dwg No. 1-45W760-211-8, R14) Project stage: Other ML1022903652010-08-0505 August 2010 Final Safety Analysis Report Figure 8.3-7 (Dwg No. 1-45W760-211-9, R16) Project stage: Other ML1022903662010-08-0505 August 2010 Final Safety Analysis Report Figure 8.3-8 (Dwg No. 1-45W760-211-10, R12) Project stage: Other ML1022903672010-08-0505 August 2010 Final Safety Analysis Report Figure 8.3-9 (Dwg No. 1-45W760-211-11, R13) Project stage: Other 2010-06-28
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Category:Request for Additional Information (RAI)
MONTHYEARML23166A1142023-06-15015 June 2023 Document Request for Watts Bar Nuclear Plant - Radiation Protection Inspection - Inspection Report 2023-03 ML23067A2372023-03-0808 March 2023 WB_2023-02_RP_inspection_doc_request ML23030A3512023-01-25025 January 2023 Notification of Watts Bar Nuclear Plant - Design Bases Assurance Inspection (Programs) and Initial Information Request ML22343A0692022-12-0808 December 2022 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML22227A0272022-08-11011 August 2022 NRR E-mail Capture - Request for Additional Information Related to Alternative Requests RP-11 for Sequoyah Nuclear Plant, Units 1 and 2, and IST-RR-9 for Watts Bar Nuclear Plant, Units 1 and 2 ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Revised the TVA Plants' Radiological Emergency Plans ML22115A1402022-04-25025 April 2022 NRR E-mail Capture - Requests for Confirmation of Information and Additional Information Regarding Watts Bar Nuclear Plant, Unit 2 Exemption Request Re 10 CFR Part 26 (L-2022-LLE-0017) ML22083A2372022-03-24024 March 2022 NRR E-mail Capture - Request for Additional Information and Confirmation of Information Related to Tva'S Request for Changes to Watts Bar Nuclear Plant, Units 1 and 2, Technical Specification 3.7.8 ML22056A3802022-02-25025 February 2022 Document Request for Watts Bar Nuclear Plant - Radiation Protection Inspection - Inspection Report 2022-02 ML21267A1392021-09-23023 September 2021 Document Request for Upcoming RP Inspection at Watts Bar ML21221A2602021-08-0909 August 2021 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise Watts Bar, Unit 1 Tech Specs Related to Continuous Opening of the Auxiliary Building Secondary Containment Enclosure Boundary ML21102A1312021-04-19019 April 2021 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Unit 1 ML21095A0422021-04-0202 April 2021 NRR E-mail Capture - Added Clarification to RAI 2 for Thot LAR ML21095A0402021-04-0202 April 2021 NRR E-mail Capture - Request for Additional Information Re Generic Letter 95-05 90-Day Report and LAR to Adjust Growth Rate for Thot (EPIDs L-2021-LRO-0003 and L-2021-LLA-0026) ML21095A0412021-04-0101 April 2021 NRR E-mail Capture - Revised Draft RAI - Combined RAI Set for Watts Bar Unit 2 90-Day Report and Thot LAR (EPIDs L-2021-LRO-0003 and L-2021-LLA-0026) ML21095A0442021-04-0101 April 2021 NRR E-mail Capture - Revised Draft RAI - Combined RAI Set for Watts Bar Unit 2 90-Day Report and Thot LAR (EPIDs L-2021-LRO-0003 and L-2021-LLA-0026) ML21091A0772021-04-0101 April 2021 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise Technical Specification 5.7.2.19, Containment Leakage Rate Testing Program ML21095A0462021-03-22022 March 2021 NRR E-mail Capture - Draft Request for Additional Information Regarding Tva'S Generic Letter 95-05 90-Day Report for Watts Bar Unit 2 ML21039A6402021-02-0808 February 2021 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise the Watts Bar Nuclear Plant, Unit 1 Technical Specifications Related to Steam Generator Tube Inspection Frequency ML21012A2032021-01-11011 January 2021 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise the Watts Bar UFSAR to Use Alternate Probability of Detection ML20350B5592020-12-15015 December 2020 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Adopt Traveler TSTF-490 Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec ML20338A3202020-12-0303 December 2020 Notification of an NRC Fire Protection Team Inspection (NRC Inspection Report 05000390/2021011 and 05000391/2021011) and Request for Information ML20322A4412020-11-17017 November 2020 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise TS 3.7.11 Related to the MCR Chiller Replacement ML20322A4392020-11-0505 November 2020 NRR E-mail Capture - Draft Request for Additional Information Regarding Tva'S Request to Revise TS 3.7.11 Related to the MCR Chiller Replacement ML20308A3512020-11-0202 November 2020 Request for Additional Information on WBN Request for Exemption from 10 CFR Part 73, Appendix B, Section VI for the Conduct of an Annual Force-on-Force Exercise (EPID L-2020-LLE-0165 (COVID-19)) ML20253A1782020-09-0909 September 2020 Emergency Preparedness Program Inspection Request for Information ML20266G4592020-08-14014 August 2020 Notification of Inspection and Request for Information ML20196L8622020-07-14014 July 2020 NRR E-mail Capture - Watts Bar Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Request to Implement the Full Spectrum LOCA Methodology ML20086G4802020-03-26026 March 2020 NRR E-mail Capture - Request for Additional Information for WBN2 Request Measurement Uncertainty Recapture Power Uprate (L-2019-LLS-0000) - Part 2 ML20085G3572020-03-25025 March 2020 NRR E-mail Capture - Request for Additional Information for WBN2 Request Measurement Uncertainty Recapture Power Uprate (L-2019-LLS-0000) ML20084M1942020-03-24024 March 2020 NRR E-mail Capture - Request for Additional Information for WBN2 Request Measurement Uncertainty Recapture Power Uprate (L-2019-LLS-0000) ML20083J3952020-03-12012 March 2020 NRR E-mail Capture - Draft Request for Additional Information for WBN2 Request Measurement Uncertainty Recapture Power Uprate (L-2019-LLS-0000) ML19340A6842019-12-0505 December 2019 NRR E-mail Capture - Request for Additional Information for WBN2 Request for One-Time Extension of Completion Time for TS 3.7.8 (L-2019-LLA-0020) ML19218A0302019-08-0505 August 2019 NRR E-mail Capture - Watts Bar Nuclear Plant - Second-Round Request for Additional Information Related to Application to Revise Technical Specifications Regarding DC Electrical Systems, TSTF-500, Revision 2 ML19218A0282019-07-25025 July 2019 NRR E-mail Capture - Watts Bar Nuclear Plant - Draft Second-Round Request for Additional Information Related to Application to Revise Technical Specifications Regarding DC Electrical Systems, TSTF-500, Revision 2 ML19186A4352019-07-0505 July 2019 NRR E-mail Capture - Watts Bar Nuclear Plant - Correction to Final Request for Additional Information Related to Application to Adopt 10 CFR 50.69 ML19169A3592019-06-18018 June 2019 NRR E-mail Capture - Watts Bar Nuclear Plant - Final Request for Additional Information Related to Application to Adopt 10 CFR 50.69 ML19148A7912019-05-28028 May 2019 NRR E-mail Capture - Sequoyah Nuclear Plant and Watts Bar Nuclear Plant - Final Request for Additional Information Related to Request for Alternative to OM Code Requirements ML19106A0462019-04-15015 April 2019 NRR E-mail Capture - Watts BAR, Units 1 and 2 Request for Additional Informatin (RAI) Regarding Changes to Technical Specifications Sections 3.8.1, 3.8.7, 3.8.8, and 3.8.9 ML19071A3542019-03-0808 March 2019 NRR E-mail Capture - Watts Bar Nuclear Plant - Final Request for Additional Information Related to Request to Adopt TSTF-425 to Relocate Specific Surveillance Frequency Requirements to Licensee-Controlled Program ML18313A2202018-11-0707 November 2018 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML18282A6372018-10-0909 October 2018 NRR E-mail Capture - RAIs (Final) - LAR to Revise the Steam Generator Technical Specifications for Watts Bar Nuclear Plant, Unit 2 ML18270A2362018-09-26026 September 2018 NRR E-mail Capture - Watts Bar Units 1 and 2 RAIs - Modify TS 3.8.9 Completion Time for Inoperable 120V AC Vital Buses (L-2018-LLA-0050) ML18240A0702018-08-27027 August 2018 NRR E-mail Capture - RAI for Watts Bar Unit 2 Tpbars LAR and Watts Bar Units 1 and 2 LAR Related to Fuel Storage ML18199A1822018-07-17017 July 2018 NRR E-mail Capture - Request for Additional Information Regarding Watts Bar Unit 1 Extension of Surveillance Requirement Intervals ML18123A3942018-05-0303 May 2018 NRR E-mail Capture - Request for Additional Information Unit 2 Cycle 1 Steam Generator Tube Inspection Report ML18057A6372018-02-23023 February 2018 NRR E-mail Capture - Request for Additional Information Related to TVA Fleet Topical Report TVA-NPG-AWA16 - EPIC: L-2016-TOP-0011) ML18031A6592018-02-0606 February 2018 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Revise Technical Specification 4.2.1 and Technical Specifications Related to Fuel Storage ML18016A0112018-01-12012 January 2018 Draft Request for Additional Information Exigent Amendment Request for Inoperable Reactor Coolant Temperature Indication ML17226A0032017-08-11011 August 2017 NRR E-mail Capture - Watts Bar, Unit 1 - Final Request for Additional Information Concerning Request to Amend Turbine Trip Low Fluid Oil Pressure Reactor Protection System Trip Setpoint 2023-06-15
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Text
REQUEST FOR ADDITIONAL INFORMATION WATTS BAR UNIT 2 ODCM REVIEW
- 1. Surveillance Requirement 2.0.2 is not adequate to prevent surveillance frequency creep (e.g., an annual surveillance could be performed every 15 months indefinitely and still meet this ODCM requirement as written). In addition to the 1.25 times the frequency interval grace period provided in paragraph 4.0.2.a of NUREG 1301, paragraph 4.0.2.b specifies that three consecutive surveillances not exceed 3.25 times the applicable surveillance frequency interval. Revise the ODCM in accordance with (IAW) NUREG 1301 4.0.2.b or provide a technical justification demonstrating the adequacy of the current deviation.
- 2. Surveillance Requirement 2.0.2 is not IAW NUREG 1301 paragraph 4.0.3 which specifies that the time limit for an Action Requirement start at the time the non-performance of the surveillance is identified, but then allows a delay of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to complete the surveillance. Revise the ODCM IAW NUREG 1301 paragraph 4.0.3, or provide a technical justification demonstrating the adequacy of the current deviation.
- 3. Tables 2.1-1 and 2.1-2 are not IAW NUREG 1301, Tables 4.3-8 and 4.3-9, respectively, in that several Channel Operational Test (COT) frequency intervals are listed as every 276 days (3Q) instead of every 92 days (Q) per NUREG 1301 (see ODCM Table 3.1for surveillance frequency designations). Also, this deviation from NUREG 1301 is not identified and discussed in ODCM Appendix B. Provide a technical basis demonstrating the adequacy of this relaxation of the COT frequency, or revise the ODCM IAW NUREG 1301.
- 4. Table 2.1-1 footnotes (5) & (6) are not IAW NUREG 1301, Table 4.3-8 in that they inappropriately limit the scope of the COT. Provide a technical basis for this narrowing of the COT scope, or revise the ODCM IAW NUREG 1301.
- 5. Tables 1.1-2 and 2.1-2 indicate that the operability and surveillance requirements (respectively) for the Condenser Vacuum Exhaust Iodine and Particulate monitor were deleted in revision 5 to the ODCM. Revise the ODCM IAW NUREG 1301 with appropriate operability and surveillance requirements for this monitor, or provide a technical basis demonstrating the adequacy of the current deviation.
- 6. Foot notes (6), (7) & (10) to Table 1.1-2 all allow their respective monitors to be considered operable without isokinetic sampling. Provide a technical basis for determining that these monitors will provide representative sampling.
- 7. Foot note (5) to Table 1.1-2 states that the operability requirement for the Shield Building Iodine/Particulate monitor applies to charcoal and particulate filters, does not apply to detection channels. Define an operable charcoal or particulate filter. Provide a technical basis for why the detection channel for this monitor does not have to be operable.
- 8. Table 2.1-2 is not IAW NUREG 1301, Table 4.3-9 in that it does not specify weekly channel checks for the iodine/particulate monitors. The discussion in ODCM Appendix B item 3 does not explain how weekly detection channel tests are redundant with daily flow checks, and therefore are not applicable. Provide a revised technical basis for this deviation from NUREG 1301 or revise the ODCM IAW NUREG 1301.
- 9. Table 2.2-1 is not IAW NUREG 1301, Table 4.11-1in that the frequency of sampling continuous liquid effluent releases are specified as daily, monthly and quarterly grab samples instead of the continuously collected composite samples specified in NUREG 1301. ODCM Appendix B item 5 identifies this as a deviation from NUREG 1301.
However the only basis given is that it is consistent with the SQN effluents program.
This is not an adequate basis. Provide an adequate technical basis as to how representative samples are collected from the WBN liquid release streams or revise the ODCM IAW NUREG 1301.
- 10. Table 2.2-2, foot notes 3 & 7, are not IAW NUREG 1301. ODCM Appendix B item 6 identifies this as a deviation from NUREG 1301. However the only basis given is that it is consistent with the SQN effluents program. This is not an adequate basis. Provide an adequate technical basis as to how noble gas samples are collected from the WBN following reactor power changes or revise the ODCM IAW NUREG 1301.
- 11. Table 2.3-1, foot note 8 appears to be inconsistent with groundwater sampling specified in Table 9.1. Explain and/or resolve this apparent conflict.
- 12. Surveillance Requirement 2.3.3 erroneously states that the Interlaboratory Comparison Program is described in ODCM Section 9.0. The description contained in ODCM Section 9.4 Interlaboratory Comparison Program, is inadequate in that it provides little more than a restatement of the requirement in Control 1.3.3 and Surveillance Requirement 2.3.3. Revise the ODCM IAW NUREG 1301 paragraph 4.12.3. In addition, ODCM Section 9.4 contains a reference to providing an EPA program code designation in lieu of a results summary. Delete this reference or provide a technical basis for why this is acceptable.
- 13. The list of radioactive materials at the bottom of page 51 appears to be missing C-14.
Correct or explain why appropriate.
- 14. Appendix C, the ODCM Revision Process item 1.2 can be read to imply incorrectly that the acceptance criteria in 10 CFR 50.59 apply to the ODCM revision process (See 10
CFR 50.59(b)(4), and NEI 96-07 Rev.1, for guidance on 10 CFR 50.59 implementation).
Revise the change process in ODCM Appendix C or provide a justification why no change is appropriate.
- 15. Equation 6.11: the subscript Wai to the variable A, in this equation should be revised to read Waij to indicate that it is organ specific. Correct or explain why appropriate.
- 16. Table 9.1 is not IAW NUREG 1301, Table 3.12-1in that:
- a. No control samples are provided for milk, fish, or food products;
- b. Only one sample of a commercially important, and one sample of a recreationally important, fish species is provided where as NUREG 1301specifies one sample of each fish species that is commercially or recreationally important;
- c. The frequency of sampling food products does not specify enhanced sampling for products that are harvested more than once a year IAW NUREG 1301, Table 3.12-1, foot note (9).
Revise the ODCM IAW NUREG 1301, Table 3.12-1, or provide a technical justification demonstrating the adequacy of each of the above deviations.
- 17. Table 9.2 locations for milk sampling, are not consistent with the information in WBN2 FSAR, Table 11.3-8. Resolve this inconsistency, or provide a technical basis why no change is appropriate.
- 18. Foot note 1 to Table 9.1 indicates that REMP monitoring sample locations are given in Table 9.2. However, no locations for food product sampling are included in Table 9.2.
In addition, Table 11.3-8 of the FSAR gives 16 garden locations as dose pathway points of interest near the plant. Resolve these inconsistencies, or provide a technical basis why no change is appropriate.
- 19. ODCM Appendix B items 6.h & j, discuss the basis for sampling requirements in Table 2.2-2 (associated with the TPBAR operations) that appear to have been deleted in ODCM revision 11 (items H, I, & J?). Correct or explain why it is not appropriate for this combined ODCM to address the gaseous effluent sampling associated with the TPBARs.
- 20. ODCM Appendix B item 11, gives the basis for Controls/Surveillance Requirement 1/2.2.1.4 which is not in the current draft of the ODCM. Correct or explain why appropriate.
- 21. ODCM Appendix B item 15, states that the definition of a member of the public is consistent with 10 CFR 20, not NUREG 1301, as a basis for establishing the WBN unrestricted area boundary on opposite side of the Tennessee River (as indicated on
Figure 3.1). Does the licensee have the legal authority to limit or control access to the Tennessee River consistent with the Part 20 definition of the controlled area? Provide a technical basis, and justification, for including a navigable river within the WBN controlled area.