ML101600498

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Chapter 12 - Question 8 - FSAR Change Package
ML101600498
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Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 06/03/2010
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Office of Nuclear Reactor Regulation
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{{#Wiki_filter:003 - Chapter 12 - Question 8 - FSAR Change Package

1617 SOO PKG SAR CHANGE REQUEST SAR CHANGE PACKAGE NO. 1617 ORIGINATOR: Don Wilder ORGANIZATION/ADDRESS -S~E~-~D~EJ~E~Q~8-:=.2~N----- DATE: PHONE: 1/6/00 1363 CHANGE REQUIRED DUE TO: O' DCN/MODIFICATION* DATE IMPLEMENTEO JUSTIFICATION: o TECH SPEC CHANGe*: DATE IMPLEMENTED JUSTIFICATION: ~ OTHER* Remove excessive detail ~-i-'-{)~lJl-JUSTIFICATION: Information is contained in TS. ODCM. etc. This level of detail is inaopro-priate for the UFSAR. o Nonsignificant* JUSTIFICATION: ----------

  • Attach a marked up copy of applicable SAR page, table. revised figures, table of contents, list of tables. etc.

w;u:s A safety assessment/safety evaluation is required to accompany any technical SAR change. Nonsignificant changes do not require a safety assessment/evaluation. Contact Site Licensing organization if confusion or uncertain exists over whether a chan e is nonsi nificant. Phone: \\ 3", Prepared By: PROPOSED CHANGES HAVE BEEN COORDINATED WITH AND ARE CONCURRED BY THE SUPPORTING ORGANIZATIONS, IF APPLICABLE. --::z:==::-N"7A"::JM,.-E_~--n JtL{1P

  • SUPPORTING ORG DArE

~...,JJacsd~r-fr-l-~fIf:I<c;.r.r.:~--~ SITE ENGINEERING-DESIGNIMNE %r RADCON /3 {o~~ CHEMISTRY J l~hD.O ______....iiitiiiiiiiitiilOltilli.......,-____ i SITE ENGINEERING-SYSTEMS ').z?- Z,()()O Transmit to: Site Licensing Manager RIMS Management Services Living FSAR (Issued by Site Licensing)

      • Forward to Ori inator Amendment No.

__~ Dale:~ II

  • 1 Date:

Phone: Rejected 0 Licensing 0.sposition Approved JQ. Licensing Approval***: TVA 40505 (05-97) Page 1 of 1 NADP*7*1 (05-27.97)

12.3.4.1.2.3 Local Indicator-Alann Panel WBNP-l )1.61 7 5to 0 PIG With the exception ofthe main control room and Reactor Building upper and lower compartment , post accident monitors, each monitor has a locally mounted panel which contains an indicator, a visual and audible high radiation alann, and a power-on light. 12.3.4.1.2.4. Multipoint Recorders <Main Control Room O-M-12, 1-2-M-31l The area monitors are recorded on multipoint recorders on panels O-M-12, or 1*,2-M*31 in the MeR. 12.3,4.1.2.5 Monitor Sensitivity and Range The ranges ofthe instrumentation provided are given in Table 12.3-4. The area monitors set points, adjustable over the entire range, are determined by the radiation control group based on. operating background levels. The setpoints fQr the Reactor Building upper and lower companment post accident monitors are determined'by engineering analysis. 12.3.4.1.3 Area Monitor Calibration and Maintenance With the exception ofthe Reactor Building upper and lower compartment post accident monitors, periodic testin e e monitor includes a channel calibration erformed at least once per e c et and a channel 9pera *0 . test t IS performed at east once per quarte. Testing of e Reactor, g upper an lower compartment post acci ent monitors IS e cnbed by plant Technical ~pecifications. The channel calibration is the adjustment, as necessary, ofthe channel so that it responds within the required range and accuracy to known input from a radioactive calibration source. The channel calibration encompasses the entire channel, including the required sensor, alarm, interlock, display and trip functions. The channel calibration may be performed by means ofany series ofsequential, overlapping calibratioDS or total channel steps so that the entire channel is calibrated. The channel operational test (COT) is the injection ofa simulated or actual signal into the channel as close to the ~,ensor as practicable to verify the operability ofrequired alarm, interlock, display and trip functioDS. The COT includes adjustments, as necessary, ofthe required alarm, interlock. and trip setpoints so that the setpoints are within the required range and accuracy.

+--+-n.e~bmu-H-il.."t-...,iDl'I--eI~~ecksource function exposes the channel detector to a radioactive source for ail channels except those employing an ion chamber detector. The checksource function simulates a detector signal at the channel electronics in channels employing an ion chamber detector. The built-in checksource feature is used to verifY functional response ofthe detector and/or electronics during the performance ofthe channel operational test. This functiC?n is also used by operations personn s such as after maintenance, to rapidly determine channel operability.

'Z2 *S' 1'Y\\GlI\\.""",~ (II!. ""tIYI+I.~ f'I.Jio "LS1~ J 'l.1I\\J. ~ G h",Ylrle.~ ~~c>",~l ftag i, re.r~~~e~ re",c~\\~\\\\y ~~ reti" \\~ ~ ~e. "'e~~,,\\"~ SfS~.ct""-+'tMS1 k'-".e OO~t'\\aDr +"'-e. TVAc.~\\\\'o~+\\o\\'\\ flro~r~'M. froc..eJ.\\J~S. ____-----------r----- 12.3-19

WBNP-l 12.3.4.2.5 Sensitivity, Range and Set Point The permanently installed paniculate monitors located in the Auxiliary Building have a required range of 1.99E-8 to 7.96E-6 IJ.Cilcc. For the Reaetor Building instrument room particulate monitor, the required range is 1.08E-8 to 4.32E-6 ).lCi/cc. This required range is sufficient to detect 10 DAC hours ofairbome radionuclides expected in the area (i.e., Co-60, Cs-137. etc.). 12.3.4.2.6 Calibration and Maintenance This section applies only to pennanently installed monitors. The channel calibration is the adjustment, as necessary, ofthe ch~el so that it responds wiihin the required range and accuracy to known input from a radioactive calibration source. The channel calibration encompasses the entire channe~ including the required sensor, alarm, interlock, display and trip functions. The channel calibration may be performed by means ofany series ofsequential, overlapping calibrations or total channel steps so that the entire channel is calibrated. 'Z,'Vh.,o\\,\\-\\\\'S (\\" -.""\\-\\-.S r\\\\1 S 'Z.'5 "70 I o"vJ. '" c:.~ n.e.\\ of'!~-h~~ fe("-~rMeJ. eer-\\oJ. i <:.11\\.\\\\'f,,!'. re6'"\\t'co\\ bt t"'-e Te~1\\\\C41 "Sf'e Co; +i Co...\\-i6....S, t\\..e. OC <:.1"\\, or" +~ \\'JII. 0::4\\'.10",,+l'ell\\ f ('0~ro..- \\ roc..eJ" reS. c ec nsc e m81ntenance IS e onne as re Ulre. The channel operational test (COT) is the injection ofa simulated or actual signal into the channel as close to the sensor as*practicable to verifY the operability ofrequired alarm, interlock, display and trip functions. The COT includes adjustments, as necessary, ofthe required alarm, interlock, .and trip setpoints so that the setpoints are within the required range and accuracy. The built-in checksource function exposes the channel detector to a radioactive source. The built-in checksource feature is used to verify functional response ofthe detector andlor electronics during the performance ofthe channel operational test. This function is also used by operations personnel at other times, such as after maintenance, to rapidly determine channel operability. Periodic maintenance to change filters and to ensure proper sampler operation is performed at a frequency based upon length ofservice time for filters and sample equipment as determined by operational experience and trending. Maintenapce is performed, as necessary, ifabnonnalities are detected durin an ofthe above 12.3-23

000329 878 SAFETY ASSESSMENT/SCREENING REVIEW/SAFETY EVALUATION COVERSHEET Document No: SAR Change Package No. 1617 Screening Review Only 0 Safety Assessment/Screening Review 0 Plant WBN Affected Unites) Preparing Group 1 LEE-OFF Page _1_ of _,_ Rev. --.;;.o~_ '16 1" S0 0 pOK G Safety Assessment/Screening Review/Safety Evaluation ~ Procedure Exemption tJ Procedure Change Evaluation 0 Preparer Don Wilder Reviewer D. Faulkner Activity Number (Include Revision No.) DCN No. EDC No. TACF No. Special Test No. TSRF No. Procedure No. and PCF No. (if applicable) Procedure No. WRlWONo. SAR Change Request 1617 o Maintenance ~ Other (Identify) Comments: o Design Change o Engineering Document Change o Temporary Alteration o Special Test/Experiment o Temporary Shielding Request o Procedure Change o New Procedure Remove excessive detail from sections 12.3.4.1.3 and 12.3.4.2.6 of the UFSAR. WBP-Lee-OO-004 Revision: (Provide a brief summary of the reason for the revision to the SR. SA. or SE) Distribution: cc: EDM Preparer - Return original to originating document TVA 40518 (11.19981 Page 1 of 1 SPP*9.4*1 (11*23-1998 )

SAFETY ASSESSMENT FORM Document No: SAR Change Package No. 1617 I. SAFETY ASSESSMENT Page_1_ Of...::t:.- Rev. 0-- A. Description 1. Brief synopsis of the change, special test, experiment or condition including the systems, structures. and components affected. Include the number of the activity proposed (e.g., ECN/DCN No.* procedure No.). UFSAR Sections 12.3.4.1.3 and 12.3.4.2.6 details specific channel operational test (COT) intervals for the area radiation monitors and the airborne particulate monitors, respectively. This level of detail is not appropriate for the UFSAR, as it is not Important to the description of the plant or to the presentation of its safety analysis and design bases. The information concerning the COT intervals is given in the Technical Specifications, the Offsite Dose Calculation Manual (ODeM), and the TVA Calibration Program Procedure. SPP-6.7, and maintenance instructions. This change, SAR Change Request 1617. removes the specific Interval and instead refers to the Technical Specifications, the Offsite Dose Calculation Manual (aDCM), and the TVA calibration program procedures. This is consistent with the UFSAR treatment of calibration of other radiation monitors and instruments (e.g., sections 7.5.1.7.1, 7.6.7, and 11.4.4). The intent of this change is to allow an interval of 18 months between COTs for the radiation loops (radiation monitoring flow loops will continue to have a COT interval of three months). The interval is currently 3 months. The change substitutes a reference to the Technical Specifications, etc., for the numerical value of the COT interval. The COT will be performed at a frequency reqUired by the Technical Specifications, the Offsite Dose Calculation Manual (ODCM), and the TVA Calibration Program Procedure and maintenance instructions. The following are the affected monitors. According to the Radiation Monitoring Design Criteria, WB-DC-40-24, none of them perform a primary safety function, are required by the Technical Specifications. or are required by the ODeM. The calibration requirements for these monitors are contained in the TVA calibration program procedures. Area Radiation Monitors 1-RE-90-1 Spent Fuel Pool Area - Continuously monitors ambient radiation levels in the spent fuel pool area to assure that exposure rates do not exceed the prescribed radiation zone limits, and to provide early warning of abnormal process system operations. 1-RE.90.2 Personnel Air Lock - This monitor is located to indirectly mea"sure the airborne radioactivity in the primary containment under accident conditions. The monitor includes devices to transmit measured radiation exposure rate data to the Plant Computer System for display in the Technical Support Center. o-RE-90-3 Waste Packaging Area* Continuously monitors ambient radiation levels in the waste packaging area to assure that exposure rates do not exceed the prescribed radiation zone limits, and to provide early warning of abnormal process system operations. O-RE-90-4 Equipment Decontamination Area - Continuously monitors ambient radiation levels in the equipment decontamination room to assure that exposure rates do not exceed the prescribed radiation zone limits, and to provide early TVA 40674 [11.1998] Page 1of 1 SPP-9.4-3111-23-1998l

SAFETY ASSESSMENT FORM Document No: SAR Change Package No. 1617 Page _2_ of...::e.- Rev. 0--- warning of abnormal process system operations. O-RE-90-5 Spent Fuel Pool Pump Area - Continuously monitors ambient radiation levels in the area of the spent fuel pool pump to assure that exposure rates do not exceed the prescribed radiation zone limits. and to provide early warning of abnormal process system operations. 1-RE-90-6 Component Cooling Heat Exchanger Area - Continuously monitors ambient radiation levels in the area of the component cooling heat exchangers to assure that exposure rates do not exceed the prescribed radiation zone limits. and to provide early warning of abnormal process system operations. 1-RE-90-7 Sample Room - Continuously monitors ambient radiation levels in the Unit 1 sample room to assure that exposure rates do not exceed the prescribed radiation zone limits, and to provide early warning of abnormal process system operations. 1-RE-90-8 Aux Feedwater Pumps Area - Continuously monitors ambient radiation levels in the area of the. auxiliary feedwater pumps to assure that exposure rates do not exceed the prescribed radiation zone limits, and to provide early warning of abnormal process system operations. O-RE-90-9 Waste Evaporator Condensate Tank Area - Continuously monitors ambient radiation levels in the waste evaporator area to assure that exposure rates do not exceed the prescribed radiation zone limits, and to provide early warning of abnormal process system operations. 1-RE*90-10 CVCS Board Area - Continuously monitors ambient radiation levels in the CVCS Board area to assure that exposure rates do not exceed the prescribed radiation zone limits, and to provide early warning of abnormal process system operations. O-RE-90-11 Containment Spray and RHR Pump Area - Continuously monitors ambient radiation levels in the spent area of the Containment Spray Pumps and the RHR pumps to assure that exposure rates do not exceed the prescribed radiation zone limits. and to provide early warning of abnormal process system operations. 1-RE-90-59 Containment Refueling Floor* Continuously monitors ambient radiation levels In the area of the containment refueling floor to assure that exposure rates do not exceed the prescribed radiation zone limits. and to provide early warning of abnormal process system operations. 1*RE*90-60 Containment Refueling Floor - Continuously monitors ambient radiation levels in the area of the containment refueling floor to assure that exposure rates do not exceed the prescribed radiation zone limits. and to provide early warning of abnormal process system operations. 1-RE*90-61 Lower Compartment Instrument Room - Continuously monitors ambient radiation levels in the lower compartment instrument room to assure that exposure rates do not exceed the prescribed radiation zone limits, and to provide early warning of abnormal process system operations. O-RE*90-135 Main Control Room Radiation Monitor - Continuously monitors ambient radiation levels in the main control room to assure that exposure rates do not exceed the prescribed radiation zone limits, and to provide early warning of abnormal process system operations. O-RE-90-230 Condensate Demin Area - Continuously monitors ambient radiation TVA 40674 (11-1998] Page 1 of 1 SPP-9.4-3 (11-23-1998)

SAFETY ASSESSMENT FORM Document No: SAR Change Package No. 1617 Page _3_ of.:2-Rev..........0__ levels in the condensate demineralizer area to assure that exposure rates do not exceed the prescribed radiation zone limits, and to provide early warning of abnormal process system operations. O-RE-90-231 Condensate Demin Area* Continuously monitors ambient radiation levels in the condensate demineralizer area to assure that exposure rates do not exceed the prescribed radiation zone limits, and to provide early warning of abnormal process system operations. 2-RE-90-1 Spent Fuel Pool Area - Continuously monitors ambient radiation levels in the spent fuel pool area to assure that exposure rates do not exceed the prescribed radiation zone limits, and to provide early warning of abnormal process system operations. 2-RE-90-6 Component Cooling Heat Exchanger Area* Continuously monitors ambient radiation levels in the area of the component cooling heat exchangers to assure that exposure rates do not exceed the prescribed radiation zone limits, and to provide early warning of abnormal process system operations. 2-RE-90-7 Sample Room - Continuously monitors ambient radiation levels in the Unit 2 sample room to assure that exposure rates do not exceed the prescribed radiation zone limits,' and to provide early warning of abnormal process system operations. 2-RE-90-8 Aux Feedwater Pumps Area - Continuously monitors ambient radiation levels in the area of the Auxiliary Feedwater Pumps to assure that exposure rates do not exceed the prescribed radiation zone limits, and to provide early warning of abnormal process system operations. 2-RE-90-10 CVCS Board Area - Continuously monitors ambient radiation levels in the CVCS Board area to assure that exposure rates do not exceed the prescribed radiation zone limits, and to provide early warning of abnormal process system operations. 1-RE-90-280 Post Accident Sampling Room Unit 1 - Continuously monitors ambient radiation levels in the Post Accident Sampling Room to assure that exposure rates do not exceed the prescribed radiation zone limits, and to provide early warning of abnormal process system operations. Airborne Particulate Monitors O-RE-90-12 Spent Fuel Pool Area - Continuously monitors the spent fuel area for airborne particulate radioactivity and where normal occupancy is required either on a continuous basis or on an infrequent but routine basis. 1-RE-90*14 Sample Room Unit 1 - Continuously monitors the Unit 1 Sample Room for airborne particulate radioactivity and where normal occupancy is required either on a continuous basis or on an infrequent but routine basis. Q*RE-90-15 Holdup Valve Gallery General Spaces - Continuously monitors the holdup valve gallery general spaces for airborne particulate radioactivity and where normal occupancy is required either on a continuous basis or on an infrequent but routine basis. TVA 40674 (11-1998) Page 1 or 1 SPP-9.4-3 (11-23-19981

SAFETY ASSESSMENT FORM Document No: SAR Change Package No. 1617 Page _4_ of.:1-. Rev. _O~_ O-RE-90..16 Decontamination Area.. Continuously monitors the Decontamination Room for airborne particulate radioactivity and where normal occupancy is required either on a continuous basis or on an infrequent but routine basis. O-RE-90-17 Safety Injection Pump General Spaces.. Continuously monitors the Safety Injection Pump area for airborne particulate radioactivity and where normal occupancy is required either on a continuous basis or on an infrequent but routine basis. 1..RE..90..62 Lower Compartment Instrument Room.. Continuously monitors the Containment lower Compartment Instrument Room for airborne particulate radioactivity and where normal occupancy is required either on a continuous basis or on an infrequent but routine basis. O-RE-90-13. Shipping Bay - Continuously monitors the shipping bay for airborne particulate radioactivity and where normal occupancy is required either on a continuous basis or on an infrequent but routine basis. O-RE-90-138 Waste Packaging Room.. Continuously monitors Waste Packaging Room for airborne particulate radioactivity and where normal occupancy is required either on a continuous basis or on an infrequent but routine basis. 2. References (SARITechnical Specifications/etc.). UFSAR Section 7.5.1.7.1 Post Accident Monitoring Instrumentation Programs UFSAR Section 7.6.7 Loose Parts Monitoring System (LPMS) System Description UFSAR Section 11.4.4 Process and Effluent Radiological Monitoring and Sampling System Calibration and Maintenance UFSAR Section 12.3.4.1 Area Radiation Monitoring Instrumentation UFSAR Section 12.3.4.2 Airborne Particulate Radioactivity Monitoring Technical Specifications Section 3.3, Instrumentation Safety Evaluation Report and Supplements 1 through 20 WB*DC*40*24 Rev. 8. Radiation Monitoring Spp 6.7 Instrumentation Setpoint, Scaling, and Calibration Program, Rev. 0 O-RE-90-101. TVA Calculation: Demonstrated Accuracy Calculation for Auxiliary Building Vent Radiation Monitor Q-RE-90-135, TVA Calculation: Demonstrated Accuracy for Control Room Area Radiation Monitor WBN.EEB*EDQ1090*99005, TVA Calculation: Extending Channel Operational Test Frequency for Radiation Monitors Watts Bar Nuclear Data Evaluation of Channel Operational Test Data (RIMS 69000125497) TVA 40674 (11-19981 Pag~ 1of 1

SAFETY ASSESSMENT FORM Document No: SAR Change Package No. 1617 Page _5_ of..:1-Rev. _O~_ B. Safety Assessment Checklist (Form Spp-g.4-4) * (required for all changes) 6. Design Basis Document The Design Criteria does not address the frequency of the channel operational tests. This change does not contradict any statements nor affect any requirements of the Radiation Monitoring Design Criteria. This change is safe from a design basis document standpoint.

15. Equipment Failure Modes This change does not affect the manner in which any component functions, nor does it replace, add, or delete any equipment. No new equipment failure modes are created by this change. Therefore, this change is safe from an equipment failure mode perspective.
17. Equipment Reliability The subject radiation loops are comprised of several components. The loops include ratemeters with local and/or main control room indication, recorders, local audible alarms, main control room alarms, etc. No part of these loops provide a primary safety function nor do they fulfill any requirement of the ODCM. The demonstrated accuracy calculation for these radiation loops has determined that in order to maintain the accuracy of the radiation monitors, they must be calibrated every eighteen months (plus 25%). There are no other calibrations or functional checks required by the calculation. Changing the COT interval is consistent with the conclusions of the demonstrated accuracy calculations.

Corporate Engineering calculation WBN-EEB-EDQ 1090-99005 performed a review of radiation monitor loops to determine the reliability of the components. None of the components of the radiation loops were found to be outside the lias found" values (This indicates that the loop components were performing as required). In fact none of the components of the radiation loops were found outside the lias left" values (This indicates that the loop components were not even required to be recalibrated at their scheduled COT). WBN Site Engineering/Systems also performed an evaluation of the performance of the radiation monitor loop components. The results are documented in "Watts Bar Nuclear Data Evaluation of Channel Operational Test Data", (RIMS T6900125497). Of the components in the radiation loops that were found outside the lias found" values. a majority of them (11 of 18) were related to iodine detection channels. There are no iodine channels associated with the radiation monitors within.the scope of this change. Of the remaining components that were outside the lias found" values, all were associated with the local indicators or the loop recorders. The local indicators are not typically used for determining radiation in an area, and the recorders are used for trending. The utilization of the recorders does not require a precise value in order to provide trending. For TVA 40674 (11*1998) Page 1or 1

SAFETY ASSESSMENT FORM Document No: SAR Change Package No. 1617 Page _6_ of..:1.- Rev. _0 these non-safety related radiation monitors the most important attribute is the ability to alarm for a high radiation signal. None of the alert or high radiation alarms were found outside the Uas found" values. For the most important attribute of these non-safety related radiation loops, this evaluation demonstrates that the area monitors and airborne monitors within the scope of this change are and will perform reliably. There is no threat to nuclear safety with regards to equipment reliability from this change.

36. Radioactive Effluent (Liquid or Gaseous) Release Pathways This change does not affect any radioactive effluent release pathways nor any equipment that monitors such a pathway. It only affects the area monitors and the airborne particulate monitors. The radiation monitoring system will function in the same manner as it did before this change. This change is safe from a Radioactive Effluent (liquid or Gaseous) Release Pathway standpoint.

C. Acceptability from a Nuclear Safety Standpoint A determination if the. proposed activity is acceptable from a nuclear safety perspective. This includes a written justification for the acceptability. This change does not revise any system or component functions or operational logic. The subject radiation monitors do not perform any primary safety function, nor.do they contribute to the limitation or monitoring of effluent releases. Therefore, this change is acceptable from a nuclear safety perspective. TVA 40674 (11-1998) Page 1 of 1 SPP-9.4-3 (11-23-1998)

SAFETY ASSESSMENT FORM Document No: .SAR Change Package No. 1617 Page _7_ of.:l..- Rev. _0..;;....._ Do Review and Approvals Preparer: Don Wilder V;). tlas&~ Name Signature Date Reviewer: \\)~AJ F, FA-'L)C-~£~ 9~ 2= :l.J)L.. '3/1-YO, Name Signature Date Other:. .o~~~ 3kyGJZ) Reviewers Name Date (as appropriate) TVA 40674 (11-1998) Page 1 of 1 SPP-9.4-3 [11-23-1998)

SAFETY ASSESSMENT CHECKLIST Document No. SAR Change Package No. 1617 Page -,- of "\\,... Potential Impact On N/A Nuclear Safety 1. 0 ~ ASME Section XI 2. 0 I8J Chemistry Changes or Chemical Release Pathways 3. 0 181 Compensatory*Measure 4. 0 181 Control Room Habitability 5. 0 ~ Decay Heat Removal Capability 6. I8J 0 Design Basis Document 7. 0 181 Digital Upgrade (NRC Generic Letter 95-02) 8. 0 ~ Electrical Breaker Alignment Changes 9. 0 181 Electrical Loads 10. 0 I8J Electrical Separation/Isolation 11. 0 181 EMI/RFI Potential 12. 0 I8J Environmental Impact Statement (See SPP-5.5) 13. 0 181 Environmental Qualification Category 14. 0 181 Equipment Diversity 15. 181 0 Equipment Failure Modes 16. 0 181 Equipment Redundancy 17. 1&1 0 Equipment Reliability 18. 0 181 Erosion/Corrosion/MIC 19. 0 I8J Fire Protection (Appendix R) 20. 0 181 Hazardous Material 21. 0 181 Heavy Load Lifts or Safe Load Paths (NUREG-0612) 22. 0 181 Human Factors ~.). U I2SJ Ip..;an 11T1~nl or IIlO>> 24. 0 181 Instrument/Relay Settings 25. 0 181 Internal Flooding Protection (MELB) 26. 0 181 Internal/External Missiles 27. 0 181 Jet Impingement Effects 28. 0 181 Materials Compatibility 29. 0 181 Modification to Non-Seismic Areas in CB/AB TVA 40516 (08-1998) Page 1 or 2 SPP*9.4-4 (08-14-1998)

SAFETY ASSESSMENT CHECKLIST Document No. SAR Change Package No. 1617 Page l..- of -z-Potential Impact On N/A Nuclear Safety 30. 0 181 Physical Separation 31. 0 181 Pipe Breaks 32. 0 ~ Pipe Vibration 33. 0 ~ Pipe Whip 34. 0 ~ Primary Containment Integrity/Isolation 35. 0 181 Protective Coatings Inside Containment 36 ~ 0 Radioactive Effluent (Liquid or Gaseous) Release Pathways 37. 0 181 Radwaste System Changes 38. 0 181 Reactor Coolant Pressure boundary 39. 0 181 Reactor Core Parameters 40. 0 181 Requires an increase in operator staffing to complete newly required -actions 41. 0 181 Response Time of Emergency Safeguards Equipment 42. 0 181 Safety Injection/Core Cooling Capability 43. 0 181 Scaffolding 44. 0 ~ Secondary Containment Integrity/Isolation 45. 0 181 Security System 46, 0 ~ Seismic/Dead Weight 47, 0 181 Shield Building Integrity (SQNIWBN) 48. 0 jgJ Shutdown Reactivity Control 49, 0 jgJ Single Failure Criteria 50, 0 181 System Design Parameters ~1 n rs?I T 52. 0 181 Test and Retest Seaping Document (Post Modification Test) 53. 0 181 Tornado or External Flood Protection 54. 0 181 Toxic Gases 55. 0 181 Valve Alignment Changes 56. 0 181 Ventilation Cooling for Electronic Equipment 57. 0 jgJ Water Spray/Condensation TVA 40516 (08-1998) Page 1 of 2 spp*g.4-4 (08-14-1998)

SCREENING REVIEW FORM Document No: SAR change Package No. 1617 Page _1_ of..:::::.. Rev. _0__ A. Potential Technical Specification (TIS) Impact (List TS sections reviewed) Yes 0 No ~ Is a change to the TIS required for conducting or implementing the change (design or procedure), test, or experiment? Justification: This change does not involve any radiation monitors that are subject of the Technical Specifications. Therefore, there is no change to the Technical Specifications. If the answer is "Yes," a TIS change is required prior to implementation or the activity needs to be revised or canceled. B. Potential Safety Analysis Impact (List FSAR sections reviewed) Yes 0 No 181 Is this a special test, or experiment not described in the SAR? Does the proposed activity affect (directly or indirectly) any information presented in the SAR or deviate from the description given in the SAR? Yes r8J No 0 By changing: The system design or functional requirements: the technical content of text, tables, graphs, or figures? (For radwaste changes see Note in Appendix B for guidance.) If the answer is "Yes," process an FSAR change. Justification: UFSAR Sections 12.3.4.1.3 and 12.3.4.2.6 are being revised by SAR Change Request 1617. Does the proposed change involve new procedures or instructions or revisions thereof that: Yes 0 No ~ N/A 0 Differ with system operation characteristics from that described in the SAR? Yes 0" No ~ N/A 0 Conflict with or affect a process or procedure outlined, summarized, or described in the SAR? Justification: This change does not conflict with or affect any processes or procedures nor does it differ with any system operational characteristics that are described in the UFSAR If the questions are answered "No" or "N/A," the activity may be"implemented without a safety evaluation. If any question is answered "Yes." an SE is required. TVA 40673 [11.1998) Page 1 of 1 SPP*9.4-2 (11-23-19981

SCREENING REVIEW FORM Document No: SAR Change Package No. 1617 Page _2_ of -2:::...... Rev. _0..;....-_ c. Review and Approvals Preparer: Don Wilder c&wd ,/z,/~ Name Signature Date Reviewer: b~~ ~. F".. t..JelJt~ Qd:a,tL. 3/L,)O~ Name Signature Date Other: IJ.J/. ~ Y~~(J?? Reviewers Name/Organization Signa=~ ate (as appropriate) TVA 40673 (11*1998) Page 1of 1

SAFETY EVALUATION FORM Document No.: SAR Change Package No. 1617 Page 1 of C-Rev.: 0 A. Description and Accident Evaluation: Detailed description of the change, test, or experiment. including the design basis accident, and credible failure modes of activity. UFSAR Sections 12.3.4.1.3 and 12.3.4.2.6 details specific channel operational test (COl) interVals for the non-safety related area radiation monitors and the airborne particulate monitors, respectively. This level of detail is not appropriate for the UFSAR, as it is not important to the description of the plant or to the presentation of its safety analysis and design bases. The information concerning the COT intervals is given in the Technical Specifications, the Oftsite Dose Calculation Manual (ODeM), and the TVA Calibration Program Procedure and maintenance instructions. This change does impact the Safety Evaluation Report. Section 12.4 of Supplements 10 and 12 are affected. A search of docketed correspondence turned up no additional commitments to the NRC. The following radiation monitors are affected: Area Radiation Monitors 1~RE-90-1 Spent Fuel Pool Area 1~RE-90*2 Personnel Air Lock O-RE-90-3 Waste Packaging Area O-RE-90-4 EqUipment Decontamination Area O-RE-90-S Spent Fuel Pool Pump Area 1*RE-90-6 Component Cooling Heat Exchanger Area 1-RE*90-7 Sample Room 1-RE-90-a Aux Feedwater Pumps Area O-RE-90-9 Waste Evaporator Condensate Tank Area 1-RE-90-10 CVCS Board Area O-RE-90*11 Containment Spray and RHR Pump Area 1-RE-90-S9 Containment Refueling Floor 1-RE-90-60 Containment Refueling Floor 1-RE-90-61 Lower Compartment Instrument Room O-RE-90-135 Main Control Room Radiation Monitor Q-RE-90~230 Condensate Demin Area O-RE-90-231 Condensate Demin Area 2-RE-9Q-1 Spent Fuel Pool Area 2-RE-90-6 Component Cooling Heat Exchanger Area 2-RE-90-7 Sample Room 2-RE-90-8 Aux Feedwater Pumps Area 2-RE-90-10 evcs Board Area 1-RE-90-280 Post Accident Sampling Room Unit 1 Airborne Particulate Monitors O-RE-90-12 Spent Fuel Pool Area TVA 40676 (11-1998) Page 17 of 17 SPP-9.4-6 [11-23-19981

SAFETY EVALUATION FORM Document No.: SAR Change Package No. 1617 1-RE*90-14 Sample Room Unit 1 O-RE-90-15 Holdup Valve Gallery General Spaces O*RE-90*16 Decontamination Area O*RE-90-17 Safely Injection Pump General Spaces 1*RE*90*62 Lower Compartment Instrument Room O*RE*90*13 Shipping Bay O*RE-90*138 Waste Packaging Room Page 2 of (' Rev.: 0 This change, SAR Change Request 1617, removes the specific interval and instead refers to the Technical Specifications, the Offsite Dose Calculation Manual (ODCM), the TVA calibration program procedures. This is consistent with the UFSAR treatment of calibration of other radiation monitors and instruments (e.g., sections 7.5.1.7.1,7.6.7, and 11.4.4). The intent oflhis change is to allow an interval of 18 months between COTs for the radiation loops (radiation monitoring flow loops will continue to"have a COT interval of three months). The interval is currently 3 months. The change substitutes a reference to the Technical Specifications, etc., for the numerical value of the COT interval. The COT will be performed at a frequency required by the Technical Specifications, the Offsite Dose Calculation Manual (aDeM), and the TVA Calibration Program Procedure and maintenance instructions. The affected monitors do not perform a primary safety function. They are utilized for personnel protection. If a monitor detects high radiation, an alarm is generated to warn personnel in the area. The monitors can also be used by the operators as an aid in diagnosing leaks of radioactive material in the plant. They are not required to mitigate a design basis accident. Their failure as a result of a design basis accident is acceptable and does not threaten nuclear safety. B. Evaluation of Effects 8.1 May the proposed activity increase the probability of an accident previously evaluated in the SAR? Yes 0 No ~ Justification: The affected monitors do not perform a primary safety function and are not required to mitigate an accident previously evaluated in the SAR. This change revises the COT frequency for these non-safety related radiation monitors. It does not change their function or failure modes. Their failure does not threaten nuclear safety. Therefore, there is no increase in the probability of an "accident previously evaluated in the SAR. B 2 May the proposed activity increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the SAR? Yes 0 No 181 Justification: The affected monitors do not perform a primary safety function and are not required to mitigate an accident previously evaluated in the SAR. This change revises the COT frequency for these non*safety related radiation monitors. It does not change their function or failure modes. The demonstrated accuracy calculation for each of these radiation loops has determined that in order to maintain the accuracy of the radiation monitors, they must be calibrated every eighteen months (pius 25%). There are no other calibrations or functional checks required by the calculation. Changing the COT interval to eighteen months is consistent with the conclusions of the demonstrated accuracy calculations. The failure of a monitor does not threaten nuclear safety. Therefore. this change does not increase the probability of a malfunction of equipment important to safety previously evaluated in the SAR. TVA 40676 {11.1998) Page 17 of 17 SPP*9.4-6 (11*23*1998J

SAFETY EVALUATION FORM Document No.: SAR Change Package No. 1617 Page 3 of C Rev.: 0 8.3 May the proposed activity increase the consequences of an accident previously evaluated in the SAR? Yes 0 No~ Justification: The affected monitors do not perform a primary safety function and are not required to mitigate an accident previously evaluated in the SAR. This change revises the COT frequency for these non-safety related radiation monitors. It does not change their function or failure modes. Their failure does not threaten nuclear safety. Therefore, there is no increase in the consequences of an accident previously evaluated in the SAR. 8.4 May the proposed activity increase the consequences of a malfunction of equipment important to safety previously evaluated in the SAR? Yes 0 No 1:81 Justification: The affected monitors do not perform a primary safety function and are not required to mitigate an accident previously evaluated in the SAR. This change revises the COT frequency for these non-safety related radiation monitors. It does not change their function or failure modes. Sufficient accuracy is maintained by calibrations within the revised frequency. The failure of a monitor does not threaten nuclear safety. Therefore, there is no increase in the consequences of a malfunction of equipment important to safety previously evaluated in the SAR. 8.5 May the proposed activity create a possibility for an accident of a different type than any evaluated previously in the SAR? Yes 0 No ~ Justification: The affected monitors do not perform a primary safety function. This change revises the COT frequency for these non-safety related radiation monitors. The function and failure modes of the monitors have not changed. Therefore, there is no possibility for an accident of a different type than any evaluated previously in the SAR. 8.6 May-the proposed activity create a possibility for a malfunction of a different type than any evaluated previously in the SAR? Yes 0 No ~ Justification: The affected monitors do not perform a primary safety function. This change revises the COT frequency for these non-safety related radiation monitors. The function and failure modes of the monitors has not changed. Less frequent manipulations of the monitor electronics will reduce unavailability and the potential for human induced malfunctions. Therefore, there is no possibility for a malfunction of a different type than any evaluated previously in the SAR. B.7 May the proposed activity reduce the margin of safety as defined in the basis for any Technical Specification? YesD No~ Justification: None of the affected components are required by the Technical Specifications. Therefore, the margin of safety as defined in the Technical Specifications bases has not been reduced. C. Unrevlewed Safety Question Determination Conclusion The change. test. or experiment Does not involve an unreviewed safety question. rgJ Involves an unreviewed safety question and must be revised. canceled. or reviewed by the NRC prior to implementation. 0 Summarize why the activity does or does not constitute a usa. TVA 40676 (11-19981 Page 170' 17 SPP-9.4-6 (11.23-1998]

SAFETY EVALUATION FORM Document No.: SAR Change Package No. 1617 Page 4 of ~r__ Rev.: 0--- UFSAR Sections 12.3.4.1.3 and 12.3.4.2.6 details specific channel operational test (COT) intervals for the area radiation monitors and the airborne particulate monitors, respectively. This level of detail is not appropriate for the UFSAR, as it is not important to the description of the plant or to the presentation of its safety analysis and design bases. The information concerning the COT intervals is given in the Technical Specifications, the Offsite Dose Calculation Manual (aDCM), and the TVA Call~ratlon Program Procedure, SPP-6.7, and maintenance instructions. This change, SAR Change Request 1617, removes the specific interval and instead refers to the Technical Specifications. the Offsite Dose Calculation Manual (ODCM), and the TVA calibration program procedures. This is consistent with the UFSAR treatment of calibration of other radiation monitors and instruments (e,\\g., sections 7.5.1.7.1,7.6.7. and 11.4.4). The intent of this change is to allow an interval of 18 months between COTs for the radiation loops (radiation monitoring flow loops will continue to have a COT interval of three months). The interval is currently 3 months. The change substitutes a reference to the Technical Specifications. etc.* for the numerical value of the COT interval. The COT will be performed at a frequency reqUired by the Technical Specifications, the Offsite Dose Calculation Manual (ODCM), and the TVA Calibration Program Procedure and maintenance instructions. The affected monitors do not perform a primary safety function. They are not required to mitigate a design basis accident. This change, therefore, does not constitute a USQ. TVA 40676 [11-1998) Page 17 of 17 SPP-9.4-6 [11-23.1998)

SAFETY EVALUATION FORM D.ocument No.: SAR Change Package No. 1617 Page 5 of Rev.: 0 D. Reviews and Approvals Preparer: Reviewer: Reviewer: (PORC)I Other: Reviewers (as appropriate) lAs required by Technical Specification TVA 40676 (11.19981 Page 17 of 17 SPP*9.4-6l11.23.1998J}}

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