Text

Responses to NRC Acceptance Review Questions Regarding Essential Raw Cooling Water and Component Cooling System License Amendment Request
	ML15197A357
Person / Time
Site:	Watts Bar
Issue date:	07/14/2015
From:	James Shea; Tennessee Valley Authority
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML15202A267	List: CNL-15-147, Responses to NRC Acceptance Review Questions Regarding Essential Raw Cooling Water and Component Cooling System License Amendment Request;
References
	CNL-15-147, TAC MF6376
	Download: ML15197A357 (75)
	v • d • e

Tennessee Viltey Authority, 1 101 Market Street, Chattanooga, Tennessee 37402 cNL-1 5-147 July 14,2015 10 cFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001

Subject:

Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NFP-90 NRC Docket No. 50-390 Responses to NRC Acceptance Review Questions for Watts Bar Nuclear Plant Unit 1 Essential Raw Cooling Water and Component Cooling System License Amendment Request (TAC No. MF6376)

1. Letter from TVA to NRC, "Watts Bar Nuclear Plant Unit 1 - Application to Revise Technical Specifications for Component Cooling Water and Essential Raw Cooling Water to Support Dual Unit Operation (TS-WBN-1 5-13)," dated June 17, 2015 [M11517044741

2. Emailfrom NRC to TVA, "Preliminary Draft RAls Associated with Proposed WBN 1 ERCW and CCS Technical Specifications LAR," dated July 2,2015

3. Letter from NRC to TVA, "Watts Bar Nuclear Plant, Unit 1 - Supplemental lnformation Needed for Acceptance of Requested Licensing Action Regarding Application to Add Technical Specifications to Support Dual-Unit Operations (TAC No. MF6376),'dated July 9, 2015

[M115187A4031 By letter dated June 17, 2015, Tennessee Valley Authority (TVA) submitted a request for a change to Facility Operating License No. NPF-90 for Watts Bar Nuclear Plant (WBN) Unit 1 (Reference 1). The proposed change would create new Technical Specifications (TS)3.7.16, "Component Cooling System (CCS) - Shutdown," and TS 3.7.17, "Essential Raw Cooling Water (ERCW) System - Shutdown," to support dual unit operation of WBN Units 1 and 2. ln addition, changes were proposed to TS 5.7.2.18, "Safety Function Determination Program," and LCO 3.0.6 Bases to adopt TSTF-273-A. By email dated July 2,2015, the Nuclear Regulatory Commission (NRC) provided requests for additional information (RAl) on the proposed WBN Unit 1 license amendment (Reference 2).

References:

U.S. Nuclear Regulatory Commission cNL-1 5-147 Page 2 July 14,2015 By letter dated July 9, 2015, the NRC requested supplemental information associated with the proposed WBN Unit 1 license amendment (Reference 3). provides the TVA responses to the Reference 3 supplemental information requests. As a result of the TVA response to NRC Acceptance Review Question 1, proposed TS 3.7.16, TS 3.7.17, and the associated Bases have been revised. The proposed changes to TS 5.7.2.18 and LCO 3.0.6 Bases are being withdrawn from the license amendment request. Attachment 1 to Enclosure 1 provides the updated versions of WBN Unit 1 TS 3.7.16 and Bases. Attachment 2 to Enclosure 1 provides the updated versions of WBN Unit 1 TS 3.7.17 and Bases. provides the TVA responses to the Reference 2 RAls.

Consistent with the standards set forth in Title 10 of the Code of Federal Regulations (10 CFR) 50.92(c), TVA has determined that the response, as provided in this letter, does not affect the no significant hazards considerations associated with the proposed license amendment to add TS 3.7.16 and TS 3.7.17 previously provided in Reference 1. TVA has further determined that the proposed amendment still qualifies for a categorical exclusion from environmental review pursuant to the provisions of 10 CFR 51.22(cX9). However, the no significant hazards considerations associated with the proposed license amendment to revise TS 5.7.2.18 is no longer required, as this change is being withdrawn from the license amendment request. Additionally, in accordance with 10 CFR 50.91(b)(1), TVA is sending a copy of this letter and the enclosures to the Tennessee Department of Environment and Conservation.

There are no new regulatory commitments associated with this letter. Please direct any questions concerning this matter to Gordon Arent at (423) 365-2004.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 14th day of July 2015.

Respectfully, Digitally rigned by J-W shea J. W. S h e a il*Id,I"{-,i"}.n',-- J.w.shea hter2o15.07'1421:3er34@' Vice President, Nuclear Licensing Enclosures cc: See Page 3

U.S. Nuclear Regulatory Commission cNL-1 5-147 Page 3 July 14,2015

Enclosures:

1. Responses to NRC Acceptance Review Questions Associated with WBN Unit 1 ERCW and CCS License Amendment Request

2. Responses to NRC RAls for WBN Unit 1 ERCW and CCS License Amendment Request cc (w/Enclosures):

U.S. Nuclear Regulatory Commission, Region ll NRC Senior Resident lnspector - Watts Bar Nuclear Plant, Unit 1 NRC Project Manager - Watts Bar Nuclear Plant, Unit 1 Director - Division of Radiological Health - Tennessee State Department of Environment and Conservation

ENCLOSURE 1 Responses to NRC Acceptance Review Questions Associated with WBN Unit 1 ERCW and CCS License Amendment Request Backqround By letter dated June 17, 2015, Tennessee Valley Authority (TVA) submitted a request for a change to Facility Operating License No. NPF-90 for Watts Bar Nuclear Plant (WBN) Unit 1 (Reference 1). The proposed change would create new Technical Speciflcations (TS) 3.7.16, ';Component Cooling System (CCS) - Shutdown," and TS 3.7.17, "Essential Raw Cooling Water (ERCW) System - Shutdown," to support dual unit operation of WBN Units 1 and2. By letter dated July 9, 2015, the Nuclear Regulatory Commission (NRC) requested slpplemental information associated with the proposed WBN Unit 1 license amendment (Reference 2). The TVA responses to the NRC's request for supplemental information are provided below. NRC Acceptance Review Question I Proposed CCS fS 3.7.16 and ERCW Sysfem TS 3.7.17 include APPLICABILIW NOTE b, which sfafes that the limiting conditions for operation (LCOs) are not applicable "When complying with Required Actions to be in MODE 5." The only iustification prouided in the submittalforthis MODE APPLICABILIW exclusion rs sfafed in the proposed Bases forthese Technicat Specifications (ISs), which refer to proposed additions to LCO 3.0.6 Bases consisfent with Technbat Specifications lask Force (TSTF) TravelerTSTF-273-A. TSTF'273-A clarifies the Safety Function Determination Program (SFDP) process by specifying that assuming a single faiture orloss of electrical power when pertorming an analysisis nof required. To adopt a ISTF change the licensee must state that the reasoning for the change applies for its facility and specificatty how it applies to the plant'specific licensing basrs. The submittatdid not provide justification forthe inclusion of APPLICABILITY NOTE b. Also, the retationship of the proposed TSTF-273-A changes to the proposed CCS and ERCW ISs was not afticulated. The staff needs fhis information to understand the application of the proposed exception and SFDP clarification to the interpretation of the proposed CCS and ERCW ISs. For example, the staff postulated a scenaio in which the MODE APPLICABILITY NOTE b exception may result in the inability to complete required actions of other ISs. Speci/ically, TS 3.8.1 (AC falternating cunentl Sources - Operating), ACTTON G, requires in the event of a /oss of offsite power with /oss of an onsite emergency power train that lJnit 1 be in Mode 5 in 37 hours. The licensee has acknowledged that in the event that this postulated scenario occurs shortly following a unit shutdown it may be incapable of completing this required action in the specified time period without ensuriig the availabitity of the additionalCCs and ERCW pumps that the proposed ISs would make avaitable; however, the MODE APPLICABILITY NOTE b exception appears to exclude requiring the availability of these pumps in the event of a TS-required shutdown. Provide information to justify and explain the inclusion of APPLICABILTY NOTE b in the proposed ISs 3.7.16 and 3.7.17. Also, clearly articulate the relationship of the proposed 'adoption of TSTF-273-A changes to the proposed CCS and ERCW ISs. A// known scenarios similar to that of IS 3.8.7 discussed above should be identified and discussed. TVA Response E1-1

ENCLOSURE 1 Responses to NRG Acceptance Review Questions Associated wlth WBN Unit I ERCW and CCS License Amendment Request The Applicability statements of TS 3.7.16 and TS 3.7.17, as submitted in Reference 1, have been revised by removing the exception of.'When complying with Required Actions to be in MODE 5.' ln order to help determine the Required Actions to address the differences in the requirements relative to a TS-required shutdown and operation in Mode 4 or 5, the decision tree below was developed. ,/,/' \\ ,r'\\ . pio6r?I urrr s,ooc L r. t ot _/\\ ,/ \\_ VTRlrY RC3 uloPls OPfiAttf AIID ?-! fff I otctARt Bim totr tf{oe AilD EI{TER tm t.4,7 Ac?ilo?rt T3 3.7_t6 AHO T3 3"7J7 ( ../ TS \\ REq,O 3/D? zuspfr*B t co t o t AttD alt t@ Acnor.s Rtqutnmc MoDE cHAilGES Uilnt OTI.E RHN TOOP NESTONEO TO OPENADT^E STATUT NO t 5 f /-.--.------J j;,.*;Hn r'oPS r*o, *, I MODI T rl 0E 5? .?-- E1-2

ENCLOSURE 1 Responses to NRG Acceptance Review Questions Associated with WBN Unit I ERCW and CCS License Amendment Request The proposed changes to TS 3.7.16 and TS 3.7.17 (and associated Bases) are provided in Attachments 1 and 2 to this enclosure, respectively. With these changes to TS 3.7.16 and TS 3.7.17 and the withdrawal of the proposed changes to TS 5.7.2.18 and LCO 3.0.6 Bases, Attachments 1 and 2 to this enclosure entirely replace Attachments 1,2,3 and 4 to Enclosure 1 provided in TVA lefter dated June 17, 2015 (Reference 1). The Applicability statements for TS 3.7.16 and TS 3.7.17 have been revised with the addition of a new Note b to recognize that the additional CCS and ERCW System requirements are not required, if either unit has been shutdown for greater than 48 hours. TS 3.7.16 Condition A and TS 3.7.17 Condition A provide the Required Actions for an inoperable CCS or ERCW train, respectively, when complying with Required Actions to be in Mode 5. In this condition, adequate capability exists to cool down both units or cool down one unit while mitigating a loss of coolant accident in the other unit. Therefore, consistent with Required Action B.1 of LCO 3.4.6, "RCS Loops - MODE 4,' TS 3.7.16 and TS 3.7.17, Required Action A.1 requires the unit to be placed in Mode 5 in 24 hours. The new proposed Condition B provides Required Actions for one inoperable CCS/ERCW train when not complying with Required Actions to be in Mode 5. These Required Actions maintain the unit in Mode 4 with decay heat removal provided by two operable reactor coolant system (RCS) loops with one RCS loop in operation. Maintaining the unit in Mode 4 provides conditions for additional methods of decay heat removal and minimizes the likelihood of a situation where the decay heat and residual heat of the unit may exceed the capability of the available residual heat removal (RHR) loop, resulting in the possibility of an unintentional Mode change. Condition C provides actions in Mode 4 when two CCS / ERCW trains are inoperable. Required Action C.1 requires immediate action be taken to restore one of the CCS / ERCW trains to an operable status, as no RHR train is available to support the heat removal function. This action is consistent with LCO 3.4.6, 'RCS Loops - MODE 4," Required Action B.1 for the Condition of one required RHR loop inoperable and no RCS loops OPERABLE. Required Action C.1 is modified by two Notes. Note 1 indicates that all required Mode changes or power reductions are suspended until one CCS / ERCW train is restored to an operable status. ln this case, LCO 3.0.3 is not applicable because it could force the plant into a less safe condition. Note 2 indicates that the applicable Conditions and Required Actions of LCO 3.4.6 be entered for RHR loops made inoperable by the inoperable CCS / ERCW trains. This is an exception to LCO 3.0.6 and ensures the proper actions are taken for these components. Condition D provides actions in Mode 5 when two CCS / ERCW trains are inoperable. Required Action D.1 requires immediate action be taken to restore one of the CCS/ERCW trains to an operable status, as no RHR train is available to support the heat removal function. This action is consistent with the Conditions and Required Actions of LCO 3.4.7, 'RCS Loops - Mode 5, Loops Filled," for RHR loops made inoperable by CCS / ERCW. Although the current TS do not provide explicit Required Actions for an inoperable CCS / ERCW train in Mode 5, the inability of a non-TS support system to enable the TS supported system to perform its safety function results in the inoperability of the TS supported system. Therefore, the TS 3.7.16 and TS 3.7.17 Required Actions for inoperable CCS / ERCW trains in Mode 5 are the same as the current TS Required Actions for inoperable required RHR loops. E1-3

ENCLOSURE 1 Responses to NRC Acceptance Review Questions Associated with WBN Unit 1 ERCW and CCS License Amendment Request The proposed TS changes made to TS 5.7.2.18 and LCO 3.0.6 Bases per NRC-approved TSTF-273-A are not required and are being withdrawn from this license amendment request. NRC Acceotance Review Question 2 The licensee's lefter dated January 22, 201 5 (ADAMS Accessrbn Number ML15187A403), stated that there are two events where a unit may need to be returned to Mode 3 from Mode 4 or Mode 5, without all the conditions for a mode change required by the TS being satisfied. The descriptions of the proposed CCS and ERCW ISs rn TVA's letter dated June 17, 2015, address one of the events, but do not address the other event, described in TVA's January 22 letter as: "A simultaneous or near simultaneous shutdown of both units occurs. The units are being cooled down. The units may be in Mode 4 or Mode 5, a /oss of offsite power occurs, and simultaneously there is fhe /oss of an emergency power train." Provide dr'scussrbn of this second event in the proposed change. TVA Response The simultaneous or near simultaneous shutdown of both units is similar to, but less demanding than the case of a single unit shutdown with reliance on RHR for cooling, concurrent with a postulated loss of coolant accident (LOCA) on the other unit. For the LOCA case, there are two key assumptions relative to heat removal requirements. The first assumes that the non-accident unit is placed on RHR as early as possible. Secondly, the accident unit is assumed to have been operating at 100 percent power after equilibrium decay heat is achieved. These two assumptions maximize the decay heat required to be removed by CCS and ERCW. ln addition, the LOCA requires ERCW flow to the containment spray heat exchanger. This is a flow load on ERCW that does not exist in a dual unit non-accident shutdown case. For a dual unit shutdown, the most limiting case is when the units are assumed to trip simultaneously. The initial cooldown of the units will be performed using auxiliary feedwater to remove decay and sensible heat from the RCS. Using the same assumptions that were used for the non-accident unit described above, RHR was placed in service at the earliest opportunity. However, it will be several hours (approximately 7 hours) before this can occur. Thus, the total decay heat that CCS and ERCW must remove is lower than in the LOCA case. As noted above for the non-accident shutdown, containment spray is not used. Therefore, the demands on ERCW are lower. The flow requirements are reduced to the point that the third ERCW pump is not required. When the assumptions include a loss of offsite power and the loss of Train A power, two CCS pumps need to be aligned to the CCS Train B header and in operation when RHR is in service on both units and both units have been shutdown for less than 48 hours. TVA agrees that the submittal did not provide much discussion of the non-accident case because the LOCA plus shutdown case is more limiting. There is discussion on pages E1-10 and E1-11 of the license amendment with respect to required ERCW pumps. E1-4

ENCLOSURE 1 Responses to NRC Acceptance Review Questions Associated with WBN Unit 1 ERCW and CCS License Amendment Request NRC Acceotance Review Question 3 The licensee stated that tJnit 1 could be maintained in Mode 3 or Mode 4 with decay heat being removed through the steam generators for at least 48 hours as one of the options for managing a unit shutdown. tJsing the steam generators in some scenaios, including a /oss of offsite power, would require operation of Auxiliary Feed Water (AFW) for up to 48 hours; however, the Condensate Storage Tank (CST) lacks sufficient inventory to support operation of AFW for 48 hours. Final Safety Analysis Report (FSAR/ Section 9.2.6.1 sfafes, "The ERCW system pool quality feedwater will be used during an extreme emergency when safety is the prime consideration and steam generator cleanliness is of secondary importance." Address the use of available and approved clean water sources, ERCW, and the CSf,n accordance with the approved licensing basls. The submittal should address whether ERCW wautd be added to the non-accident unit's steam generators for events other than fhose described,n FSAR 9.2.6.3. Also address a dual-unit shutdown and cooldown to Mode 5, for instance as required by LCO 3.0.3, and the available water sources that are uedited for use, inctuding reference to approved procedures that implement these water sources for steam generator cooldown method s. TVA Resoonse The safety-related water supply for AFW is ERCW. The AFW suction source automatically switches from the CST to ERCW when a low pressure condition exists in the AFW pump suction piping from the CST. The switchover to ERCW will occur whenever AFW is in service to assure heat removal through the steam generators if the low pressure condition exists. This assures the safety function of decay heat removal is accomplished. There is adequate clean water to support a unit being maintained on AFW for 48 hours. The capacity of each of the two CSTs is 395,000 gallons and the normal maximum volume in the CSTs is approximately 385,000 gallons. Review of operational data for the past five years shows that the WBN Unit 1 CST has been maintained at approximately 330,000 gallons. Because AFW is not the only system that uses CST water, a standpipe is provided in the tank to assure that a minimum of 200,000 gallons of water is available for the sole use of AFW. Thus, the site maintains approximately 130,000 gallons of water in the CST above the TS limit. Normal make-up to the CST comes from the Demineralized Water Storage (DWST) Tank and the Make-up Water Treatment Plant (MWTP). The DWST tank has a capacity of 500,000 gallons and the level has historically been maintained between 65 and g0 percent full. There have been instances, including one earlier this year, where WBN Unit 1 was maintained in Mode 3 for more than two days using the DWST and the MWTP. WBN recently added the Auxiliary Feedwater Storage Tank (AFWST) as part of the FLEX mitigating strategies. This tank has a capacity of 500,000 gallons and is an immediately available source of clean water. The tank was designed to be seismically robust and to withstand the effects of tornados. The AFWST supply piping is normally isolated by air operated valves (AOVs) from the Unit 1 and Unit 2 condensate piping that supply the suction for the AFW pumps. The AOVs open on a low pressure signal from the upstream condensate piping, a loss of AC power, or a loss of control air. Water can be transferred from the DWST to the AFWST using hoses and pumps that are E1-5

ENCLOSURE 1 Responses to NRC Acceptance Review Questions Associated with WBN Unit 1 ERCW and CCS License Amendment Request maintained by the FLEX program if power cannot be provided to the DWST booster pumps. The two CST; have a cross tie that when opened provides an additional approximately 330,000 gallons of clean water for the case of a LOCA on one unit and the other unit being shutdown. The design basis requires 410 gpm of AFW flow to remove the decay and sensible heat from the RCSIt the time of a reactor trip. The actual demand on AFW drops substantially in the first hours after the reactor trip, as shown in the figure below. AFW Flow vs. Time After Shutdown to Remove Decay Heat _, _t L, Jl;Ll

5C AFw Flolv (spm) lsc r+\\\\"

r+\\a-,* I ^-. 5C U O lC

C ll

.:a 5C t5C t-C 8'O Tinre After Shutclo'ivrr (hours) General Operating lnstruction, GOI-6, the unit cooldown procedure, provides the actions to maintain steam generator cooling. System Operating lnstruction, SOI-59.01, "Demineralized Water System," provides the guidance for maintaining water to the CSTs. Adequate clean water sources are available to support maintaining a unit on AFW in excess of 48 hours. Alternate makeup to the AFWST is controlled by FLEX Support lnstruction, FSI-6, "Alternate AFWST Makeup" and Maintenance lnstruction, Ml-360.020, 'FLEX - Water Transfer Pump Makeup to Auxiliary Feedwater Supply Tank." ln conclusion, there are several large sources of clean water that can be used to support maintaining WBN Unit 1 on steam generator cooling for 48 hours or longer without transferring AFW pump suction to ERCW. Notwithstanding that, the FSAR is clear that ERCW is the safety grade water supply to AFW. lf clean water is not available or clean water is available but cannot be supplied to the steam generators for required decay heat removal, ERCW will be used. i-l-,\\J TI E1-6

ENCLOSURE 1 Responses to NRC Acceptance Review Questions Associated with WBN Unit 1 ERCW and CGS License Amendment Request NRC Acceptance Review Question 4 lnformation needed by the U.S. Nuclear Regulatory Commission staff to begin its review of the Iennessee Valley Authority's (the licensee) request to add technical specifications to support dual-unit operations related to containment considerations is described below. tn the June 17, 2015, submittal, the licensee committed to provide a revised containment pressure analysis by separate conespondence to reflect the dual-unit Essential Raw Cooling Water (ERCW sysfem flowrate to the Component Cooling Sysfem (CCS) heat exchangers. Please provide quantitative information regarding the impact of changes resulting from dual-unit operation of the ERCW and CCS sysfemg including the changes proposed to ensure compliance with General Design Criterion 5, on containment performance for both Unit 1 and Unit 2. The information provided for both units should include the results of containment pressure, temperature, and sump temperature responses, and net positive suction head analysis. These analyses should include conections for errors in the WCAP-I0325-P-A /oss of coolant accident (LOCA) mass and energy (M&E) release methodology reported in Nuclear Safety Advisory Lefters (NSAts)-06'6, '11-5, and -14'2. Additionally, the NRC sfaffrs aware of Westinghouse's lnfoGram lc-l4-1, dated November 5, 2014, which sfafes that the LOCA containment M&E release analysis methodology was found fo use a reactor coolant system (RCS) sfaln/ess steel volumetric heat capacity value lower than the American Society of Mechanical Engineers (ASME) values. The staff has received information which indicates that the impact on the LOCA peak containment pressure in the cunent licensing basis would be significant if the analysis included the ASME values for the RCS metal volumetic heat capacity. Therefore, the information provided in response fo fhls request should include use of the ASME values for the RCS mefal volumetric heat capacity. The analysis for lJnit 1 should also provide information consisfenf with the /tcensee's December 17, 2014, response to Requestfor Additional lnformation (RAI) regarding Watts Bar Unit 2 FSAR, Amendment 112, Chapter 6, RAI Number SCVB-RAI-3 (ADAMS Accession Number MLl4352A248). ln addition, consrsfenf with Wafts Bar Unit 2, please revisit the initial containment temperatures sfafed in assumption number (10) in Secfion 6.2.1.3.3 of the Wafts Bar Unit 1 FSAR, and revise the containment analysis for conseruatism based on the maximum containment air temperatures specified,n IS 3.6.5. TVA Response TVA will provide a revised containment LOCA pressure analysis with updated FSAR Section 6.2.1, "Containment Functional Design," for WBN Unit 2 and revised Technical Specification Surveillance Requirements (SR) 3.6.1 1.2 and 3.6. 1 1.3 related to ice weight by August 14,2015. The WBN Unit 2 FSAR analysis as described in Amendment 113 had incorporated the three Westinghouse Nuclear Safety Advisory Lefters (NSALS) 06-6, 11-5, and 14-2, as well as initial containment compartment temperatures. The analysis to be submitted on August 14,2015 will include the changes to heat exchanger heat removal rates to account for a E1-7

ENCLOSURE 1 Responses to NRC Acceptance Review Questions Associated with WBN Unit I ERCW and GCS License Amendment Request case with loss of Train A power and sharing of the CCS Train B heat exchanger between units, as well as changes to the specific heat values for RCS metal mass to address the issue identified in Westinghouse lnfogram 14-1. The impacts on equipment qualification and issues related to sump water temperature will be addressed in the submittal. The WBN Unit 1 containment LOCA analysis is being reanalyzed using WCOBRA/TRAC to generate the mass and energy (M&E) releases. The containment response will be calculated using LOTIC 1. The LOTIC 1 analysis will incorporate the changes to heat exchanger heat removal based on the dual unit sharing of Component Cooling System Train B. The WCOBRA/TRAC analysis for WBN will conform to all the applicable limiting conditions described in the NRC Safety Evaluation Report (SER) for WCOBRA/TRAC. Two specific issues that will be included in the WBN M&Es are: 1) the specific heat values for the RCS metal mass will be equal to or higher than the ASME values, and 2) PAD4 plus fuel thermal conductivity degradation will be explicitly accounted for. Based on information currently contained in the WCOBRA/TRAC topical report, it is known that the current containment response in the WBN Updated FSAR is conservative and that the current TS SRs 3.6. 1 1.2 and 3.6.1 1.3 regarding total ice bed and per basket ice weights are acceptable and do not have to be increased. A revised WBN Unit 1 containment analysis that addresses the NSALS, initial containment compartment temperature, RCS metal specific heat values, and heat exchanger performance will be completed by September 18, 2015. NRC Acceptance Review Question 5 TVA's June 17, 2015, submittal, identified several manualoperator actions assoclafed with the proposed change.

1. Provide a description of the operator actions being added, changed, or deleted.

2. Provide a description of changes, additions or deletions to procedures in addition to those listed on page El-12, if any (e.9., LOCA, fire).

3. Provide a description of changes, additions, or deletions to training or to the plant-specific simulator.

4. ldenttfy any changes, additions or deletions to instrumentation, controls, alarms, annunciators, and Safety Parameter Display Sysfem.

5. Provide a description of the validation of the feasibility and reliability of added or changed operator actions, including time required vs. time available.

6. ldenttfy any applicable precedents or other operating experience.

TVA Response

1. Provide a description of the operator actions being added, changed, or deleted.

One operator action outside of the main control room is being added. This action is for an E1-8

ENCLOSURE 1 Responses to NRC Acceptance Review Questions Associated with WBN Unit 1 ERCW and CCS License Amendment Request Assistant Unit Operator (AUO) to go to the appropriate 6.9 kilovolt (kV) shutdown board room and actuate a single switch (ERCW pump interlock bypass switch) as described on page E1-11 of the license amendment request. Depending on the system alignments prior to the event and the electrical train that is lost as a part of the event, three possible actions that may be performed by a main control room operator have been added.

a. ln the event of a loss of offsite power and the loss of Train A onsite power, a second CCS pump must be started if two are not already running. lf CCS pump 2B-B was the second pump aligned to the CCS Train B header and it was not running, the operator would be required to start the pump. lf CCS pump 2B-B was running or CCS pump 1B-B was the second pump aligned to the B header, no operator action would be required.

b. ln the event of a loss of offsite power and the loss of either Train A or Train B power, a main control room operator would place the motor driven auxiliary feedwater pump powered from the shutdown board on which the second ERCW pump was to be started in pullto-lock to ensure that it was not running and would not start.

c. ln the event of a loss of offsite power and the loss of either Train A or Train B power, a main control room operator would start a second ERCW pump.

No other operator actions are associated with this license amendment request. The alignment of CCS pump 1B-B or 2B-B to CCS Train B header is not a manual action because the alignment takes place before the LOCA occurs.

2. Provide a description of changes, additions or deletions to procedures in addition to those listed on page E1-12, if any (e.9., LOCA, fire).

a. Emergency Procedure E-0, "Reactor Trip or Safety lnjection," contains an action to verify CCS pumps '1A-A, 1B-B, and C-S are running. The step will be modified to verify that CCS pump 2B-B is running if the pump is being used as the second pump on the B Train CCS header.

Emergency Procedure ES-1.3, "Transfer to Containment Sump" is the procedure where actions are taken by the main control room operator to start the ERCW pumps and to place the AFW pump in pullto-lock will most likely be located. Because the actions to start a second ERCW pump and place the AFW pump in pull-to-lock occur on the non-accident unit shutdown board, these steps could be placed in an abnormal operating instruction associated with the loss of a 6.9 kV shutdown board. The final decision about what procedures will be affected by this license amendment request is part of the impact review that occurs once the submittal is approved. No changes to fire procedures are associated with this license amendment request. The operation of two ERCW pumps on one diesel for some fire scenarios has been b. C. E1-9

ENCLOSURE 1 Responses to NRG Acceptance Review Questions Associated with WBN Unit I ERCW and CCS License Amendment Request addressed in the fire protection report. This report is undergoing a separate review by the NRC. This submittal does not change the fire protection report.

3. Provide a desciption of changes, additions, or deletions to training or to the plant-specific simulator.

The operating training program has been revised as part of the WBN Unit 2 licensing process to address both unit differences and operation with both units in operation. The procedures being revised by this amendment request are part of the operator training program and the training program is regularly updated when the procedures are revised. A design change has been issued to prepare and implement this license amendment. Similar to the discussion on procedures above, training has been identified as being impacted by this submittal. Updates to the training program to incorporate the necessary information is part of the TVA design change process. The simulator programming will need to be updated to allow a second ERCW pump to be started when the interlock bypass has been activated. An annunciator window will illuminate showing that the interlock bypass has been activated.

4. ldentrfy any changes, additions or deletions to instrumentation, controls, alarms, annunciators, and Safety Parameter Display Sysfem.

An interlock bypass switch for ERCW pumps will be installed as described above and in the license amendment request. An annunciator window will be added in the main control room to show when an interlock bypass switch has been activated.

5. Provide a description of the validation of the feasibility and reliability of added or changed operator actions, including time required vs. time available.

a. The action to start a second Train B CCS pump must occur before the unit in an accident transfers RHR suction from the refueling water storage tank (RWST) to the containment sump. The single failure that necessitates the action also causes the loss of one of the two trains of Emergency Core Cooling System (ECCS) equipment.

For this case, the operator has approximately 20 minutes to start the CCS pump. Starting the pump is a single switch manipulation on the control board. The time required is thus very short and the time available is 20 minutes. The action is procedurally controlled and taken in an environmentally controlled area by a licensed operator trained in the action. Thus the action is feasible. ln addition, this is not a new action. As noted above, Emergency Operating lnstruction E-0 already requires the control room operators to ensure the required CCS pumps are running. a. b. E1-10

ENGLOSURE 1 Responses to NRG Acceptance Review Questions Associated with WBN Unit I ERCW and CCS License Amendment Request

b. The action to start a second ERCW pump must occur before the containment spray pump suction is transferred from the RWST to the containment sump. The operator has approximately 40 minutes before the containment spray pump suction must be transferred. There are three actions that must be accomplished. An AUO is dispatched from the main control room to activate the interlock bypass switch.

Preliminary walkdowns have shown that this action can be accomplished in approximately 215 seconds. This time includes the transit time from the Main Control Room to the most distant shutdown board room and operating the interlock bypass switch. There is more than 100 percent margin in the required time, the action is proceduralized, and personnelwill be trained on the action. ln addition, the action is the same type of action that AUOs currently are required to perform in the 6.9 kV shutdown board rooms. Thus this action is feasible. More details on this action outside of the control building are provided in response 6 below. The other actions are two switch manipulations from a control panel in the main control room. The time required for a reactor operator on the control board to manipulate a switch is very short. These actions are identical in form to actions that operators are taking within this time period. The actions are procedurally controlled and taken in an environmentally controlled area by a licensed operator trained in the actions. Thus the actions are feasible.

c. Preliminary walkdowns of the actions outside of the main control room support that these actions can be performed within required time limits without adverse impact.

The procedure development process requires that a formal validation of the set of actions be conducted following installation of plant design changes.

6. ldenttfy any applicable precedents or other operating experience.

There is substantial operating experience for these types of actions. For the action outside of containment, a specific WBN example is emergency procedure E-0, which requires an AUO to be dispatched to open breakers on the 480 V reactor vent boards. These boards are on an elevation above the 6.9 kV shutdown boards and are thus farther from the main control room and more actions are required since four breakers are to be opened versus actuating one switch. There are numerous steps in emergency procedure E-0 and in emergency procedure ES-1.3 that currently require the operator to start and stop ERCW and CCS pumps during the events of interest in this submittal. These are routine actions that occur both during normal operation and during accidents and transients. NRC Acceotance Review Question 6 Provide information regarding fhe basrs for the statement on page E1-1 1 that the mlssion dose is within the General Design Criterion 19 criteria, including: o Plant layout drawings depicting access and egress routes. o Maximum anticipated accident dose rafes. Maximum mission dose for the operator pefforming this manual action. E1-11

ENCLOSURE 1 Responses to NRC Acceptance Review Questions Associated with WBN Unit 1 ERCW and CCS License Amendment Request The level of detail should be consisfent with the response prcvided to Final Safety Analysis Report Chapter 12 Request for Additional lnformation Number 6 in support of the Unit 2 operating license review. TVA Response Bullet 1: Plant layout drawings depicting access and egress routes. The plant layout drawing below depicts the four "Performance Paths" from the main control room to the shutdown board room for manipulating each of the ERCW pump interlock bypass switches. The "Mission Dose Path" depicts the route upon which the mission dose is based. E1-12

ENCLOSURE 1 Responses to NRC Acceptance Review Questions Associated with WBN Unit I ERCW and CCS License Amendment Request Bullet 2: Maximum anticipated accident dose rates. The table below indicates the dose rates (rem/hr) inside and outside of the auxiliary building secondary containment enclosure (ABSCE). All of the dose rates along the "Mission Dose Path" for performance of the subject manual action are outside of the ABSCE. Mission Area Dose Rates (rem/hr) Outside ABSCE (All Elevations) lnside ABSCE El.713 Et.737 El.757 All Stainrvays lnhalation Beta Gamma 6.053E+01 1.220E+00 2.132E+00 6.228E+01 2.703E+00 1.088E+00 6.228E+01 2.703E+00 1.385E+00 6.228E+01 2.703E+00 1.344E-01 6.2288+01 2.703E+00 1.385E+00 Bullet 3: Maximum mission dose for the operator performing this manual action. Calculation of the mission dose for the operator performing the manual action includes occupancy, ingress/egress, and mission doses for the entire accident duration. a) One operator dressed in anti-contamination clothing will leave the main control room at El. 755 and ascend the short stairway to room 757.0-45. Walking Distance: 22.5ft+ 2ft Time: 15 sec + 4 sec = 19 sec b) Proceed through door A143 and walk north across room 757.0-A2 to close to T line wall. Turn to east and continue to the farthest 6.9 kV shutdown board, located at A12 line. Walking Distance:203ft Time: 136 sec c) Switch operating time to one of 6.9 kV shutdown boards. Time: 60 sec d) Travel back from the farthest 6.9 kV shutdown board to door A143, and into room 757.0-A5. Walking Distance: 203 ft Time: 136 sec e) Descend the short stairway from El. 757.0 to the main control room El. 755.0. Walking Distance: 2ft+ 22.5ft Time: 4 sec + 15 sec = 19 sec Total mission time = 370 seconds E1-14

ENCLOSURE 1 Responses to NRG Acceptance Review Questions Associated with WBN Unit I ERCW and GCS License Amendment Request As indicated below, mission dose for the manual action is wellwithin the 10 CFR 50, Appendix A, General Design Criterion 19 limits of 5 rem whole body, 30 rem beta (skin), and 30 rem thyroid (inhalation)with or without a respirator. Step # / Stay Time Dose Rate Dose (rem) No Dose (rem) with Respirator Description a) From Control Rom to room 757.0-A5 b) From room 757.0-A5 to 6.9 KV board c) Switch operating time d) From 6.9 KV board to room 757.0-A5 e) From room 757.A-A5 to Control Room sec 19 Thyroid Skin Whole Body 136 Thyroid Skin Whole Body 60 Thyroid Skin Whole Body 136 Thyroid Skin Whole Body 19 Thyroid Skin Whole Body rem/hr 6.053E+01 1.220E+00 2.132E+00 6.053E+01 1.220E+00 2.132E+00 6.053E+01 1.220E+00 2.132E+00 6.053E+01 1.220E+00 2.132E+00 6.053E+01 1.220E+00 2.1328+00 Total Total Total Resoirator 3.195E-01 6.439E-03 1.125E-02 2.287E+00 4.609E-02 8.054E-02 1.009E+00 2.033E-02 3.553E-02 2.287E+00 4.609E-02 8.054E-02 3.195E-01 6.439E-03 1.125E-02 6.22E+00 1.25E-01 2.19E-01 PF=1 0000 3.195E-05 6.439E-03 1.125E-02 2.287E-04 4.609E-02 8.054E-02 1.009E-04 2.033E-02 3.553E-02 2.2878-04 4.609E-02 8.054E-02 3.195E-05 6.439E-03 1.125E-02 6.22E-04 1.25E-01 2.19E-01 Outside ABSCE (7s7) Outside ABSCE (757) Outside ABSCE (757) Outside ABSCE (757) Outside ABSCE (757) Thyroid Skin Whole Body E1-15

ENCLOSURE 1 Responses to NRC Acceptance Review Questions Associated with WBN Unit 1 ERCW and CCS License Amendment Request REFERENCES

1. Letter from TVA to NRC, "Watts Bar Nuclear Plant Unit 1 - Application to Revise Technical Specifications for Component Cooling Water and Essential Raw Cooling Water to Support Dual Unit Operation (TS-WBN-15-13)," dated June 17, 2015 [M115170A4741

2. Letter from NRC to TVA, "Watts Bar Nuclear Plant, Unit 1 - Supplemental lnformation Needed for Acceptance of Requested Lie,ensing Action Regarding Application to Add Technical Specifications to Support Dual-Unit Operations (TAC No. MF6376),'dated July 9, 2015 [ML15187A403]

E1-16

ENCLOSURE 1 Responses to NRG Acceptance Review Questions Associated with WBN Unit 1 ERCW and CCS License Amendment Request ATTACHMENTS - WBN Unit 1 TS 3.7.16 and Bases - WBN Unit 1 TS 3.7.17 and Bases E1-17

ENCLOSURE 1 ATTACHMENT 1 WBN Unit 1 TS 3.7.16 and Bases E1-18

CCS - Shutdown 3.7.16 3.7 PLANT SYSTEMS 3.7. 16 Component Cooling System (CCS) - Shutdown LCO 3.7.16 APPLICABILITY: Two CCS trains shall be OPERABLE with one pump powered from Train A and aligned to the Train A header, and two pumps powered from Train B and aligned to the Train B header. MODES 4 and 5. -NOTE----- This LCO is not applicable for either of the following conditions:

a. More than 48 hours after Unit 1 entry into MODE 3 from MODE 1 or 2.

b. Unit 2 defueled or in MODE 4 or 5 more than 48 hours after entry into MODE 3 from MODE 1 or 2.

COMPLETION TIME 24 hours ACTIONS CONDITION One CCS train inoperable in MODE 4. AND Complying with Required Actions to be in MODE 5. One CCS train inoperable in MODE 4 for reasons other than Condition A. Once per 12 hours Once per 12 hours (continued) REQUIRED ACTION A.1 Be in MODE 5. 8.1 Verify two OPERABLE reactor coolant system (RCS) loops and one RCS loop in operation. AND 8.2 Verify Tavg > 200oF. Watts Bar-Unit 1 3.7-33 Amendment XX

C. CONDITION Two CCS trains inoperable in MODE 4. One or more CCS train(s) inoperable in MODE 5. CCS - Shutdown 3.7. 1 6 COMPLETION TIME lmmediately lmmediately D. ACTIONS (continued) REQUIRED ACTION

l.cd-#3lFf;;;;;;---

LCO Required Actions requiring MODE changes are suspended until one CCS train is restored to an OPERABLE status.

2. Enter Conditions and Required Actions of LCO 3.4.6, "RCS Loops -

MODE 4," for residual heat removal (RHR) loops made inoperable by CCS. lnitiate action to restore one CCS train to OPERABLE status. D.1

NOTE--

Enter applicable Conditions and Required Actions of LCO 3.4.7, "RCS Loops - MODE 5, Loops Filled," for RHR loops made inoperable by CCS. lnitiate action to restore CCS train(s) to OPERABLE status. Watts Bar-Unit 1 3.7-34 Amendment XX

SURVEILLANCE REQU I REMENTS CCS - Shutdown 3.7.16 FREQUENCY SURVEILLANCE sR 3.7.16.1 12 hours sR 3.7.16.2 Verify two CCS pumps are aligned to CCS Train B. 12 hours Verify correct breaker alignment and indicated power available to the required pump(s) that is not in operation. Watts Bar-Unit 1 3.7-35 Amendment XX

CCS - Shutdown B 3.7.16 B 3.7 PLANT SYSTEMS B 3.7.16 Component Cooling System (CCS) - Shutdown BASES BACKGROUND The general description of the Component Cooling System (CCS) is provided in TS Bases3.7.7, "Component Cooling System." The CCS has a Unit 1 Train A header supplied by CCS Pump 1A-A cooled through CCS Heat Exchanger (HX) A. Unit 2 has a separate Train A header containing HX B supplied by CCS Pump 2A-A. The Train B header is shared by Unit 1 and Unit 2 and contains HX C. Flow through the Train B header is normally supplied by CCS Pump C-S. CCS Pump 1B-B can be aligned to supply the Train B header, but it is normally aligned to the Unit 1 Train A header. Similarly, CSS Pump 2B-B can supply cooling water to the Train B header, but is normally aligned to the Unit 2 Train A header. The following describes the functions and requirements within the first 48 hours after shut down, when the Residual Heat Removal (RHR) System is being used for residualand decay heat removal. Entry into MODES 4 and 5 can place high heat loads onto the RHR System, CCS and the Essential Raw Cooling Water System (ERCW) when shutdown cooling is established. Residual and decay heat from the Reactor Coolant System (RCS) is transferred to CCS via the RHR HX. Heat from the CCS is transferred to the ERCW System via the CCS HXs. The CCS and ERCW systems are common between the two operating units. During the first 48 hours after reactor shutdown, the heat loads are at sufficiently high levels that the normal pump requirement of LCO 3.7.7 for one CCS pump on the Train B header may not be sufficient to support shut down cooling of Unit 1, concurrent with either a nearly simultaneous shutdown of Unit 2 or adesign basis loss of coolant accident (LOCA) on Unit 2, with loss of offsite power and a single failure of Train A power to 6.9 kV Shutdown Boards 1A-A and 2A-4. ln either scenario, CCS Pump C-S would normally be the only pump supplying the Train B header and the Train B header would be supplying both the Unit 1 RHR Train B HX and the Unit 2 RHR Train B HX. During the Unit 2 LOCA scenario, the Unit 2 RHR Train B HX would be cooling the recirculating Emergency Core Cooling System (ECCS) water from the containment sump. To assure that there would be adequate CCS flow to both units' RHR Train B HXs, prior to placing RHR in service for Unit 1, either CCS Pump 1B-B or 2B-B would be aligned to the CCS Train B header. Watts Bar-Unit 1 B 3.7-78 (continued)

CCS - Shutdown B 3.7.16 BASES (continued) BACKGROUND (continued) After either unit has been shut down for greater than 48 hours, a single CCS pump on Train B provides adequate flow to both the Unit 1 and the Unit 2 RHR Train B HXs. tf the single failure were the loss of Train B power, the normal CCS alignment is acceptable, because CCS Pump 1A-A supplies the Unit 1 RHR Train A HX and CCS Pump 2A-A supplies the Unit 2 RHR Train A HX. CCS Pump 1A-A does not provide heat removalfor Unit 2. Additional information on the design and operation of the system, along with a list of the components served, is presented in the FSAR, Section 9.2.2 (Ref. 1). The principal safety related function of the CCS is the removal of heat from the reactor via the RHR System. This may be during a normal or post accident cool down and shut down. The Unit 1 CCS Train A header is not used to support Unit 2 operation. APPLICABLE SAFETY ANALYSES The CCS functions to cool the unit from RHR entry conditions in MODE 4 (Tcou < 350"F), to MODE 5 (T"ou < 200"F), during normal operations. The time required to cool from 350"F to 200"F is a function of the number of CCS and RHR trains operating. One CCS train is sufficient to remove heat during subsequent operations with T-ro < 200'F. This assumes a maximum ERCW inlet temperature of 85'F occurring simultaneously with the maximum heat loads on the system. The design basis of the CCS is for one CCS train to remove the post LOCA heat load from the containment sump during the recirculation phase, with a maximum CCS HX outlet temperature of 110"F (Ref. 2). The ECCS LOCA analysis and containment LOCA analysis each model the maximum and minimum performance of the CCS, respectively. The normal maximum HX outlet temperature of the CCS is 95"F, and, during unit cooldown to MODE 5 (T"or < 200'F), a maximum HX outlet temperature of 110"F is assumed. The CCS design based on these values, bounds the post accident conditions such that the sump fluid will not increase in temperature after alignment of the RHR HXs during the recirculation phase following a LOCA, and provides a gradual reduction in the temperature of this fluid as it is supplied to the RCS by the ECCS pumps. The CCS is designed to perform its function with a single failure of any active component, assuming a loss of offsite power. CCS - Shutdown satisfies Criterion 4 of 10 CFR 50.36(c)(2)(ii). Watts Bar-Unit 1 B 3.7-79 (continued)

CCS - Shutdown B 3.7.16 BASES (continued) LCO The CCS trains are independent of each other to the degree that each has separate controls and power supplies and the operation of one does not depend on the other. During a unit shut down, one CCS train is required to provide the minimum heat removal capability assumed in the safety analysis for the systems to which it supplies cooling water. To ensure this requirement is met, two trains of CCS must be OPERABLE. At least one CCS train will operate assuming the worst case single active failure occurs coincident with a loss of offsite power. This LCO provides CCS train OPERABILITY requirements beyond the requirements of LCO 3.7.7 during the first 48 hours after reactor shut down, when the heat loads are at sufflciently high levels that the normal pump requirement of one CCS pump on the Train B header may not be sufficient to support shutdown cooling of Unit 1, concurrent with a nearly simultaneous shutdown of Unit 2 or a LOCA on Unit 2, a loss of offsite power, and single failure of Train A power to 6.9 kV Shutdown Boards 1A-A and 2A-A. Because CCS Train B supports heat removalfrom Unit 1 and Unit 2, when Unit t has been shutdown 3 48 hours and the RHR System is relied on for heat removal, the following is required for CCS OPERABILITY:

a. Train A is OPERABLE when CCS Pump 1A-A is available and aligned to the CCS Train A header.

b. Train B is OPERABLE when two CCS pumps are available and aligned to the CCS Train B header using any combination of CCS Pumps 1B-8, 2B-B, and C-S.

c. The associated piping, valves, HXs, and instrumentation and controls required to perform the safety related function are OPERABLE.

Because Unit 1 is shutdown and on RHR cooling, no automatic actuations are required as a DBA on Unit 1, such as a LOCA, does not have to be mitigated. APPLICABILITY Prior to aligning the RHR System for RCS heat removal in MODE 4, an additional CCS pump must be powered from and aligned to the CCS Train B header to ensure adequate heat removal capability. The Applicability is modified by a Note stating the LCO does not apply after the initial 48 hours after either unit enters MODE 3 from MODE 1 or MODE 2. Following extended operation in MODE 1, the heat loads are at sufficiently high levels that the normal pump requirement of LCO 3.7.7 for Watts Bar-Unit 1 B 3.7-80 (continued)

CCS - Shutdown B 3.7.16 BASES APPLICABILITY (continued) one CCS pump on the Train B header may not be sufficient to support shutdown cooling of Unit '1, concurrent with a near simultaneous shutdown of Unit 2 or a design basis LOCA on Unit 2, with loss of offsite power and a single failure of Train A power to 6.9 kV Shutdown Boards 1A-A and 2A-A. However, after the initial 48 hours following shutdown of either unit, the heat removal capabili$ of both units is within the capabilities of the GCS without the need for an additional CCS pump aligned to the CCS Train B header. ACTIONS 4.1 ln MODE 4, if one CCS train is inoperable, and the unit is required to be placed in MODE 5 to comply with Required Actions, action must be taken to place the unit in MODE 5 within 24 hours. ln this Condition, the remaining OPERABLE CCS train is adequate to perform the heat removal function. The 24 hour Completion Time is consistent with LCO 3.4.6, "RCS Loops - MODE 4," Required Action 8.1 for the Condition of one required RHR loop inoperable and no RCS loops OPERABLE. B.1 and B.2 ln MODE 4, if one CCS train is inoperable, and the unit is not required to be placed in MODE 5 to comply with Required Actions, actions are taken to verify LCO 3.4.6 is being met with two OPERABLE RCS loops with one loop in operation, and that the unit remains in MODE 4 (T*s > 200oF). Maintaining the unit in MODE 4 provides conditions for additional methods of decay heat removal and minimizes the likelihood of a situation where the decay heat and residual heat of the unit exceeds the capability of the available RHR loop resulting in the possibility of an unintentional MODE change. The Frequency of once per 12 hours ensures that the systems being relied on for heat removal are operating properly and are maintaining the unit in MODE 4. The 12 hour Frequency is reasonable, considering the low probability of a change in system operation during this time period. c.1 ln MODE 4, if two CCS trains are inoperable, immediate action must be taken to restore one of the CCS trains to an OPERABLE status, as no CCS train is available to support the heat removal function. Required Action C.1 is consistent with LCO 3.4.6, "RCS Loops - MODE 4,' Required Action B.1 for the Condition of one required RHR loop inoperable and no RCS loops OPERABLE. Watts Bar-Unit 1 B 3.7-81 (continued)

CCS - Shutdown B 3.7.16 BASES ACTIONS C.1 (continued) Required Action C.1 is modified by two Notes. Note '1 indicates that all required MODE changes or power reductions are suspended until one CCS train is restored to OPERABLE status. ln this case, LCO 3.0.3 is not applicable because it could force the plant into a less safe condition. Note 2 indicates that the applicable Conditions and Required Actions of LCO 3.4.6 be entered for RHR loops made inoperable by the inoperable CCS trains. This is an exception to LCO 3.0.6 and ensures the proper actions are taken for these components. D.1 Required Action D.1 is modifled by a Note indicating that the applicable Conditions and Required Actions of LCO 3.4.7, "RCS Loops - MODE 5, Loops Filled," be entered for RHR loops made inoperable by one or more inoperable CCS train(s). This is an exception to LCO 3.0.6 and ensures the proper actions are taken for these components. ln MODE 5, if one or more CCS train(s) is inoperable, action must be initiated immediately to restore the CCS train(s) to an OPERABLE status to restore heat removal paths. The immediate Completion Time reflects the importance of maintaining the capability of heat removal. SURVEILLANCE REQUIREMENTS sR 3.7.16.1 Verification that each required CCS pump that is not in operation is OPERABLE ensures that an additional pump can be placed in operation, if needed, to maintain heat removal. Verification is performed by verifying proper breaker alignment and power available to the CCS pump(s). The 12 hour Frequency is based on engineering judgment. sR 3.7.16.2 This SR verifies that two of the three CCS pumps that are powered from Train B are aligned to the Train B header. Verification of the correct physical alignment assures that adequate CCS flow can be provided to both the Unit 1 and Unit 2 RHR Train B HXs, if required. The 12 hour Frequency is based on engineering judgment, is consistent with procedural controls governing valve alignment, and ensures correct valve positions. Watts Bar-Unit 1 B 3.7-82 (continued)

CCS - Shutdown B 3.7.16 BASES REFERENCES 1. Watts Bar FSAR, Section 9.2.2,"Component Cooling System."

2.

Watts Bar Component Cooling System Description, N3-70-4002. Watts Bar-Unit 1 B 3.7-83

ENCLOSURE 1 ATTACHMENT 2 WBN Unit 1 TS 3.7.17 and Bases

ERCW - Shutdown 3.7.17 3.7 PLANT SYSTEMS 3.7.17 Essential Raw Cooling Water (ERCW) System - Shutdown LCO 3.7.17 APPLICABILITY: CONDITION One ERCW train inoperable in MODE 4. AND Complying with Required Actions to be in MODE 5. One ERCW train inoperable in MODE 4 for reasons other than Condition A. Two ERCW trains shall be OPERABLE as follows:

a. Three ERCW pumps aligned to Train A, including two pumps capable of being powered from 6.9 kV Shutdown Board 1A-A, and

b. Three ERCW pumps aligned to Train B, including two pumps capable of being powered from 6.9 kV Shutdown Board 1B-8.

MODES 4 and 5. -NOTE------ This LCO is not applicable for either of the following conditions:

a.

More than 48 hours after Unit 1 entry into MODE 3 from MODE 1 or 2.

b. Unit 2 defueled or in MODE 4 or 5 more than 48 hours after entry into MODE 3 from MODE 1 or 2.

COMPLETION TIME 24 hours Once per 12 hours Once per 12 hours (continued) Amendment XX ACTIONS REQUIRED ACTION A.1 Be in MODE 5. 8.1 Verify two OPERABLE reactor coolant system (RCS) loops and one RCS loop in operation. AND 8.2 Verify Tavg > 200oF. Watts Bar-Unit 1 3.7-36

C. ACTIONS (continued) CONDITION Two ERCW trains inoperable in MODE 4. One or more ERCW train(s) inoperable in MODE 5. ERCW - Shutdown 3.7.17 COMPLETION TIME lmmediately lmmediately D. REQUIRED ACTION C.1 .--NOTES

1. LCO 3.0.3 and all other LCO Required Actions requiring MODE changes are suspended until one ERCW train is restored to an OPERABLE status.

2. Enter Conditions and Required Actions of LCO 3.4.6, "RCS Loops -

MODE 4," for residual heat removal (RHR) loops made inoperable by ERCW. lnitiate action to restore one ERCW train to OPERABLE status. D.1

NOTE--

Enter applicable Conditions and Required Actions of LCO 3.4.7, "RCS Loops - MODE 5, Loops Filled," for RHR loops made inoperable by ERCW. lnitiate action to restore ERCW train(s) to OPERABLE status. Watts Bar-Unit 1 3.7-37 Amendment XX

SURVEILLANCE REQU I REMENTS sR 3.7.17.1 SURVEILLANCE Verify correct breaker alignment and indicated power available to the required pump(s) that is not in operation. ERCW - Shutdown 3.7.17 FREQUENCY 12 hours Watts Bar-Unit 1 3.7-38 Amendment XX

ERCW - Shutdown B 3.7.17 B 3.7 PLANT SYSTEMS B 3.7.17 Essential Raw Cooling Water (ERCW) System BASES BACKGROUND The general description of ERCW is provided in TS Bases 3.7.8, "Essential Raw Cooling Water (ERCW) System." The descriptions of Applicable Safety Analyses, LCOs, Applicability, ACTIONS and Surveillance Requirements for applicable MODES are also described in TS Bases 3.7.8. The following discussion applies to the specific Applicability in TS 3.7.17 during the first 48 hours after shut down when the Residual Heat Removal (RHR) System is being used for residual and decay heat removal. The ERCW System provides a heat sink for the removal of process and operating heat from safety related components during a design basis accident (DBA) or transient. During normal operation, and a normal shutdown, the ERCW System also provides this function for various safety related and non-safety related components. The major post-accident heat load on the ERCW System is the Component Cooling System (CCS) heat exchangers (HXs), which are used to cool RHR and the containment spray HXs. The major heat load on the ERCW System when a unit is shut down on RHR is the CCS HX associated with the train(s) of RHR in service. Normally, two ERCW pumps are sufficient to handle the cooling needs for maintaining one unit in normal operation while mitigating a DBA on the other unit. However, in the unlikely event of a loss of coolant accident (LOCA)on Unit 2 with a concurrent loss of offsite power and a single failure that results in the loss of both Train A or both Train B 6.9 kV shutdown boards while Unit 1 is on RHR shutdown cooling and has been shutdown for less than 48 hours, three ERCW pumps may be required. This LCO controls the availability of ERCW pumps necessary to support mitigation of a LOCA on Unit 2 when Unit t has been shut down for s 48 hours and is utilizing RHR for heat removal. Additional information about the design and operation of the ERCW System, along with a list of the components served, is presented in the FSAR, Section 9.2.1 (Ref. 1). Watts Bar-Unit 1 B 3.7-84 (continued)

ERCW - Shutdown B 3.7.17 BASES (continued) APPLICABLE SAFETY ANALYSES The design basis of the ERCW System is for one ERCW train, in conjunction with the CCS and a 100o/o capacity Containment Spray System and RHR, to remove core decay heat following a design basis LOCA as discussed in the FSAR, Section 9.2.1 (Ref. 1). This prevents the containment sump fluid from increasing in temperature during the recirculation phase following a LOCA and provides for a gradual reduction in the temperature of this fluid as it is supplied to the Reactor Coolant System (RCS) by the Emergency Core Cooling System (ECCS) pumps. The ERCW System is designed to perform its function with a single failure of any active component, assuming a loss of offsite power. The ERCW System, in conjunction with the CCS, also cools the unit, as discussed in the FSAR, Section 5.5.7 (Ref. 2) from RHR entry conditions to MODE 5 during normal and post accident operations. The time required to enter MODE 5 is a function of the number of CCS and RHR System trains that are operating. One ERCW train is sufficient to remove heat during subsequent operations in MODES 5 and 6. This assumes a maximum ERCW inlet temperature of 85oF occurring simultaneously with maximum heat loads on the system. ln the first 48 hours after the shutdown of Unit 1 assuming a DBA LOCA on Unit 2 with the loss of offsite power and the concurrent loss of two 6.9 kV shutdown boards on the same power train as a single failure. Three ERCW pumps are required to provide the heat removal capacity assumed in the safety analysis for Unit 2 while continuing the cooldown of Unit 1. ERCW - Shutdown satisfies Criterion 4 of 10 CFR 50.36(cX2Xii). LCO This LCO provides ERCW train OPERABILIW requirements beyond the requirements of LCO 3.7.8 during the first 48 hours after reactor shutdown, when the heat loads are at sufficiently high levels that the normal pump requirement of two ERCW pumps on one train may not be sufficient to support shutdown cooling of Unit 1, concurrent with a LOCA on Unit 2, an assumed loss of offsite power, and a single failure that affects both 6.9 kV shutdown boards in one power train. Two ERCW trains are required to be OPERABLE to provide the required redundancy to ensure that the system functions to support a cooldown to MODE 5. An ERCW train is considered OPERABLE during the first 48 hours after shutdown when:

a.

Two pumps per train, aligned to separate shutdown boards, are OPERABLE; and Watts Bar-Unit 1 B 3.7-85 (continued)

ERCW - Shutdown B 3.7.17 BASES LCO (continued) b. One additional Train A pump and one additional Train B pump are capable of being aligned to their respective Unit 1 6.9 kV shutdown board (1A-A and 1B-B) and manually placed in service. APPLICABILITY Prior to aligning the RHR System for RCS heat removal in MODE 4, one additional ERCW pump must be capable of being powered by its respective Unit 1 6.9 kV shutdown board (1A-A and 1B-B) and manually placed in service to ensure adequate heat removal capability. The Applicability is modified by a Note stating the LCO does not apply after the initial 48 hours after either unit enters MODE 3 from MODE 1 or MODE 2. Following extended operation in MODE 1, the heat loads are at sufficiently high levels that the normal pump requirement of LCO 3.7.8 for two ERCW pumps may not be sufficient to support shutdown cooling of Unit 1, concurrent with a design basis LOCA on Unit 2 with loss of offsite power and a single failure of Train A power to 6.9 kV Shutdown Boards iR-R anO 2A-A. However, after the initial 48 hours following shutdown of either unit, the heat removal capability of both units is within the capabilities of the ERCW System without the need for an additional ERCW pump in each train. ACTIONS e1 ln MODE 4, if one ERCW train is inoperable, and the unit is required to be placed in MODE 5 to comply with Required Actions, action must be taken io place the unit in MODE 5 within 24 hours. ln this Condition, the remaining OPERABLE ERCW train is adequate to perform the heat removal function. The 24 hour Completion Time is consistent with LCO 3.4.6, "RCS Loops - MODE 4," Required Action B.1 for the Condition of one required RHR loop inoperable and no RCS loops OPERABLE. B.1 and 8.2 ln MODE 4, if one ERCW train is inoperable, and the unit is not required to be placed in MoDE 5 to comply with Required Actions, actions are taken to verify Lco 3.4.6 is being met with two oPERABLE RCS loops with one loop in operation, and that the unit remains in MODE 4 (T"us > 2OOoF). Maintaining the unit in MODE 4 provides conditions for additional methods of decay heat removal and minimizes the likelihood of a situation where the decay heat and residual heat of the unit exceeds the capability of the available RHR loop resulting in the possibility of an unintentional MODE change. The Frequency of once per 12 hours ensures that the systems being relied on for heat removal are operating properly and are Watts Bar-Unit 1 B 3.7-86 (continued)

ERCW - Shutdown B 3.7.17 BASES ACTIONS B.1 (continued) maintaining the unit in MODE 4. The 12 hour Frequency is reasonable, considering the low probability of a change in system operation during this time period. c.1 ln MODE 4, if two ERCW trains are inoperable, immediate action must be taken to restore one of the ERCW trains to an OPERABLE status, as no ERCW train is available to support the heat removal function. Required Action C.1 is consistent with LCO 3.4.6, "RCS Loops - MODE 4," Required Action B.1 for the Condition of one required RHR loop inoperable and no RCS loops OPERABLE. Required Action C.1 is modified by two Notes. Note 1 indicates that all required MODE changes or power reductions are suspended untilone ERCW train is restored to OPERABLE status. ln this case, LCO 3.0.3 is not applicable because it could force the plant into a less safe condition. Note 2 indicates that the applicable Conditions and Required Actions of LCO 3.4.6 be entered for RHR loops made inoperable by the inoperable ERCW trains. This is an exception to LCO 3.0.6 and ensures the proper actions are taken for these components. D.1 Required Action D.1 is modified by a Note indicating that the applicable Conditions and Required Actions of LCO 3.4.7, "RCS Loops - MODE 5, Loops Filled," be entered for RHR loops made inoperable by one or more inoperable ERCW train(s). This is an exception to LCO 3.0.6 and ensures the proper actions are taken for these components. ln MODE 5, if one or more ERCW train(s) is inoperable, action must be initiated immediately to restore the ERCW train(s) to an OPERABLE status to restore heat removal paths. The immediate Completion Time reflects the importance of maintaining the capability of heat removal. SURVEILLANCE REQUIREMENTS sR 3.7.17.1 Verifying the availability of the ERCW pumps provides assurance that adequate ERCW flow is provided for heat removal. Verification that each required ERCW pump that is not in operation is OPERABLE ensures that an additional pump can be placed in operation, if needed, to maintain decay heat removal. Verification is performed by verifying proper breaker alignment and power available to the ERCW pump(s). The ERCW pump Watts Bar-Unit 1 B 3.7-87 (continued)

ERCW - Shutdown B 3.7.17 BASES SURVEILLANCE SR 3.7.17.1 (continued) REQUIREMENTS lnterlock Bypass Switches do not need to be in 'Bypass' in order to meet this SR. The associated ERCW pump lnterlock Bypass Switch is positioned by procedure when the third ERCW pump in the respective train is required to be started. The 12 hour Frequency is based on engineering judgment. REFERENCES 1. Watts Bar FSAR, Section 9.2.1, "Essential Raw Cooling Water."

2.

Watts Bar FSAR, Section 5.5.7, "Residual Heat Removal System." Watts Bar-Unit 1 B 3.7-88

ENCLOSURE2 - Responses to NRC RAls for WBN Unit 1 ERCW and CGS License Amendment Request Backqround By letter dated June 17, 2015, Tennessee Valley Authority (TVA) submitted a request for a change to Facility Operating License No. NPF-90 for Watts Bar Nuclear Plant (WBN) Unit 1 (Reference 1). The proposed change would create new Technical Specifications (TS) 3.7.16, "Component Cooling System (CCS) - Shutdown," and TS 3.7.17, "Essential Raw Cooling Water (ERCW) System - Shutdown," to support dual unit operation of WBN Units 1 and2. By email dated July 2,2015, the Nuclear Regulatory Commission (NRC) provided requests for additional information (RAl) on the proposed WBN Unit 1 license amendment (Reference 2). The TVA responses to the NRC RAIs provided in Reference 2 are provided below. NRC RAI Question lt a.i.

1) Because of the added pumping power of CCS and ERCW, provide new flows as follows:

a. lnitial Conditions: LOCA floss of coolant accidentl on Unit 2; Unit 1 at 100%, /oss of offsite power (LOOP), and /oss of Train A electrical power.

i. ldentify required minimum flow to perform safety-related (SR) function for each load cooled by ERCW and CCS in Unit 1 and Unit 2.

TVA Resoonse For clarification, the following assumptions are also made with regard to the above scenario:

1. Unit 1 is operating at 100% power prior to the Unit 2 LOCA (also from 100o/o power).

2. The LOOP / loss of Train A accompanying Unit 2 LOCA will trip Unit 1.

3. Unit 1 is able to remain in Mode 3 (being cooled by steam generators) for at least 48 hours.

4. Two ERCW Train B pumps and one CCS Train B pump (aligned to CCS HX C) are available.

The applicable MULTIFLOW case is Unit 1 Cold Shutdown and Unit 2 LOCA with LOOP. For ERCW, this case is identified in calculation MDQ00006720080341, Revision 19, Appendix 11, Table A1 1.5 (Enclosure 2, Attachment 1). For CCS, this case is identified in calculation MDQ00007020090200, Revision 9, Appendix 10, Case 7E (Enclosure 2, Attachment 2). Resultant flows in both calculations are identified in their respective calculation appendices. Calculation MDQ00006720080341, Appendix 11, is with the ERCW discharging to the cooling tower (Enclosure 2, Attachment 1). lf the discharge is through the hydraulic gradient discharge structure, then refer to Appendix '14 (Enclosure 2, Attachment 3). E2-1

ENCLOSURE 2 Responses to NRC RAls for WBN Unit 1 ERCW and CCS License Amendment Request NRC RAI Question lt a.ii. ii. ldentify actual flow to each of the loads with only Train B ERCW (i.e. 2 pumps) and Train B of CCS available because of the /oss of Train A electrical power. TVA Resoonse The attachments identified in response to Question 1) a.i contain both the required minimum and expected actual flows (determined from Multiflow as benchmarked from flow balance testing). NRC RAI Question lt a.iii. iii. Describe operator actions and timing of operation required to achieve the req u i red/actu al flow s. TVA Response The operator will perform the following actions to establish CCS flow:

1. The operator will set CCS flow to RHR HX 2B-B as > 5000 gpm by controlling valve 2-FCV-70-153 from the main control room (MCR). This is performed as part of the emergency core cooling system (ECCS) switchover sequence as described in Final Safety Analysis Report (FSAR) Section 6.3.2.2 and Table 6.3-3 (approximately 20 minutes, minimum).

The operator will perform the following actions to establish ERCW flow. These actions are performed prior to establishing Containment Spray switchover to recirculation (approximately 40 minutes, minimum) as described in FSAR Section 6.3.2.2 and Table 6.3-3:

1. The operator will set ERCW flow to CCS HX C as > 7125 gpm by controlling valve 0-Fcv-67-152.

2. The operator will also open the ERCW supply to Containment Spray HX 2B-B by opening valves 2-F CV 123 and 2-F CV 124.

NRC RAI Question 1l b.i.

b. lnitial Conditions: LOCA on Unit 2; Unit 1 just entered Mode 4 in minimum time allowed by procedure (i.e. maximum decay heat), LOOP, and /oss of Train A electrical power.

i. ldentify required minimum flow to pertorm SR function for each load cooled by ERCW and CCS in Unit 1 and Unit 2.

E2-2

ENCLOSURE 2 Responses to NRG RAIs for WBN Unit 1 ERCW and CGS License Amendment Request TVA Response CLARIFICATION: The below responses are based on just entering Mode 4 with RHR shutdown cooling only without assistance by RCS loop cooling via the steqm generators' This is a conservative assumption as all residual heat will be placed on the RHR heat exchangers and thus the CCS and ERCW sYstems. The ERCW minimum required and expected actualflows are provided in calculation MDQOOOO672OO8O341, Appendix 17, Case 1300 (Enclosure 2, Attachment 4). This case considers flow through the hydraulic gradient discharge structure whereas the first case (question 1) a.i.) considered flow to either the cooling tower basin or to hydraulic gradient discharge structure. The CCS minimum required and expected actualflows are provided in calculation MDqOO0O7O2OO9O2O0, Appendix 11, Cases 8C and 8D (Enclosute2, Attachment 5). NRC RAI Question lt b.ii. ii. ldenttfy actual ftow to each of the loads with only Train B ERCW (i.e. 3 pumpi) and Train B of CCS (2 pumps) available because of the loss of Train A electical Power. TVA Response The attachments identified in response to Question 1) b.i contain both the required minimum and expected actual flows (determined from Multiflow as benchmarked from flow balance testing). NRC RAI Question 1l b.iii. iii. Describe operator actions and timing of operation required to achieve the required/actual flow. TVA Resoonse The operator will perform the following actions to establish ccs flow:

1. The operator will verify CCS flow to RHR HX 1B-B as > 5000 gpm by controlling valve 1-FCV-70-153 from the MCR. This would be an "immediate" action (TS 3.4.6) to restore RHR shutdown cooling after the LOOP and would be performed prior to re-starting the RHR pump (RHR pump does not automatically sequence on during a LooP).

2. The operator will verify that two CCS pumps are running on CCS Tgln B. lf not, the operaior would start the second CCS pump prior to starting the ECCS switchover sequence as described in FSAR Section 6.3.2.2 and Table 6.3-3 (approximately 20 minutes, minimum).

E2-3

ENCLOSURE 2 Responses to NRC RAls for WBN Unit 1 ERCW and CCS License Amendment Request

3. The operator will set CCS flow to RHR HX 2B-B as > 5000 gpm by controlling valve 2-FCV-TO-153 from the MCR. This is performed as part of the ECCS switchover sequence as described in FSAR Section 6.3.2.2 and Table 6.3-3 (approximately 20 minutes, minimum)

The operator will perform the following actions to establish ERCW flow. All actions are required to be completed prior to establishing containment spray switchover to recirculation (approximately 40 minutes, minimum) as described in FSAR Section 6.3.2.2 and Table 6.3-3:

1. The operator will stop the motor-driven place it in pullto-lock from the MCR.

auxiliary feedwater (MDAFW) pump 1B-B and

2. The operator will travel to the "B" train 6.9 kV shutdown pump interlock bypass for shutdown board 1B-8.

3. The operator will start the non-running ERCW pump tied to 6.9 kV shutdown board 1B-B from the MCR.

4. The operator will set ERCW flow to CCS HX C as > 9200 gpm by controlling valves 0-FCV-67-1 52 and O-FCV -67'144.

5. The operator will open the ERCW supply to Containment Spray HX 2B-B by opening valves 2-F CV 123 and 2-F CV 124.

NRC RAI Question lt b.iv. iv. Discuss the flow and differential pressure across the C CCW HX on both the tube side and shett side from the 3 Train B ERCW pumps and the 2 CCS pumps before and after ERCW flow is initiated to the containment spray (CS) HXs. Specify whether tube and shell flows and differential pressures across fhe C CCS HX are accePtable and whY-TVA Response The CCS HXs are designed for various operating cases per CCS HX datasheet, provided in vendor document WBN-WD-OO15-0020 (Enclosure 2, Attachment 6). The highest pressure drop and highest flow are for the tube side (ERCW) with 8,000,000 lb/hr (approximately t6,bOO gpmJ at 6.4 psi and for the shell side (CCS) with 6,000,000 lb/hr (approximately 12,OOO gpm)at 19.7 psi. The ERCW and CCS models are constructed based on the flow and pressure'drop identified in WBN-WD-OO15-0020 and if one value was exceeded then the other value would also be exceeded. The following data is from the models established for ERCW and CCS that are identified in the data files tor tne respective calculation, but may not be speciflcally identifled in the respective calculation. board room and defeat the ERCW E2-4

ENCLOSURE 2 Responses to NRC RAls for WBN Unit 1 ERCW and CCS License Amendment Request Unit 1 Normal/ Unit 2 LOCA Unit 1 Hot Shutdown/ Unit 2 LOCA CCS HX C ERCW Flow (gPm) 7390 9432 CCS HX C ERCW Pressure DroP (Psi) 1.4 2.3 CCS HX C CCS Flow (gPm) 8,1 46 11,204 CCS HX C CCS Pressure DroP (Psi) 9.2 17.4 The model flow and pressure drop are less than the design of the CCS HX and are therefore acceptable. NRC RAI Question lt b.v.

v. Discuss flow and differentialpressure across the ERCW strainers and traveling screens when 3 ERCW pumps pertrain are operating. Address whether flows and differential pressures across the strainers and screens are accePtable and whY.

TVA Resoonse For comparison, the following flow data is extracted from the models discussed in 1) a.i. and

1) b.i.

Unit 1 Normal/ Unit 2 LOCA Unit 1 Hot Shutdown/ Unit 2 LOCA Flow Through ERCW Strainer 1B-B (gpm) 11,462 13,366 Flow Through ERCW Strainer 2B-B (gpm) 9,878 11,407 Total ERCW Flow (gPm) 21,340 24,773 The ERCW Multiflow model conservatively uses a fouled strainer pressure drop for all cases. During normal operation, the strainers are periodically and automatically back flushed, removing debriJthat has accumulated. During an accident scenario, the strainers are continuously back flushed and the actual strainer pressure is approximately that of a clean strainer. A fouled strainer pressure drop is the maximum pressure drop during any mode of operation and bounds the accident scenarios. The ERCW Multiflow model calculates the strainer pressure drop based on the flow using the fouled strainer pressure drop input into the model. The increased flow between the cases is based on a fouied strainer which is the maximum strainer pressure drop experienced due to the automatic back flush feature. The ERCW strainers are 24-inch size. Per vendor document WBN-VTD-K143-OO2O, the ERCW strainers can handle flows up to 33,000 gpm which is well above the required ERCW flow. E2-5

ENCLOSURE 2 Responses to NRC RAls for WBN Unit 1 ERCW and CCS License Amendment Request Traveling screen effectiveness is not impacted by the change of two ERCW pumps to three ERCW pumps during an accident with LOOP event. Design criteria WB-DC-20-20 requires one traveling screen to have sufficient capacity to pass the required amount of water, although two traveling screens are available per train. Calculation EPMRCPO52992 evaluates flow through one traveling screen during accident conditions and concludes that one screen can pass the required flow with loss of a train based on TVA guidance and industry standard Practice. This conclusion is valid for three ERCW pumps or two ERCW pumps in operation. The traveling screen is acceptable for the higher ERCW flow produced from three ERCW pumps. The increase in flow across the traveling screens does result in higher pressure drop and less available submergence or NPSHa for the screen wash pumps. Calculation EPMWUCO72489 documents that sufficient margin exists to ensure that available submergence and NPSHa are acceptable. NRC RAI Question 2l The MODE 5 REQUTRED ACIIONS of proposed TS 3.7.16 and fS 3.7.17 do not appear to provide any remedial actions to place the non-accident unit in any safer sfafus in the event of an 'inoperable CS /CCS/ or ERCW train. Provide additionaliustification forthe action proposed and discuss any aiernative actions available to place the unit in a safer sfafus in the event of an inoperable CCS or ERCW train. TVA Resoonse The changes made to the TS 3.7.16 and TS 3.7.17 Required Actions provide actions to address the loss oi redundancy, similar to the Required Actions of TS 3.7.7, "Component Cooling System," and TS 3.7.8, "Essential Raw Cooling Water." See the revised TS 3.7.16 and TS 3.7.17 in Enclosure 1, Attachments 1 and 2, respectively. IVRC RAI Quesfion 3l Please provide exptanation for the reference to the 10CFR50 Appendix R fire scenario and the need for two ERCW pumps on one DG identified on page E1'11. TVA Resoonse WBN Unit 1 repair procedure Ml-0.047, Section 6.3 for the Train A pumps installs a jumper to bypass the relay contact for fire scenarios when additional ERCW flow is required. The inierlock bypasi switches will perform a similar function as the existing Unit 1 repair procedure. These swiiches will be used to support Dual Unit Appendix R requirements where Dual Unit Appendix R flow calculations have shown the need for three ERCW pumps running to place boih units in a safe shutdown condition. ln fire zones where Train A is unavailable, this will require starting two pumps from the same diesel generator backed Train B board. Note that no fire event results in the reverse situation for Train B unavailable. E2-6

ENCLOSURE 2 Responses to NRC RAls for WBN Unit 1 ERCW and CCS License Amendment Request The new interlock bypass switches will allow this similar function to be performed in a timely manner for safe shutdown. For dual unit operation, the interlock bypass switches allow Manual Operator Actions (MOAs) instead of a repair procedure for Appendix R events and thus the repair procedure will no longer be required. The new plant configuration is described in Sections Vl and Vll of the Dual Unit Fire Protection Report, previously submitted to the NRC on June 24,2015 (Reference 3). NRC RAI Question 4l The staff noted the following statement in the APPLICABILITY section of the proposed IS 3.7. f 6 Bases "... any resulting temporary loss of redundancy or single failure protection is taken into account..." This statement appears to be an interpretation of the IS, nof a bases (reason) forthe specification. Per 10CFR50.36(a)(1) "... bases orreasons for such specifications..." are to be included "... but shall not become part of the specifications." Please either remove this statement or provide additional justification for its inclusion in the TS bases. TVA Response The statement provided in the TS 3.7.16 Bases is not required for understanding of the TS and has been removed from the Bases. REFERENCES

1. Letter from TVA to NRC, "Watts Bar Nuclear Plant Unit 1 - Application to Revise Technical Specifications for Component Cooling Water and Essential Raw Cooling Water to Support Dual Unit Operation (TS-WBN-15-13),'dated June 17, 2015. [ML15170A474]

2.

Email from NRC to TVA, "Preliminary Draft RAls Associated with Proposed WBN 1 ERCW and CCS Technical Specifications LAR," dated July 2,2015.

3. Letter from WA to NRC, "Watts Bar Nuclear Plant (WBN) Unit 2 - Transmittal of Unit 1/Unit 2 As-Constructed Fire Protection Report (TAC No. ME3091)," dated June 24,2015.

E2-7

ENCLOSURE 2 Responses to NRG RAls for WBN Unit I ERCW and CCS License Amendment Request ATTACHi,IENTS Attachment I - ERCW Flow Model - U{ Cold Shutdown, U2 LOOP, LOCA - CCS Flow Model-U{ Gold Shutdown, U2 LOOP, LOCA - ERCW Flow Model with Discharge Through Hydraulic Gradient Discharge Structure - ERCW FIow Model, Mode 4'RHR Cooling - CCS Flow Model, Mode 4'RHR Cooling - CCS Heat Exchanger Data Sheet

ENCLOSURE 2 Attachment I ERCW FIow Model - Ui Cold Shutdown, U2 LOOP / LOCA

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{t 13% 0.0 NRqd EDG 182-B 0 DG1BB.2 - DGtBB i 650.0 08.0 t lsi. 76r.0 746.0 + 15% 0.0 NRqd iDG 1A2-A 0 fBBl

Fl 650.0 r,@3.9 t 60%

788.0 lA219*. 745.8

ts"r 0.0 NRqd EOG 281-8 0

DG2BB.tt - OG2BB.6 650.0 0.0 NRqd 757.6

J tlx 741.9

+ 14% o.0 NRqd iDG 2AT-A 0 436'1 - 'l8P 650.0 0 NRqd 711. S uc6 704.8 lr eY, 0,0 NRqd EOG 282-8 0 DG2BB.2 + DG2BB.S 050.0 0.0 NRqd 759.r 17% 770.8 i rg* 0.0 NRqd EDG 2A2.4 0 [8lil - 48C3 650.0 0.o NRqd 755.0 r8% 717.7

to*

0_0 NRqd EGTS RC &B 0 EGT2BDIS.4 - EGT2BDIS.s r0.0 20.8 t toex 3"9 S rery. 16.3 h og% 0.0 NRqd EGTS RC Ad 0 il)r2--+51Y2 t0.o 29.r lrsr% t8.1 tatx 20.5 iroox 00 NRqd -cc rB-B ,l t0O1 + 10E1 306.0 426.5 t ose6 293.3 4% N/A NRqd '134"0 f res6 ,cc 1A-A ,0O 4 goE 300.o 4/,02 I {s6 303.6 ] -tx N/A NRqd w.2 t sox .cc 1D B -cvcDl - rcvcD2 306"0 Ito 8 t ssse 301.7 .t% N'A l8qd /t13.9 t 35% -cc rGA LCVCC1 - LCVCC2 3G.0 a21.7 t 30% 29't.3 1 -s* NlA NRqd 371.7 7 zt'v" .cc 2B-B 2 l.tOD1 - 2.181 306.0 491.7 41% N/A NRqd 34e.5 ?rs a71.8 I erx -cC2A-A 2 5OD + 2.5oE 3m.0 490.6 i ese6 N'A NRqd 3116.6 H7% 378.8 A21% -cc 2rlB 2 .LCVCDI + 2.LCVCD2 306.0 424.5 0 sse6 N/A NRqd 158.0 + 17% 415"9 i sex lcc zGA 2 I.LCVCCI - 2.LCVCC2 306.0 512.5 iezn N,A NRqd 320.2 i596 381.0 )d zsx UCR RC SB o 15.9

15.1O 2&.O 421.8 t 76%

320.8 t sen 308.2 V zsx 423.6 irtx I'CRRGAA 0 55C -55D 240.0 434.5 El96 400.4 t erx 25t.9 Y snr 3t).8 l rzgo )c Rc tlB pCCtB.T - pCCtB.9 15.0 rll "8 179% 31.6 $ tttq6 29"4 t eox 4r.8 $ tzse6 PC RC 1&A 1 67y2

67N2 15.0 30.1 ttotlt 2'.t.7 i tsx 18.9

/r4 B% n.7 t zae6 PC RC 28 2 28124 - 28125 r5.0 26.3 t 75% r 7.0 13% 19.7 t otx 28.8 t rse. ,CRC2.A 2 87U.6 < 07M.E t5.0 9.4 trr29i6 rE.0 F 2o.r 20.8 F so% 21_1 i ose6 RBIR RC1+B lRlB.10 - ll.lC 30.0 52.7 I zego 33.2

ttq" 39-0 I aoa 19.9 t ee*

RBIR RC 1A.A I 51.19.- it.1C 30.0 17.6 t ce96 37.6 E<zsx 35.7 t 19% 48.0 O ea* RBIR RC hEB 2 lRWC2B04 - 1'lC [rlU\\lC.2BO2 - IRU 30.0 c2,6 I zoso 1(F.7 Broken 107.3 Brolten 56.7 ! egeg RBIR RC 2A.A 2 30.0 54.1 $ aoqo 98.6 Broten il Brohon 4.1 t lo"r tcP MAC 1-2 < IOSI - tozl) I i0.0 tut.8 ,12% 606.7 Broken N'A NRgd 124.0 t i3% tcP MAC l-r-A t {ilD - 50Zl 110.0 119,6 096 480.3 Broken 0.0 NRqd 1(p.7 $o* tCP IITAC t{.8 1 tCP4.8 - LCVCDOIS1 'RCpa r - RcPa-2) 110 0 131.3 + rgqb $8.2 Broken N/A NRqd 133.6 Eq ztx tCP MAC 1.}A t il0.0 117.1 Her 1l,2.3 Broken N'A NRCd 105,0 jtx RCP inAC 2-&B 2 2.'16t17'1 - 2.10S1 l2.l0lt + 2.102'l) 1r0_0 I r8.8 H8% N/A NRqd 90.4 NRqd 5.0 !6% tcP iiAc 2-1-A 2 2.!Q! < 2.50S t2,st < 2.!i02) I t0.o r87.0 t 70% N/A NRqd 128..1 NRCd r40.0 t ss* RCP MAG 2.4.8 2 2.RCPa.8 - 2.LCVCDOlSt l2.RCP4"l - 2.RCP4.2) t 10.0 'll5.7 x5% tvA NRgd 102.9 NRqd 122.4 .+ 12vo RCP iilAc 2-3A 2 l.RCEl.8 - 2.LC\\EGDISi r2.RCP3.l - 2.RCP3.2) i10.0 178.7 Sorx N'A NRqd 1r9.6 NRqd t36.1 El znx Thia Pagc Replaocd bY RevBhn 013. Page 22 ot 23

Calculation MDQ0000672008034 1 Appendix 11 -Table A1 1.5 Page 23 of 23 ?a lrl^ faila All.6: Trrt Drtr for ERCaY P I Cvr Co{tDoilnl Unlt R.q'd LormdI Xo.tlral Cs.20O e...200 UrOli ut cs, u2 LOCA LOTA Cri. tOO 6rr !00 tugln ut Loc/ u, c8 bra Cr..t00 lr.r$no ut ltt, u, au C... t00 Cu 700 til.'!h Corlpoil.i Uni Lht R.q'd Itoim.l, ilo.trtal Cre,r 200 Gu !00 Itiiloln ut cE, u2 locA LoTB Crrrl0O Xrrgh ut LocA, u2 c3 toll C.r. aoo C.!.e00 LOtor rx Ht/ ut tt Ca..7oo Cr..7oo t flln RCP RC 1C.B RCP1C.13 - 6ED8 12.0 16.7 t ose6 2.8 NRqd .8 -2% 17,0 t lzc6 RCP RC Dummy NA N/A N/A N/A N/A N/A N/A N/A N/A i.l/A RC 1&B tOGlO - 68G17 19.O 12.O l rztx 3'l a7% 28.S i czqr 42.4 t rzslt RHRP RC 1A.A !5SO - 65S8 r0.0 29.9 t 62% 24.5 ilzcw 21.7 1.1% 30.8 t ozx RHRP RC 2B-B 2 IRPRCg ' RHRPRCg.I 19.0 32.7 72i9a 21.0 .t ttx 27.0 t 42% 36.3 f, er* RHRP RC 2AA 2 il5S12

85314 t0.o 3

t 97,/o r9.9 t6% 21.8 I gtx n.3 l sr* }DBR RC SB 0 gpspg2 r 27 560.0 696.4 )7 21% 041.7 I 15% 746.t S atc6 893.1 S oex SDBR RC A.A 0 5,\\3-558 560.0 608.2 il zlx 653.3

rz*

6t0.1 i3 9% 838 2 i sost ]FPP/TBBP RC B-B 0 SFPTBBT - SFPTBB9 29.0 42.8 t.s% 33.6 .l te* 30.9 !zn 43.6 t sogt }FPPITBBP RC A"A 0 54J + 5,4K1 2S.0 17 [ &{o,6 36.7 2T% u.2 't 18% 40.9 t ozx SIP RC,18.8 SIS'I0.9

66E10 22.O 0.0 NRqd 23.6 NRqd 38.9 t ttx o.o NRqd

'IP RC IA-A B5F2

65G2 212.0 0.0 NRqd 21.6 NRqd 27.5 i ztx 0.0 NRCd SIP RC 28 SISPRCS
SISPRC9 22.0 0-0 NRqd 28.4

! 29% 22.8 NRqd 0.0 NRqd SIP RC 2A"A 2 !6FG - 85G8 22.O 0.0 NRqd 23,2 + r5% 26.8 NRqd 0.0 NRCd Stralnell&B 0 08O - 4BO1 450.0 0.0 NRqd 450.0 h os6 460.0 in o% 0.0 Special itrainer 1A-A 0 l4AO + 4,1AO1 450.0 0.0 NRqd 450.0 U 096 450.0 Uox NRqd Straincr 2BB 0 4AO

4AOt 450.0 0.0 NRqd 450.0 hox 450.0 r$ 0%

0.0 Speod r2AA rl48o - 4.1562 450.0 0.0 NRqd 450.0 I 096 450.0 t 0'6 o.0 NRqd UCC 1B-B 12O1 - 12Ll (12E1 < 12F11 23.0 21.1 Io* 46.9 Broken 0.0 NRqd 21.9 !8% JCC 1A.A t 520 - 52L 23.0 42.2 0 as* 51.8 Broken 0.0 hRqd 38.2 F ear UCC lDB UCVC1D.lQ - 72y1 TUCVCTD 3 + UCVC1 23.0 25-1 1, tZx 45.7 Broken 0.0 NRqd 8.2 14% JCC rC-A t UCVCIC.l0

52Y flrcvclc 3 - Ucv 23.0

/13.9 9t% E3.5 Broten 00 NRqd 4l.5 I eogt JCC 2B.B 2 2.1201 - 2.12L1 t2.12E1 - 2.l2F1t 23.0 33.4

rs96 o.0 NRqd 60.0 Broksn 32.1 F 40%

JCC 2A-A 2 2.520 + t, qrF - 23.0 gt.3 1751" 0,o NRqd 91.2 Broken 45.9 troox UCC 2D.B 2 UCVC1D.10 - z-12Y1 l2.UCVC1D.3 r 2-UCVCID 23.0 n-7

l 2e%

0.0 NRqd 5,1.3 Brokn 30.3

sru Jcc 2c-A 2

e.ucvclc.l0 -2"52Y f, L]cvClC.3 + 2"uCVClC-{l 23.O 33.9 17% 0.0 NRqd 74.8 Broken 43.4 F es% Brok6 1-1054&8 10tA.l + lOBl N/A t{/A N/A N/A N/A N/A N/A N/A N/A Iroke 2-i0t{A A .50A - 2.5088 il/A N/A N/A NIA FUA i.lrA ivA N/A N/A 3roke 1-t05{D.B 10Al - 1082 N/A n/A N/A NiA N/A N1A N/A N/A N/A ,roke 2-109tC-A 2.5OA

2.5G5 lvA N/A N/A T{'A t'l/A NIA i.l/A NJA ruA Broke 2-10548-8 10A1 - 2.1081 t-tiA NiA N/A N/A N/A N/A N/A r.UA t{/A lroke t-'1054+A iOA - g@3 N'A N/A N/A N/A f{/A N/A N/A T\\UA N/A Sroke Z-1054O-B

.t0A'l - 2.1082 N/A NIA N/A N/A N/A N/A N/A N/A It/A Srorc 1-10S4C-A SOA - 5085 tvA N/A l.l/A N/A lvA N/A MA N/A N/A Scrn Wsh P 2B-B 0 BP3O

BP32 10.0 5

f tsx 9.8 t -zx 9.1 U-w 2 21% Scm Wsh P IAA 0 1925 t AP27 r0.o t4.6 tr46% .i rox 'l l.E 18% 11.2 F rex Scm Wslr P 1B-B 0 BP3O

BP30 10.o r.3 i tg"r

,6 & -+.r $ -ttx 2 ,h zlx Scm Weh P 2A-A 0 AP25 - AP29 10,0 10.6 H6% 8.5 -15% 8.5 -'t5% 10.3 ts3% SAC AflerC A 0 SACA.I -- SACA3 5't.0 54.0 iH 0o,6 54.0 rd 0% 50.r S -rx 54.0 bo% SAC AnerC A 0 SACA.I - SACA.3 54.0 54.0 id 0% 54.0 tt oq^ 53.0 l -zx 5,1.0 0% SAC Gylind A 0 SACA.2 - SACA4 wA N/A N/A N/A NIA N/A N'A N/A N/A SAC CYlhttl 0 SACA.2 < SACA.to N/A N/A N/A N/A N/A N/A f.l/A N1A iAC AfierO I 0 SACB.I - SACB.22 54"0 5a.0 E0% 54.0 @fo fi.2 -7sh 54.0 t oc6 SAC Af,TC 8 0 SAC8.l :. SACB.22 64.0 54.0 .}l o'a 540 J0% 53.1 lb -zx 54.0 id 0% SAC Cyllnd B 0 SACB.2 - SACB.4 IUA N/A N/A N/A N/A l.l/A N/A N/A N/A SAC Cylhd B 0 SACB,2 - SACB.4 N/A N/A N/A N/A tl/A N/A tl/A N/A N/A Src ANArc C 0 SACC.1 :- SACC.22 5.1.0 54.0 ]/ OCs 54.0 b0% 49.4 & -ee6 54,0 I os6 SAC Anero C 0 SACC.1 - SACG,22 64.0 11.0

ogo 54.0

'N 096 52.4 9 -sx 54.0 !o% SAC Cylind C 0 SACC.z - SACC.4 N/A N/A N/A N/A N/A N/A N/A N/A N/A i"AC Cylittt C 0 SACC 2 - SACC"4 N/A N/A N/A N/A l.l/A t{/A N/A N/A N/A SAC O 0 SACD.2 - SACC.24 96.3 r3{t.6 t 42% 12.1 i,n 1796 108.7

10%

127.0 t 33% SAC O 0 SACD.2 < SACC.2'l 96.3 130.6 t azr 103.7 'r 8% 100.4 'g a% 127.6 t ss* SAC B Hee<lcr aSMr -) sEM2 N/A 0.0 N/A 271.4 N/A 258.4 N/A 0.0 N/A SAC A Hsader 50, 5gA N/A 298.6 }UA 2067 N/A 250.0 t\\UA 289.6 N/A SPLY CNTMT COOLERS r0Bl,1,2.10ts1.2 N/A 679.0 tl/A t{/A N/A 621.4 frl/A 780.7 t{/A SPLY CN'TUN COOTERS 2.LCVCCSUPI

2.LCVCCSUP2 N/A 840.7 N/A N/A l.l/A 575.7 N/A e32.9 N/A SPLY CNTMT COOTERS 2.LCVCDSUPT - 2.LCVCDSUP2 880.3 N/A N/A N/A 639.8 l.UA 687.9 N'A SPLY CNTMT COOLERS 2.5081 + 2.5082 N/A 84S.2 N/A N/A N'A 6ro.8 N/A 651.

l-l/A 'PtY CNTMT COOLERS 1081.1 108i2 N/A 730.c N/A 1,057.9 N/A N/A N/A 738"0 N/A }PLY CNTMT COOLERS 5081 -)5082 N/A 768.0 tl/A s36.4 N/A it/A il/A 697.3 N/A SPLY CNTMT COOLERS LCVCOSUP1 - LCVCOSUP2 N/A 776.3 N/A 93t..l N/A N/A N/A 776.7 NIA SPLY CNTMT COOLERS ,CVCCSUPI

LCVCCSUP2 N/A 54r.7 N/A 85iI.3 N/A N/A N/A 62?.2 MA t

Greaertun 3o% ftor rnargin d Bs&reen 2}a/oe(vi 30o/o llotr, tnergin

=S getrreen 10o/o and 20% llo,v margin

\\ g"tr*"n ff6 and 10% llor margin g Less lhan o% no'i, margin Notes:

1. Caga 300, 400, 500, 600 con8ider loes of do.Ynst esrn dam and broken coolers.

2, All cases mncider 93% pumps. Thia Page Replaced by Revision 013.

ENCLOSURE 2 CCS Flow Model - Ui Cold Shutdown, U2 LOOP / LOCA

Table 1 Component Train Llnk Req'd Cace 7Y\\8, - Unlt I CSr2 LOCA, C, Traln B Caso 7Ktr.- - Unlt I CSrz LOCA, ZB'E,, Traln B Tegt Flow (spm) Cv Flow @ 90%P (gpm) lilaryln Teet Flow (gpm) Cv Flow @ 90%P (gpml taryin Flow @ 90eiP (gpm) Margln Cent Chr Pump 1&B B 169 + 190 28.0 34.31 N/A 32.8 'l7olo 34.04 N/A 33.0 18% 32.4 16% CCP 1B-B Lube Cooler 2A 2718 -* 289 20.0 22.53 4.90 21.5 8o/o 22,il 4.89 21.s go/o 21.5 BVo CCP 1&B Gear Cooler 2A 272 + 273 8.0 11.78 2.67 11.2 40o/o 11.48 2.58 11.1 39% 10.9 36% Cent Chr Pump 2BB B U21Eg.-' U2190 2E.0 32.33 N/A 31.0 110h 32,09 N/A 31.1 11o/o 30.6 9o/o CCP 2B-B Lube Cooler 2A U22718 - U2269 20.0 22.24 5.14 21.3 7% 22.23 5.11 21.6 8% 21.2 6Yo CCP 2B-B C,ear Cooler 2A U2272.,.-t U2273 8.0 10.09 2.fi 9.7 21% 9.85 2.24 9.5 1S/6 9.4 184/o CS Pump Oil HX 1B-B B 2O3 + 204 2.0 6.90 1.34 6.6 Z3fflo 6.71 1.30 6.5 225olo 6.4 22OYo CS Purnp Oil HX 2B-B B U2203 - U22O4 2.O 6.84 1.41 6.6 230% 6.72 1.38 6.5 2250h 6.4 22io/o Radiation Monitor 0-RE-9G'1 23 B 1 80C -* 180D 2108 - 21OA 6-0 O.EE N/A 6.1 2o/o 0.89 N/A 6.1 2% 6.1 20h RHR HX 1&B B 208 - 2OT 2,7?5.O 2U4.64 563.83 3000.0 100h 2835.68 561.68 2753.2 1.03% 2920.O 7o/o RHR HX 2B-B B U22C/6 + U22O7 5,000.0 5251.91 2253.N s000.0 ooh 5178.04 2079.2 5109.1 2.18% 5000,0 0% RHR Pmp Seal Water 1B-B B 199

200 10.0 13.82 2.83 13.2 32%

13.80 2.83 13.4 34% 13.2 32Vo RHR Pmp Seal Water z&.B B U2199 + U22OO 10.0 12.71 2.75 12.2 22o/o 12.67 2.73 12.3 23o/o 12.1 21olo Sl Pump 1B-B B 194 --+ 195 15.0 20.74 4.11 19.8 32o/o 20.17 3.96 19.6 31% 19.2 28o/o Sl Pump 2B-B B U2194 -" U2195 15.0 1E.52 3.93 17.8 1gofr 1E.1 1 3.81 17.4 17% 17.3 15o/o Calcu lation M DQ0000702009O200 Train tlzB Noteg:

1. Test florar3 are nominal values minug ingtrument inaccuracy.

2. Margin is the percent difrrence betureen the "Req'd* flow and "FIou, @ XX%P (gpm)".

Appendix 10 CCS Flow Batance Test Results for Dual Unit Operation Page 5 of 5 Component Traln Llnk Req'd Gase 7UF - Unlt 1 LOGAT2 CS, C, Traln B Case 7l'F - Unlt 1 LOCAT2 CS, 2B'A, Traln B Tegt Flow (gpm) Cv Flow @ 9f/uP (gPm) tlargin Teat Flow (gpm) Cv Flow @ 90P/oP (gpm) ttllaryln Flow @ 90oiP (gp,m) Hargln Cent Chr Pump 1B-B B 189 -+ 190 28.0 35.53 N/A 34.8 24Yo 31.10 N/A 30.3 8016 30.6 9o/o CCP 1&B Lube Cooler 2A 271E - 269 20.0 24.38 5.41 23.9 20o/o 20.32 4.24 19.8 -1Vo 20.0 Oo/o CCP 1B-B Gear Cooler 2A 272 + 273 8.0 11.19 2.53 11.0 38o/o 10.70 2,31 10.5 31Yo 10.5 31olo Cent Chr PumP 2B.B B U21E9--* U2190 28.0 32.78 N/A 32.1 15olo 32.71 N/A 31.9 14% 32.2 15% CCP 2*B Lube Cooler 2A U2271B --+ U2269 20.0 22.89 4.82 22.4 12o/o 22.82 4.E1 22.1 11o/o 22.3 1?h CCP 2&B Gear Cooler 2A U2272 + U2273 8.0 9.E9 2.09 9.7 21o/o 10.09 2.16 9.8 23o.h 9.9 24Vo CS Pump Oil HX 1B'B B 203 -- 204 2.O 6.46 1.24 6.4 220o/o 6.51 1.28 8.4 2200h 6.4 22OVo CS Pump Oil HX 2&B B U22Og - U22O4 2.O 6.92 1.32 6.E 24Do/o 6.90 1.32 6.7 235a/n 6.8 24Ao/o Radiation Monitor SRE'90-1 23 B 180C -r 1E0D 2108 --.210A 6.0 0.90 N/A 6.1 2% 0.88 N/A 6.1 ?alo 6.1 20h RHR HX 1&B B 2AB + 2O7 5,0@.0 51 1 5.50 1671.3 5000.0 OYo 5088.00 1683.2 4966.0 -0.68% 5000.0 ooh RHR HX 2&B B U2206 + U22O7 2,7?5.0 2A74.67 549.E 2820.O 3o/o 2848.15 548.38 27s2.s 2.490.h 2725.0 ooh RHR Pmp Seal Water 1B B 199 - 200 10.0 13.22 2.66 13.0 3004 12.79 2.57 12.5 25% 12.6 260/o RHR Pmp Seal Water 2B-B B U2199 ---r U2200 10.0 13.02 2.59 12.8 28Vo 13.10 2.63 12.8 28% 12.9 29% Sl Pump 1B-B B 194 + 195 15.0 19.27 3.74 18.9 26Yo 19.40 3.80 18.9 26% 19.1 27% Sl Pump 2B-B B U2194 -" U2195 15.0 18.69 3.64 18.3 22% 18.38 3.60 18.0 2A% 18.1 21olo This page added by revision 009.

ENCLOSURE Z ERGW FIow Model with Discharge Through Hydraulic Gradient Discharge Structure

d Foco.t o G3 E !t Eoa6 o. .nEF 3o- =(,Eul bg et-a, = bTo -Eo 1-Ea b(9 o F

trF oEoF Ioi te iE s

rO GI B attdtt

I E

rO (l 6 aIe Iool flr C' A rto A tloN tr a tO ,F o a(, I s!N K E .gE6g s gt

n oo

!oo fF + Eq G = 1'o G,z E .E eo caZo ro H N il Eq Ez ItO A Ere-s !F Ia I s Iarl IF + to ln to A

o 6',

EIt E,2 E(ttr2 *I A IN A !sri C' r.t !Fo rF q (r) F FrF ao q nl ,F tO F q N rO N l\\d N q s l[t rri clo N 6io ?d o G, to (F F t {z !,\\ rO q 1\\c, (F at q Na'l lOg t-ro oo G'IGI o. FNF o ,F G'l\\ ul F E GIg F qo IF dz z q,\\ rF G) F IF G' ir IFl',& IC' A (rl!6 a (lD iFs ata Io A GI 6

o s

I(\\l A I ,F + d, o IN + tEIt 6 r.)I A E .gUo.l R tr Etttrz touz EC G, = EcG-e tr,z *NN qs BEz f I 6 a to ^E Es

o IF 6

Gl F d

iIF 4T I!?Ft aIa It-Btrz B

G-iXsi o ,F q G' i. F. ut c.l GI iF o a't N oci F Gl G. - IFo o N N6 Gl Gl N E. U' qo rF oo{ qo o 3\\l N!P qo (r, q]\\ IF 2 (2 \\I G' oci Glot rd G'.t 'FCI o.rll F o GI t\\T\\ o sl l\\ t C'tF tF o s N o.tcl (2 (z ptoE C' c.i o ot rF c IP !F q rF F o 6lrF oci rO rF q GI C' !l q ra, N c, rtN q cl rO(, ut oICI r.t q g (F q od' N C'jN IF qrt Gl tF qo N eoN qIN ro' o d N ro' H C) Ito C' C) do qIo qo iF q H q H q fi ot GI !E J g tIt !oI I !t ciI No T\\o t (\\lUt\\6 o' c, Fo ? !tUIt\\o

Glc, Fo

? No ho o C't\\ rD t E lr6 ott rO t E E g E T E E (1 o.il t Glo E a-\\oo rJ) t ,FoI NILI t 6! uto ro (D to (tt C' GI C' t (r) C' E t g og I 6 ltro5l t rrtF ts e !t Ito tat NI E,o t E E,o 3 lO a,i t !o r., rli (\\lIc,o c,i JItr(, ^i N = 1/D!o I .\\. = ral rD = ro ID tq = l., 6 G' rO t aril 16 (lr Roo t GldlI' Ir.l U' t Et\\u) ltGt t !F ruo rD TLot t rF B a Got t !FI Q rr) Btl t.6ri N E t T E utI toI N(JIIt () 99 IUI..i toI6i Gl(,II Gl f rF(,ItJ 1\\l GC:t (l! ct !F rF t\\a d (\\a{ o o c, N rF (\\. G. o (.D Gl N lF N tF (\\l C' o o o o o tF rF Gl (\\l 'l EA Erl t rF oE u a

o c,

hrC an t ? oc, l', rF F tNoE Aa !F,\\ t o G,I. at! L T N C'tri-GI f\\ I eo g EBo T(, G. o. E s l-il I o G, G C) (J

otr o.oIJ o

t? { Irooo aat { xTo C,(t Ig dxIaI cl!f ? dIa tt totr o.3 ll.(oI Io =atr (J $o =6l E. (J t6.o-o E,(l d No BE (J II Goo

o G,

o.o(t I ,F t(-oo (l

Ioo(t toE E,oul f(P

?I ru .(( Itu + F H H To g,oFc,rll I q d q I GIoq rl C'q 3r T5

rll a}'

6

I t\\t\\

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Calculation M DQ00006720080U1 Appendix 14 -Table A14.1 Page 7 of 17 .-.?^ l,r.-l-.-ltr AriL-. trt--L GloarrOrrn a^, EE4nfft ilrti-I flfrq CnOlem Dllchrqq-StE@urr for ERCW pumpe' CYr

lllllf, At".

l.

ltg flrra!-5trb Srt Canpomilil brrarlf! t u lrrrrrl tftrfi R.q,d UI CE' u2 LocA r,oTA Clra t00 G0t0 ItrOln UI LOCA' ITIG! LOIA Grl. t00 Crr. t00 llryrre Goononmt Unlt Llnt nfil UI GB' Ut LOGA LoTB Cua0 Grr. a00 llr[ln UI LOGA ' ttc8 brB C.r t00 Gu. a00 m.Oln MCR RC B8 0 t5.E.+ 15.10 240.0 u21.2 D s{* 309.3 fr*x fJrcR RC A'A 0 56C.- !!D 21o..O 300.0 0 er* 217.1 U 316 PC RC T}B I FCqAT - PICC18.0 r5.0 31.0 $ tozx 20.5 0ezt PC RC 1A"A I B7lUt2 +67N2 r5.o 212 0lt* 1E.5 F zse6 PC RC 2}B 2 28121-?8116 t5.0 19.7 e fi99 r9.E t s2e6 FC RC 2A'A 2 B7il.0 a 67M.E r5.o 17.3 S rsr 20,.2 1 ss* RBIR RCI}B I lRlB.t0- tl.lC 30.0 32"8 U et6 39.1 S so* RBIR RC IAA t 51.lE - 51.lC 30.o 36.9 Fnx 35.1 N rnr RBIR RC 2}B 2 lmrUC[lBO4-tlO fl Rtirc2ECIl -r lRtiG2BO8) 30.0 107.7 Brokn i(n.9 Bten RBIR RC '+A 2 FmrczAm'- lRWC2MS nRum2A0lil -* lRlildlA03) 30.0 00.3 &o0isr 712.1 Bmlrcn RCP rrtAc 1-2-B 1 lo/1.- 161 ndt < rozt) 110.0 w.1 Bmlten N'A NRqd RCP lrAc l-1-A t SOt/.-'508 1501 -+ 502) il0.o 494.8 Brolrat o.0 NRqd R@ MAC l-f I RCP4.E - LO/tCDDNil tRCPa.l -+ RCP42) 110.0 &.1 Bmlren N'A NRqd RCP riAc 13{ I ncpg.a-- LCI/GOSI mCP3.1

RCP3.2!

1ro-o u7.o tsolten N'A NRqd RCP MAC 2.bB 2 2.1(lVl - 2.1GSi 12.1011 { 2.t0Zll 1too N'A lfrqd ge.8 NRqd RCP liAc 2-t.A 2 2.5OV -. 2.SG n-ffi -+2.5OlD tto.o N'A inc 121.8 NRqd RCP MAC 2+B 2 LRCP4.S - 2.LCIEOOIS! l2.RCPa-1 + 2.RGP42) fi0.0 N'A NRqd 103-3 NRqd RCP itlAc 2-$A 2 2.RCP9.8 LCI/CCOSI I!LRCP3.1.- 2.RCP3.2) Ito-o MA t{Rqd fi6.5 NFqd RCP RC lGB I RCP1C.13 -r68f,lE 12.0 12.5 NRqd 1r.e I -rx RCP RC DummY tlA N'A N'A N'A liUA N'A RHRP RC T&B I 88Gi16 +68Gt7 19.O 31.1 frel* 2?,-o t sor RHRP RC IA"A I E5S6.- 65S4 19.0 24.1 F zr* 21.3 O rar RHRP RC 2}B 2 RHRPRC9 - RI{RPRC9.1 t9.0 20.8 b oe6 27.1 $ lse6 RI{RP RC 2A,A 2 BOS12 --65514 19.0 t9.1 Hr% 24.O F zesr SOBR RC &B o SDBRSI *21 sab.o 8S}6 S ragr 71]g.3 $ slgt SDBR RC A'A o 55A3 + 55E 50.0 041.2 I rsgt 5S.1 U?% SFPP/TBBP RC }B 0 SFPTBBT - SFPTEBO 29.O 33.0 $ rl* 3t.o Ut*, SFPP'TBBP RC A"A o 54.l { 54K1 29.0 s.0 7 ztx 3!t.5 O ton SlP RC 188 t ststB.g -68Et0 a2.o 23.1 NRqd 39.r 0 zer sP RC rA"A I 85F2 -.oGtiG2 z2.o 21.1 NRqd 26.E Fzx stP RC 2Fie 2 SISPRCS.-' SBPR@ a,";o 27.9 F ztx z2.e NRqd SF RC 2AFA 2 65F6.*65G8 a2.o 21-g I roro 20.0 NRqd Shahcr t&B 0 IBO - 4BOl 450.0 460.0 U 006 450.O ( oe6 Sffitcr 1A"A 0 a4AO - 44401 4!io.0 /fiO.0 b oq6 450.0 I 016 Strlncr 2&8 0 lArO - 4AOi t50.0 450.0 b oe6 450.0 t oe6 Shchar 2A"A o f4BO.- 44@2 450.O 450.0 lor .l!n.0 b 006 UGC I&B t t2Ol a 12L1 n?El-r 12Fl) 23.0 46.8 Bdn 0.0 NRqd lrCC tArA I 620 - 6iill 6ilE -+ SllF) 23.0 5t.1 &uhen o.o NRqd ucc IDB 1 UCt CiD.lO - l2Yt (t.lclrCl D.3'+ llCt/Cl D.4) 2?.O 45.6 Brdten 0.0 NRqd UCC lGA 1 l,rCtClC.lO - SllY [UCVC1C.3 -+ [.]CVC1C.4) z3.o E3.r Em0tgr oo l.nqd ucc 2eB 2 2.l20f 12L1 iL12E7 +2.12F11 23.0 0.0 NRqd 50.3 Brdn t cc 2A"A 2 2.5:p + 2.52L t2-&2E-2.52F) 23.0 0.0 NRqd 50.7 Bldtan UCC zDB 2 2.t ClrClD.l0 + 2.1!n t2 tlc\\ret D-3 -. 2.llC\\lCl O.4) 29.0 0.0 NRd 5&7 Broltgr lrcc 2GA 2 z.trcv0lC.lO -- 2.6*l n-UC1rC I C.3 -o 2-tlCt/C I C.a) 23.0 0.0 NRS 71.1 Mn &oho 1-1064&8 t0Al - tOBt N'A N'A N'A N'A N'A Br[o 2-106{A.A 2.50A + 2.50Blt N'A N'A N'A N'A N'A Bpha t-l054DB l0Al - 10&l N'A N'A N'A N'A N'A Brdts &1031C.4 2.50A-- 2"5085 N'A N'A N'A N'A N'A Broke 2-105{eB 2.t0Al < 2.1(El N'A N'A N'A NUA N'A Brol0 1-105:{/hA 50A-' 50Bg N'A ltA N'A N'A MA Brolc 2-l0n4t}8 2.1OAr.+ 2.10&l N'A N'A N'A N'A MA Brolio t-t03lC"A 50A -.5085 N'A N'A N'A N'A N'A Scm VUBh Pz&lB 0 BP30 -+ EP3il 10.0 s.9 S -r* 9.1 $ -sq6 Scrnwth P lAnA 0 AHIS -+ tiHl? to.0 fi.E I rart 11.E O rsn Scrn Woh P 1&B 0 BPal..+ BF!i4 to.o 9-7 & -3!6 a9 & -rr* Scrn Wrh P 2AF,A 0 APilS - AHl9 ro.0 8.5 D-rsr 8.5 9 -rsr ThF P4e Amsd bY Reulslon 016.

Calculation M DQ00006720080 U1 Appendix 14 -Table 414.1 Page 8 of 1i hhlr Atl-t: To l{udmullc Gndbnt Dlrrchemc Stnrcftrm fo" ERCW Dumrr, Clrt ffirc Gndtont Dlecherrgc Structutr lor ERCW pumpo L Gw Gomponrot t&til Ur* w ul c8, UI LOGA to?A Cr.. t00 Crr. t00 iferltn Ut LOCIA, utcg L0?A croo t00 Crro t00 tlsrglne Cootporrnf UoI Lhr Raq'd ui ct, ut locA LoTB G0. a00 gtr.tl0o riqgfn U' LOGA' t2ct LoTB GD. e00 Crrt0 Eflh sAc Arb'cA 0 SACA"I - SACA3 5a.0 5{.0 Usr 49.8 1 ero SACAMtcA 0 SACAI < SACA3 54.O 54-0 i! o% 53.6 1 -rr SAC CymdA 0 SACA2'- SAGA"4 N'A N'A N'A N'A MA SAC Cylind A 0 SACA2 '+ $ffi[{ ' N'A MA N'A MA N'A SACAtLrC B o SACB.I - SAICB.ZI 54.0 5a.0 !ort 50.0 I -tx SAC AMIC B 0 SACB.I - SACB.22 54,0 54-0 Vox st.7 $ -r* SAC Cy[nd B 0 SACB.2 -- SACB.4 N'A N'A N'A itA il,A SAC Cylind B o SAC82 + SACB.4 N'A N'A N'A N'A N'A SAC AllslC C 0 SACC.I - SACC.22 54-0 5a.0 bo* 19,.2 j -ee6 SAC AfrctC C 0 SACC.I -r SACC.22 5.1.0 5.t.0 U oq6 53.0 l -zx SAC 6!{ndC 0 SACC.2 -- SACC.4 N'A N'A N'A N,A N'A glC Cyllrd C 0 SA0C2'+ 6ACC.4 N'A N'A N'A N/A N'A SAC D 0 sAcD.2 - sACC.24 90.3 t13.7 I rs* 1(lB2 0 rzr sAc o 0 SAICD2.- 8ACC.24 g8-3 10{.6 u0n r01.6 U oe6 SAC B Hodsr EAmr + 88t12 N'A n5.7 N'A 25;t.2 N'A SAC A Heeder 50 + 594 N'A 266.6 N'A 202.0 N'A SPLYCNTI'IT COOIERS 2.108r.1.) 2.1(81.2 MA N'A N'A 625.3 N'A SPLY CNTMT COOIERS 2.LO/CCSUPI - 2. LOICCSUPII N'A N'A N'A 5652 N'A SPLYCNTT'T C@LERS 2.LC1/CffiUPl + 2.LC1/CDSUP2 N'A N'A N'A 640.E l.lrA SPLY CNTTiTC@TERS 2.5081,2.S182 N'A N'A N'A 600.r N'A SPLY CNTTIIT COOTERS 1081.1,'lo8l.2 N'A 1,057.5 N'A N'A N'A gPt YcNTilTcoolERs 50Bt + 5082 N'A sto.7 N'A N'A N'A SPI-Y CNTMT COOLERS LCI/trDSUPi -. LCIICDSUHI N'A gn.7 N'A N/A N'A sPt Y ct{TMr cootERs LCITCCSUPi "+ LC\\TCCSUPII N'A 8/19.0 N'A N'A wA t Greeterlhan t)% f,ov m*gf,n Botlueen 2$6 and iln6lbrt matgln En4 BeUueen 1096 and an6 frfi, magin qJ Bstrreert (})6 and 10% f,ow merg[n I Lece than o% fior margin Notes:

1. Caeee 3(Xr. 400, 000; 6m comider loss of donwrslneam dam and bmken coffir3.

2. N cess congldcr 93% Pumpe.

Thlc Page Added !Y Ret,Ebn 016-

A142: To Gndlent SUnchrto fur ERCW tCw Componcnt thil Unlr Req'd ur c8, U2 LOCA LotB Crlc 100 Gere l0O ttlrnEt UI LOCA' ucs .LoTB Grrr 800 C.se G00 trrgln 892',RC lA-A 1 06D2-* 66G2 12.0 18.4 S ssr 15.3 Fnx GOZ RC aqnA t&2 86D.4 -r GGG.4 t2.o 12.O U oq6 16.2 S ssr 7t3, RC 1&A 1 ttEz-67(}fl. 11.0 16.0 tls* 142 Fztrr 713'RC 2AFA t&2 glBl -,07G0 11.0 122 I rtso 17.1 O ssr 737 RC 1A,A 1 B7S2 -+ 67G2 12.O 29.7 0 ge* NA $ zost 737 Rc 2A"A I &2 6754-1 07@ 10.0 10.8 Usr 12.E fl zer ACASAfu'cA 0 54Rl + tf0l 1.5 1.7 S rsr 1.6 b 'zr ACAS Cyhd A 0 S{R -- $4Q 2.O 2.2 D ro* 2.1 U 5e6 BATP'AFYUP RC IbA 0 ilo2<ilP.Z 60.0 61.3 Uz* 75.4 fl eer CCP RC 1A"A I 58Dt.+ 58D2 25.0 n.a I test 29.3 O tzq6 ccP Rc z,"'A 2 58E2 -"+ff2 25.0 2E.3 I rsr 32.8 0 stit CCS IhAFA (1'm) I l00D < 19 5,050.0 5,889.2 O rs* 5,170,2 d ztx CCS lh AFA (1t13) 1 103 -.r 1O3B 0.0 Eohbd 0.0 leffid CCS Hr B-A (116) 2 106 + 107 5,050.0 1i79.2 &t* 5301.8 Us% CCS Hx B-A (f) 2 t06A+ 1068 0.0 laolatod 0.0 lsdebd CCS/AFWP RCA.A 0 56T5 - 55F 102.0 124.9 0 zzx t21.9 i zo* CRDMC 1A.A I 50H + 5(U 124.O 130.9 NRqd N'A NRqd CRDMC lGA I CRDC1 < CRDC2 124.O 11?.7 NRqd N'A NRd CRDiJlC 2A-A 2 2.50t1+ 2.5(N 121.O N'A NRqd 191.7 Brcken CRDMC 2cA, 2 2.CRDCl-r 2.CR0C2 124.0 N'A NRqd 137.2 BroliGn CSP RC 1A.A 1 85il,12 -* BSN2 28.0 31.2 NRqd 35.1 d zex CSP RC 2A"A 2 65M.6.- 6!lltl4 B.O 34.3 D zsx 32.8 NRqd CSS F0t tA"A 1 53 1 53A 5,2q).0 0.0 NRS 5,512.3 b6rt CSS F0( a{.A 2 58.2 + CS2A01 5r00.0 5,160.2 9 -tr 00 NRqd EBR RC &A 0 578

55H 300.0 319.5 Bzx 302.0 U te6 EDG 1A1.A 0

lSEl -.48F 650.0 Tn.1 O zo* 725.2

rz*

EDG IA2.,A 0 tSBl + 4EFl e50.0 n82

ree6 735.3 ) rgr EDG 2A1"A 0

lSCl

48P 660.0 720.8

$ rzx 8e4.8

Utx, EDG 2A21A 0

{8M - 48C3 650.0 749.7 *rx 797.e M ee6 EGTS BC A-A 0 ilX2 - i4Y2 10.0 17.5 S zsqt 20.0 Otmq6 LCC 1&A 1 50D - 50E 30E.0 xn.2 & -s* N'A NRqd LCC tC-A 1 LCVCCI --+ LC[/CC2 308.0 28p,2 Scr N'A NRqd LCC 2A,A 2 2.fiD -r 2.5(E 306.0 N'A' NRqd 31E.0 ! 4e6 LCC zC"A 2 2.LCVCC1 + 2.LCVGC2 306.0 N'A NRqd 312.5 b% MCR RC &A 0 5!iQ -+ 55D 21o,.O 3e4.7 S elst 248.7 U 4et FC RC lAd 1 O7M2-- 67N2 t5.0 21.6 Slr* 18.9 F zer PC RC 2A.A 2 67M.6 -+ 67M.8 r5.o 17.4 ) rer 20.2 $ ss* RBIR RC IA.A 1 51.tE -- 5l.lC 30.0 37.1 il ztx 35.3

rs*

RB]R RC 2A"A 2 lR\\ rC2AOa -r lRWC2Afii 0RWC2A(I2 --+ IRWG2A03) 30.0 99.5 Brolen 112.3 Brcken RCP MAC t-14 1 ffIV + 50fi (501-+ 50ZI 110.0 t096.8 Brdtalt 0.0 NRqd RCPMACl OA 1 RCP3.8 < LCVCDIS1 (RCP3.1 - RCP3.2) t 10.0 149.0 Brolrcn N/A NRqd RCP itAC 2.1.A 2 2.5(ry -r 2.5OS n.S0l -+ 250iD 110.0 N/A NRS 123.1 NRqd rcP MAC 2-$A 2 2.RCP3.8 -, 2.LCVGCDISI E.RCPJ.I --r 2.RCP3.2) 110.0 N/A NRqd I 18.8 NRqd Calculation MDQ00006720080 U1 Appendix 14 -Table 414.2 Page 9 of 17 This Page Added by Ra,lsion 016.

TaUe Al{2: To Gndlelil St,chrrr bf ERCtfU pumps I Gw Contponcnt tlnlt Unk Roq'd ul c3, u2 LOCA LoIB Cere 400 Co.c 100 f,lt!ln ur locA, ue cg TOTB C..e C00 Cuc00 nsrdn RCP RC Dummy l.lA N'A N'A N'A N'A tUA RHRP RC T&A I 65S8 -+ 6{}S8 19.0 21,5 0m 211 Dun RHRP RC 2A.A 2 65312 < 05514 19.0 19.1 Ut* 24.1 fi zrx 8D8R RC &A 0 55Ail -. 55E 560.0 6a4.0

rsx fiz.2 U8tt SFPP'TBBP RC&A 0

&{J --+ 54Kl 29.0 36-4 fl zest 34.0 O rzs6 SIP RC lAA t 85F2 -.66G2 a2.o 24.6 NRqd 27,1 fi ztx SIP RC '4FA 2 85F6 -+ 65G8 22.O 24,l 0 tt* 20.1 NRqd Sffiir1&A 0 {4AO + 44fiQ1 460.0 450.0 Uox 450.0 Uott Shalnr 2&A 0 l4BO -t 44BO2 450.0 450.0 ! oso 450.0 b$t ucc 1&A I 52O + 52L (52E + 52R 23.0 51..0 Btokgn 0.0 NRqd ucc lc'A I UCVC1C.l0 -. 52Y ruCVG1C.3 --r UCMCIC.O 23.0 83.8 Brolcn 0.0 NRqd ucc ^fo,4 2 2.5aO

2.5ill f2-il2E -+ 2.52F1 23.0 0.0 NRqd 50.9

&picn ucc 2c"A 2 2.UC\\01C.10 -" 2.5 ( fil.t CVC1CS --r 2"UCVCIC.4) 29.0 0.0 NRqd 7a.5 Bolcgt Broke 2-1054A"4 2.50A -.r 2.5083 N'A N'A N'A N'A N'A Broke 2-10!t4C-A z-fl,A -+ 2.5085 N'A N'A N/A N/A N'A Brolc l-lOE{&A 50A.- 50EXt N'A N'A N/A N'A MA Brofts 1-1054C-A 50A - 50Bs N'A tvA N'A N'A N'A ScM W$ P 1A"A 0 AF'i2S- !P,tl t0.0 11.9 i ree6 fi.9

rgq6 Scm Wrh P 2&A 0

AP:t5 - AP29 10.0 8.6 1-14% 8.0 J*x SAC AnalC A 0 SACA.I -* SACA.3 5t.0 0.0 N'A 0.0 N'A SAC qffnd A 0 SACA.2 --r SACAI N'A N'A N/A N'A N/A SAC AftElC B 0 SACB.I.* SACB22 54.0 0.0 N/A 0.0 N'A SAC Cyffnd B 0 SACB.2 -, SACB.4 N'A ltA N/A N'A N/A SAC AllatC C 0 SACC.! -r SACC.2il 5{.0 0.0 N/A 0.0 N'A SAC Gytnd C 0 SACC.2.- SACC.4 N'A N'A N'A N'A N'A SAC D 0 SACD2 + SACC.24 96.3 120.5 I tsx 113.7 I tess SAC A Headcr 50,504 N'A 120.5 N'A 113.7 N'A SPLY CNTlIfrT COOLERS 2.LCVCCSUPI + 2.LCVGCSUP2 N/A N'A N/A 566.r1 ttlrA SPLY CMT,IT COOI.ERS 2.5(81 ' 2.5082 N'A N/A N'A 601..0 N'A SPLY CNIMT COOLERS sBl ' 5082 N/A 934.9 N/A N'A N'A SPLY ChtTMT COOLERS LC\\/CCSUPI -+ LCVCCSUP2 N'A 852.0 N'A N'A N'A Calcu lation M DQ0000672008034 1 Appendix 14 -Table 414.2 Page 10 of 17 t Greater than 3096 llouu rnargin @ Betwn N%and 30% flor margin tr+ Betureen rer6 and 20% floY margin S Behrcen o% and to95 frou margin & Leee than o% lfou, margin Notes:

1. Cases 400 and 600 onsider loee of dornetream dam and brcken mlers.

2. All cases oonslder 93% pumps.

'This PageAdded by Revision 016.

Catcutation MDQ00006720080341 Appendix 14 'Table A14.3 Page 11 of 17 - -(RCp Mobr Cmters Quallfed, CCS HX B Reduced Required Flw, and Thrcfring CCS FX A Valve) AtA3: To Gndlent Structurp fior ERCW ,Ctr! Conpomnt thlr Unk Rrq'd ul c8, l,2 LOGA LofB Grr100 6113400 totlln 8Sr RC 1A4 1 86D2 - 88G2 12.0 18.9 S ser 6Sr RC 2A{ 1&2 86D.4 - 88G.4 12.0 12.5 M* 713'RC tAil t BlE2 -67@. 1t.0 16.4 fr ceet 7r3 RC 2Ad 1&2 A7E4 - 67GO 11.0 12.7

rsr 737 RC lA{

1 ts7s2 -67C* 12.0 24.4 0 ros* 737 RC 2A-A 1e2 8754 - 07GO 10.0 11.3 I rgr ACASAfrrC A 0 $4Rl.- 54Ol 1.5 1.7 I rg* AGAS CYlhd A 0 l4R < S{o 2.O 2.9 ) rs* BATP'AFI,I'P RC A.A 0 ilO2-54P.2 q).0 63.9 Uzr CCP RC lAiA I SED1 -.580.2 25.0 30.4 Vnx ccP Rc 2A{ 2 58E.2 -r 58F2 25.0 n.4 I rax ccs rhA{(146) 1 100O..* 19 5,050.0 5,N.0 b.gzx CCS lfl A{ (t'f3} I 103 --r 1O3B 0.0 lsdabd ccs HI B-A (1{6) 2 lG -+ 107 4,0@.0 4.485.5 I rr* CCS l0( E.A (143) 2 106A-' l(FB 0.0 lBolstod CCS'AFWP RC Ad 0 56T0 -,55F ro2.0 128.5 F ee* CRDMC 1A"A I 50H -.50J 124.O 153.8 NRqd cRDMc tc,A I CRDCi - CRDC2 124.O 127.6 NRqd CRDilrc zAnA 2 2;5Sl -r 2.50J 124,O MA NRqd cRDUc 2cd 2 2.GROCi.- 2.CRDC2 124.0 N'A ilRqd CSP RC IAF,A I B$r2 <65N2 28.0 32.1 NRqd 3SP RC 2M 2 65n.6 --o 65}.14 28.0 35.8 fl zax CSS Hx tAnA I 53 < 53A 5,200.0 0.0 NRqd css Flx 2A-A 2 53.2 -. CS2A01 5,200.0 5,374.7 Uo.g6e6 EBR RC Ad 0 578.+ 55H 300.0 3i10.8 b toot EI}G IAI.A 0 tl6El --r 4EF 650.0 799.8 F zen EDG 142{ 0 {8Bi + 48Fl 650.0 798.3 fr zgx EDG 2AI{ o t08Cl + 48P 6!n 0 750.9 0 rer EDG 2A2{ 0 48ii -' 48C3 650.0 764.8 I re* EGTS RCAil 0 ilX2.+ 54YZ! 10.0 18.2 iu* LCC lA.A 1 EOD - 508 306.0 3a9.5 U ssg LCC 1C-A 1 Lcvccl < LO/cc2 306.0 312.6 U zgr Lcc 2Ad 2 2.50D --r 2.50E 3(E.0 ilrA NRS LCC 2C-A 2 2.LCVCCI..+ 2.LCVCC2 3ffi.0 N'A NRqd MCR RC A,A 0 56;9.-. SSD 2&.O 405.9 t egss PC RC 1A'A 1 tt)tE2 < 67N2 15.0 2,.2 S aex PC RC 2A"A 2 87M.6 -- 67M.8 15.0 1E.l 9 ztx R8R RC IA.A 1 5l.lE -' 51.lC 30.0 38.1 7 ztx RBiR RC 2A,,A 2 IRWLZAO4 + lRtlllC2AOS (lRn lrC2Am -+ lRUlE2AO3l 30.0 101.7 Brdn RCP mAC l-ld I 50V - 50S (501.-r 502) 110.0 9{.3 NRqd RCP IJlAC I.}A I RC[3.E.- LCVCDISI (RCP3.l.- Rcfts3.2) i10.0 90.1 NRqd RCP irAc 2-ld 2 2.Wrt --2.508 (2.501..+ 25(E) 110.0 N/A NR@ RCP lulA0 2.IA 2

2. RCP3. 8 -- 2.LCVCCDISI (2.RCP3.I - 2.RCP32) t t0.0 N/A t{RqC Thio Page Addod bY Revision 016.

Catcuhtion MDQO0006Z2OOSO341 Appendix 14.Table A14.3 P4e 12ot'17 - -eCp M;tor CootcrB Qtnllffed, CCS Hi'B Reduccd Required Fhuv, ard Throtting CCS HX A Vah,s) ffiraultccndl.ntotacha Cornporof t nlt tftrr tucd ur c8' U2 LOCA LofB gpl l0O Crro {00 Srrgln RCP RC Dummy NA N'A N'A N'A RHRP RC TA"A I BSIF -,6538 19.0 25.2 0 sor RHRP RC 2A{ 2 86S12 --r 65314 19.0 20.0 Usr SDBR RC A,A 0 55Alt < 55E 560.0 66a.4 ,F r$a SFPP'TBBP RC A"A 0 SrlJ - 54Kl 29.0 374 fl zgr, stP Rc lA.A t 65F2 < 65G2 u2.o 25.2 ilRqd sIP RC 2ANA 2 BSFB + 65GE 2,.O 25,4 il rsx Sfeher lAnA 0 44AO...44AO1 450.0 450.0 Uot Stminer 2A"A 0

EO +44B;o,2 450.0 450.0 h og6 ucc 1A,A I

mo;521 (528 < 52F) 23.0 50.2 Broln ucc 1C{ I Uc1rClC.rO.- Sgy tt Ct ClC.3'- UCVGIC.4) 23.0 E7.7 Erdcn UCC 2A"A 2 2.SlO -2.52L t2.5ZE -+ 2.52F) 23.0 0.0 i{Rqd ucc zc-A 2 2.UCMC1C.10 -' 2.52Y (2.Ucrrct C.3 -+ 2.UC\\IC1 C.4l 23.0 0.0 NRqd Brcke 2-106,4A4 2.glA -+ 2.5083 N'A ilrA N'A Broko 2-1054C{ 2.50A.+ 2.5G5 N/A N'A N'A Broltc l-t06{AnA 50A-+ 508!l N'A N'A N'A Brdo l-1054C{ 50A -+ 5085 N'A N'A N'A' Scrn Ursh P 1A{ 0 AHls -+ liP27 r0.0 12.1 F ztx Scrn Vlrlh P 2A"A 0 APilS -.r APiP 10.0 8.8 V-tz,lr, SAC AftelC A 0 EACAI.+ SACA.3 54.0 0.0 N'A SAC Cylind A 0 SACA2 - $ACA4 N'A N'A N'A SAC Afurc B 0 SACB.r - SACB.22 54.0 0.0 N'A SAC Cyllrd B 0 SACB.2 - SACB.4 N'A N,A N'A BAC AfigC C 0 sAcc.l < sAcc.22 5r0.0 0.0 N'A SAC Olird C 0 SACC.2 --r SACG.4 N'A N'A UA SAC D 0 SACD.2 -- SACC.24 95.3 123.4 flzrx SACAHEffi 50, 5gA tlrA 123.4 N'A SPTY CNT},IT COOLERS 2.LCVCCSUPI < 2.LC1,CCSUF2 N'A il,4 N'A SPLY CNITf,T COOLERS 2.5081 ' 2.5082 N'A N'A N'A SPIY CNTMT COOLERS 5081,5082 N'A s77.5 NIA SPLY CNIMT COOLERS LGVCCSUP1.- LCI/CCSUP2 N'A s00.3 N'A t Grsdor than 3(}15 f,ouu rnargln A Behroen 2096 and 30clt ftor maryin @+ Betreen 1(})6 and z0#of,ouu margin \\ Batuoen o% and 1o% flon maEin I Leea tlran o% fiow mrrgin Notes:

1. Cale 400 conrEen loEs of downdraam dam ald broken oooltlt.

2. l/xcasss consi&r 93% PumPo.

Thie PagP Addd bY Ranision 016.

Calcuhtion MDQ0OO(E72OO8O341 Appendlx l4'Table A1tl.4 (CCS HX B Reducod Requlld Flwv and Throt0ed CCS HX A Vahte) It+f: To ]tvrlnulb Gredbnt Dbch.l3e Structrro fu ERCW pumpc I Cw Gomponont t oli Lht n!{d ul cr8, u2l,ocA toTB 663t100 Gm{00 tugln 6se Rc 1A{ 1 86D2

66G2 12.0 r8.5

&om Ee? RC 2AnA 1&2 66D.4.-'66G.4 12iO. 12.9 Ue* 7r3 RC 1Ae 1 87E2 -.r 67G2 11.0 16.1 ll le* 7rs Rc 2A{ 1&2 WE1-'67G0 I t.0 12.5 E rlx 737 RC lAnA 1 B7S2.- 67G2 12.0 23.8 0 eoPi 73r Rc 2A-A 1&2 t7S4 -' 67Ci6 10.0 11.1 t rr* ACAS AlterC A 0 54Rl -' A4Qt t.5 1,7 N rse6 ACAS Cylhd A 0 S4R -+ S4Q 2.O 2.3 I rsx BATP'AFIA'P RC Ad 0 ilOz--+54P.2 @.0 63.0 Usx ccP Rc tAd 1 58Dl - 580.2 25.O 29.8 I rgi6 ccP Rc 2A4 2 5EE2 -r 5EF2 25.0 29.0 I re* CCS l0( A,,A (146) 1 103D - 19 5,050.0 5,149.0 Ut.e6r CCS Hx A,A (143) 1 103 -+ lO0B 0.0 lsotsted CCS Hx Bd (l/t8) 2 106 -.+ 107 4.0@.0 {.376.4 Uert CCS ]lx E{ (143) 2 1OGA+ 1068 0.0 lsolded CCS'AFWP RC A'A 0 56T5 - 55F 102.0 125.6 F zgx CRDMC tA',A I 50Dl + 30J 124,O 1o'.7 NRqd cRDirc lcd 1 CRDCI '+ CROC2 124.O 118.4 NRqd CRDiTE 2lt,A 2 2.5O{ - 250J 121.0 irrA NRqd cRDmc zc-A 2 2.CRDCi'- 2.CRDCZ 121.0 TUA NRqd CSP RC 1A.A t 850lt2 -+ 6(iltP 2E.0 31.4 ilRqd 3SP RC 2AA 2 85m.6 - 65}*l 28.0 35.3 Fzrix CSS l+( lA"A' t 53 - 58A 5,200.0 0.0 NRqd CSS HI 2A.A 2 5ti.2 - cszA[rl s,AnO.0 5,301.9 Ht.g6* EBR RCA{ o $IB + 55H 3m.0 iJ21.2 Xzn EDG IAT{ 0 {8El + 48F 85().0 7&,s Dztr*; EDG 1A2d 0 48Bl -o4EFl 650.0 7E0.9 Fnr EDG 2AT{ 0 {8Cl - 4EP 650.0 734.3 ) rgx EDG 2A2{ 0 l$/l -tf80g 650.0 718,.2 I rstt EGTS RC A.A 0 5{)e.-r 5lY!l 10.0 18.0 D aon rcc 1A-A 1 Sff) -.50E im.0 290.8 Uax LCC lc.A I LCVCC1 -. LCVCC2 306.0 287.E {}cr rcc2Ad 2 2.50D + 2.50E 306.0 N'A NRqo LCC 2cd 2 2.LCVCCT...2.LO/CC2 36.0 N,A NRqd ITICR RC A.A 0 55C - 55D 240.0 396.8 0 esx FC RC 1&A 1 E7t/t2 -.67N2 15.0 21.7 0lsn PC RC 2A"A 2 87M.6..- 67M.6 15.0 17.8 e rse6 RBIR RC IA-A I 5t.lE + 51.1C 30.0 37.3 F zex RBN RC 2A.A 2 lRtftJC2AO4.- lRWC2A0li (lRl,t C2Am + !RWC2A03) 30.0 1m.E Broken RCP I'iAC 1-1d 1 50V.- 5OS (50t < 502) 110.0 500.0 8rofton RCP MAC t&A I RCPit.E - LCIICDIS1 tRCFtrl

RGPil.2) t 10.0 451.E Brolten RCP [iAC 2-t'A 2

z.fiV -+ 250S e.501 -.2.502) 110.0 N'A NRqd RCP mAC z-il 2 2.RCP3.8 - 2.LCllGCDlSl (2.RCP3.1 - 2.RCF3.2) 110.0 N'A NRqd Page 13 of 17 Thlc Page Mded by Revlsion 016.

Calcxrhtion MDOO(!0O672OO8O341 Appendix 14 -Table A14.4 (CCS FIX B Reduced Requied Flovv and Throttled CCS HX A Valve) Itf"e: To ]ltdnulh Gndcnt Dlrchlrrre Strucfrtro br En@ Compqrnt Unlt Unk mcd ut c8, U2 LOGA LoTB g3p{00 Crtc a00 trrrgln' RCP RC DumnrY NA N'A t{rA N'A RHRP RC lAnA I 65S6 -.65SE r9.0 21.8

Vzgfr, RHRP RC 2&A 2

85S12..+ 6!iS14 t9.o 19.7 !e* SDBR RC A.A 0 55AS -+ 568 560.0 647.4 I rer SFPP/TBBP RC A"A 0 5{J + 5fi1 29.0 346 F zex SIP RC tA.A I 65F2 -o 65G2 z2.o 24.7 NRqd SP RC ^{.A 2 ESF6..* 6SGE u.o 25.1

rlr Sfafu lAnA 0

{4AO..' 44AO1 450.0 ,150.0 Um Smhr 2AA 0 t4BO <4480/2 4s).0 {9r.0 Xot UCC IAA I 520 < 5[!L (saE < 52F) 29.0 61.7 Brolsr UCC lC,A I UC:IJCIC.lQ a SEY rUClrC,C.3 - t lC\\y'Cl C.4) 23.O 84.6 Broken ucc 2A-A 2 eSao < 2.52L t2-52E< 2.52F1 23.0 0.0 NRqd rrcc zcd 2 2.UCVC!C.!0'+ 2.57,^( fil.UCVCl C.3.* 2. UC:\\rCl C.4) z3.o 0.0 NRqd Brolo2-1(F.n.A 2.50A.- 2.5@3 N'A }JA N'A Brdlo 2-1054C,A 2.50A + 2.50Bli N'A N/A N'A Broke l-10544{ 50A - 5083 N'A N,A N'A Brole 1-t054C-A 50A - 5085 N'A llrA N'A Scrn UWh P 1A'A 0 APnS -,0rF27 10.0 12.O fl zot Sar W$ P 2A'A 0 APi!5 -. Al{19 10.0 8.6 &al* SAC ArteC A 0 SACA1 - SACA3 54.0 0.0 N'A SAC Cylind A 0 SACA.Z -- SACA.4 il,4 N'A N'A SAC AfiArC B o SACB.T --r SACB.22 54.0 0.0 N'A &AC Cyllnd B 0 SACB.2 < SAGB.4 N'A N'A N'A SAC AftorC C 0 SACC.T - SACC.22 54.0 0.0 N'A SAC Cytind C 0 SACC.2 - SACC.4 N'A N'A N'A SAC O 0 SACD.2 -. SACC.24 s.3 121.1 F esr SAC A Hoeder 59 r 594 N'A 121.1 N'A SPI.Y CNNiT COOTERS 2.LO/CCS[ Pl.- 2.LC\\TCCSUP2 N/A N'A N/A SPLY CNTMT CooLERS 2.5081 +2.fiB2 N'A N'A N'A SPLY CNTi'IT COOLERS 50Bt -15082 N'A 940.5 N'A sPrY crrirn cooLERs LCVCCSUPI - LCIrcCSUF2 lUA E58.0 N'A t Grcabr than 30% flow maryin A Bemeen zDfosrld 30% frow margln E@ Bctneen lWoand 20% llow margin S Bstmen o% and l$lt flow matgin L.ear than o% tlow margin Notes:

1. Case 400 considers bss d doilnefraam dam and broken ooolcru.

2. Afl ca!e! conCder 93% rumpa.

Page 14 of 17 Thir Pagc Addod by Revlsion 01e.

Catcutation MOQO@6720080341 Appendix 14 -Table A14.5 Page 15 of 17 (RCP Mobr Coolers Qualified, Q;re Brcken Cooler, and Throttling CCS HX A VaMe) A14,6: To ltydnullc Grrdlcnt Dbch.tgc SUucfrtru fur ERCW pumpo I Cw Gompon ril tht Unh tuqt ur e8, U2 LOCA tTB Cere{00 Goco 100 trrg[n 8Sr RC lA{ I BGD2 -' 66Cf 120 19.0 $ sar 8ffi RC 2A.A 'l &2 EGD.4 + 66G.4 12;O n.a Usr 713 RC tAA I {lE2 -r 67G2 11.0 16.5 D so* 71E RC zqnA 1&2 E7E4 - 67GB 1 1.0 n.a D rer 737 RC 1A'A I BTSe -67@ 12.O 24,4 frtrar 737 RC 2AA 1&2 B7S4 - 67Go 10.0 11.4 Ou* AGAS Aftor0 A 0 54Rl < 5401 1.5 1.7

rgr ACAS Cylitrd A o

$4R.* ${Q 2.0 2.s ) rsx BATP'AFWP RC A,,A 0 ilO2-5ff.2 60.0 u.i Yzr CCP RC IA"A 1 58D1 -- 58D.2 25,O 30.5 7ax ccP Rc 2A{ 2 58E.2 -,58F2 25.0 29.6

rax DGS Hx A"A (l'f$)

I lG3D..o 19 5,050.0 5,132.0 Ur.ez* DCS llx A{ (r} I 108

t0gB 0.0 lloleted CCS )0( 8d (146) 2 106 -+ 107 4,4q).0 4,471.8 Hr.oser ccs nx B{ (14i1) 2 1OBA - 1068 0.0 leolatetl CCS'AFWP RC A,A 0

56'15 - 55F t@.0 128.8 ifr zsx cRDflrc 1&A t 50H + 5(U 124.O 154.1 NRqd cRD0nc lc-A I CRDCI

CRDC2 121.0 127.s NRqd CRDIJIC ?A.A 2

2.50H - 2.5(U 124.O N'A NRqd cRoxlc 2c4 2 2.CRDG1-2.CRDC2 124.O 1{rA NRqd CSP RC 14il I E5ir2 -,65M 28.0 e2 NRqd CSP RC 2A'A 2 85M,6 +65l*tl 28.0 36.9 Dzr,x CSS Hx 1AA 1 lXl - 53A 5,200.0 0.0 NRqd CSS HX,A{ 2 58.2 -r CS2A01 5,2qr.0 5,402.9 bg.soo6 EBR RC ArA 0 57B + 56tH 3(xr0 349.3 H ton EDG IA1.A 0 48El - 48F 650.0 801.6 F zgx EDG IA2.A 0 {881 -.48F1 650.0 E00.0 Vxtx EDG 241.4 0 fECl -r 48P 650.0 t52.6

rer EDG 2A2{

0 48lll.- 48Cg 650.0 766.5 i tse6 EGTS RC A"A 0 ilX2--r 6t0E r0.0 18.3 S aget Lcc tAd 1 50D.* 50E 3(E.0 3302 'U ax rcc lc{ I LCVCCT..+ LCVCC2 306.0 313.3 Uzr tCC 2A.A 2 2.50D.+ 2.50E 306.0 ltA NRqd rcc 2c-A 2 2.LCvCCl

2.LGVCC2 306.0 N'A NRqd MCR RC A.A 0

55C--r 55t) zfi.O 406.8 fr zo* FC RC 1A.A 1 6'.11fr2-67M 15.0 a2.3 S lget PC RC2A{ 2 67M.6 -r 67M.8 15.0 18.2 7 ztx RBIR RC 1A{ I 51.1E -* 51.lC 30.0 38.2 7 ztx RBIR RC 2A"A 2 lRWc2A04 - 1RWC2A05 fl RlrllCzAm + lRlItlCllABl 30.0 102.0 Br*sn RCP MAC 1.I{ 1 50V + 5OS f50l - 502) 110.0 94.5 NRqd RCP rmc 1-&A I RCP3.8 -r LG1/CDNi1 (RCF3.1 + RCP3.2) 110.0 90.3 t{Rqd RCP MAC 2.IA 2 2.50V < 2.50S (2-5Ol.* 2.fl)Z) 110.0 t{rA NRqd RCP rno 2d 2 2.RCP3.8 -* 2. LC1/CCDlSi l2.RCP3.1 -+ 2.RCP3.2l 110.0 ]UA NRqd This Pag Addd by Retrieion 018.

Calculaton MDQ00006720080341 Appendix 14 -Table A14.5 Pry 16 of 17 (RCP Mdor Coohrs Qualilied, Onq Broken Cooler, and Throffiing CCS HX A Vaha) Al{.6: To }tulrnih Gredbnt Dlsch!r!!! Sbuctrlt llor ERCW Dunro! I Gyr Compomnt thta thr Rrq'd ul c8, u2 LOCA LOTB C.s {00 Crs tl00 tarEln RCP RC &.unmy NA N'A UA N'A RHRP RC 1A,A I BSSO

6!iS8 r9.0 fr.s C aEx RHRP RC 2A"A 2

85St2 r 65514 19.0 n.1 Ver sosR RC A{ 0 55A3 < 5ff 560.0 860.8 f rgt SFPPTTBBP RC A"A 0 ItlJ.- 54Ki 29.0 37.5 Fzgff' stP Rc tA{ 1 65F2 - 6!i(32 n.o 25.3 NRqd SIP RC 2A"A 2 B5F6+ 66@ n.0 25.5 $ ro* SUainsr 1A"A 0 44AO -,44AO1 450.0 450.0 Uo* Sblincr 2Ad 0 {4BO +4480i2 450.0 450.0 Uo* ucb re,n 1 50O + 52L t52E + 52F) 23.0 26.9 NRqd JCC lC,A I t C\\rClC.10 - 52Y ruC\\rC1C.3 + UC\\lCiC.4) 23.0 rc.8 ilRqd ucc zr'A 2 2.5aO -.2.5i1L t2.il8 <2.52F1 23.0 0.0 NRqd ucc 2c-A 2 2.UCVC1C.10 -.2.51( f2.UCvCl C.3 - 2"UCVGi C.4) B.O 0.0 NRqd Brol 2-lGitl/td 2.50A -r 2.5083 MA N'A N'A Brdte2-16'fC{ 2.50A < 2.5085 MA ire N'A Brolre l-lq5{A{ 50A< 50B:t N'A N'A N'A Broko 1-105tlC-A 50A - 5085 N'A N'A N'A Bcrn Wlh P lA'A 0 rP25 + 0iF27 10.0 122 Fnx Scnr W3h P 2Ae 0 0ffi25 +AHl9 10.0 8.8

-tzx SAC AfidC A 0

SACAI -* SACAS 54.0 0.0 N'A SAC Cylittd A 0 8ACA2.+ SACA4 N'A N'A N'A SAC AfrgrC B 0 sAcB.l rsAcB.zt 54.0 0.o N'A SAC Cylltd B 0 SACB.2 - SACB.4 N'A N'A N'A SAC AlletC C o SACC.1 - SACC.22 54.0 0.0 N'A BAC Cy'ind C 0 SACC.2 - SACC.4 N'A N'A N'A SAC D 0 SACD.2 - SACC.24 s.3 123^7

Fzar, SAC A Hea&r 59,5gA N'A 123.7 N'A SPIY CNIII T COOLERS 2.LC\\ICCSUP1 -. 2.LCVCCSUP2 N'A N'A N'A SPLY CNTMT COOLERS 2.5(81 )2.fiW2 N'A N'A N'A SPLY CilTltlT COOLERS SoBl,5082 N'A 578.8 N/A SPLY CNTilT COOTERS LG\\TCCSUPI - LCVCCSUP2 N'A 5:i1.5 N/A t

Greebr lhan 30% flouv maryin A Betrrsen 2fioand 30% lbrv margin Etr+ Bshreon 1096 end za%fuuu maryin \\ Betreen 016 and 1(I)5 rlor mrrgin I Lesg than 0ct6 frw margin Itlotes: L Carc 100 onddert loos d downctnam dam and brcken oodrs.

2. Al ca3.. oomadr 9396 purnps.

Thig Page Mded by Reviabn 016.

Calqrlation MDQ0000672008034 1 Appendlx 14 Page 17 of 17 GtiERAtOi.tulLolxG sr^Itor trlfiE onilrtt rnrlrll ooqmmtlrtvttl Imtotmrm lLoil t{t'Ft}t --l-;F;^R-rucrEAR Pt ^i{T I rgxrss$r YAuEr ArrTrotttr I This Page Added by Revision 016.

ENCLOSURE2 ERCW Flow Model Mode 4 - RHR Cooling

Galculation Sheet - I Documenft mDCp0006720080341 Rev.: 0{8 Plant WBN I Unlts 1,2 Page: I OF t5 Sublcct Errcndal R.u, Coollnq Wer {ERC:WI Ev.bfli Prcruto Dtop Gdcule0on Appendlx 17 - ERCW Syrbm Gorfiguntlon fior Hlgh Cotr Dccey H..t.nd LOCA

1.0 Rrrpole

The purpose of thls Appendix is to eraluate 0re operatona!,node whn a unlt has hlgh oole decay heat and [p otpr unit elgeriences a Lose d Cooling Aoddcnt (LOCA) during a Loos of Oftlte Powcr (LOOP) and loos of Tnain A (LoTA) or Loec dTrain B (LoTB) whidr addrees GDC 5 requiromentB. The hlgh core decay heat impactc thc nquircmenh of the Gornporcnt Goollng S:/stern (CCS) heat exdrangerB. The aaaluation oonsidcrs limlting condltons rvitt degradod pumpo, broken oolers (ae applicable), disdrarye thrcugh tle Hydnulic Grudlent Oadtarge Struclure, and loos of downstueam dam LODD (asapplbable). The fullorrving cases lncorporab the fiov balanco test rpeults and the assodated files are gtorcd at Fllelteeper. Caso 1300: Unit t.Hot Shutdffii Modified (HIgh Core Docay Heat), Unit 2 LOCA-RECIRC (LOOP and [oTB) Caso 14fi): Unlt 1.t-lot Shutdown Modified (Hlgh Corc Decay Heat), Unit 2 LOCA-RECIRC (LOOP and LoTA) Casc 15fi): Unlt 1 LOCA-RECIRC. Unit2.Hot Shutdorn Modified (Hlgh Corc Decry lleat) (LOOP and toTB) Case 1600: Unit 1 LOCA-RECIRC, Unlt 2.Hot ShuUo{n Modifd (H[h Core Decay [bat) (LOOP and LoTA) The hydnulic andyt* preceriled in ttris Appendix wele pErfurmed utilizing MULTIFLOW Verslon 1.21. MULTIFLOA, h a WA QA computer prcgram 0rat hae been verlfred and validabd ln theWA OA Roootd Sdunre Verificatlon and Valldaton Repoil. MULTlFLOWVereion 121 ls run otrWndows NTVerslon 5.1 SeM6 Pack3. 2,0 tc0rodologylApproech: The goal is b ensur all onponents serued by ERCW recelve thelr design baeis f,orv duting a[ mods of operaffm. The llmitng modes of ERCW operation seleciEd br the frow bahnce are: Unit I ffor eech train) Unit 2llor each tnln) LOCA-Recirculation Hot Shutdoum Modified HSrn) Hot Shutdown Modified fiSm) LOCA-Redrculation The modes oJ ERCW openatirn are described in Refurenco 1. Hot Shutdown Modlfiod ia the same as Hot Shtidown Caee A ln Sedlon 6.5 of Reftrcnce '1. Hot Shutdown ilodifred is the sanre as Hot Shutdonn exced tui$ hc addiffott of Spent Fual Pool cooling. The general appoach ln deneloplng fiors durlng accldent and degraded condltons b outlned belom

1.

This Apperdix uses the MULTIFLOW models esbblbhed inAppendix 1,[ sfiidr @ntalns the llmlting cond]Uone ln Item 2 below. Appendlx 14 oonskbrs the operational mode combinatinn of a unil h Cold ShttdoYn and the other ln LOCA-Re<irqrlation. Rehrcncc I shflvs the rcquircd components rMced by ERCW betuueen Cold Shutdown and.Hot Shurtdwn difrrs by Hot Shutdown additmatly rcqddng the CRDM coolers. Thls dtangec the name for the MUTIFLOW model hrt doee nqt drange wtrldr cqnponentE reoiw ERCW. Cold Shutdown case providee coolflng to all containment cornponents due b the inability to teadlly lsolate lhe containment componentB and thu8, tre CRDM coolsrs are reeMng flowwtrldr noui beoomee requircd if he CRDM coolers ar not broken.

2.

These casea ryere executed under limililB @ndfions, induding:

a.

ERCW pumpe (thrce (3) norst pumps in eadr fain) perbrming at 93% of their facfiory acp0anca tet results (appfcable to all cases);

b.

A lake level consistent wlth a 'loes of dqvnstueam dam' errcnt (applicaUe b cases 1 3(X), I 4(X), 1 5(X), and 16fi)); and,

c.

Non-seisr{cally qualllled oomponentB hlled and eplllng ERCW rvater, e.9., Unit 2 lnstumsnt Room Chiller, Unit't E 2 Reactor Bdlding Upper Compailment Coolera, Unlt 2 CRDM Coolerc, Unlt 1 RCP ilotor Alr Coolers. r" Thls Page Replaced by Revision 019

Calculation M DQ0000672008034 1 Appendix 17 -Table 417.2 Page 11 of 1 TeUo A17.22 Hloh Go,rr llecry Helt Lo.d, Thtoe ERCW p'umpc, CG lfr Adluclrd At7.2: Hhh Colp Docat ]fe.t lotd I Thror ERCW pumpo, CC8 HX Componcrtt thlr Lhlr nct'd Ul lltol, u2 LOC/I 1.oTA Gultl@ C.!. tt00 tlOln ul LocA, Ul H8nr 1,TA Crr lt00 Grr lt00 margln Gmrporurt thli Unt Roq'd ul lltm l uz LocA lotB Crec ltl00 6119 ttl0o tergln UI LOGA' U2ll8rr I,TB Grro tt00 cers l0O mrrgh EgT RC 1B.B I PENlB1.7 + PENRMDIS.T 12.O 31.7 fr tem 30.3 i tsor 892 RC lA,A 1 8602 +66Giil 12.0 20.9 S ztg6 17.4 45!6 B9[r R{c 2&B 1&2 PENilBl D.2 -' AC2BDIS.'l 3 t2.o 19.2 S eog6 2,3 Omx 09e RC 2A-A 1&2 86D.4 -- 68G.4 12.O 12.7 V ers 17.2 43j6 713 Rc 18 1 PEN1B2.7 - PENRMOIS.S I t.o an.o il toooe 21.2 Og3* 719 Rc tA-A I BlEz-.67@ 11.0 18.2 S es* 16.'l {6% 713, Rc 28 1&2 2BlOg -28110 fi.0 17.5 D ser 20.5 S aox 713' RC 2A,A 1&2 87E4-67Gi6 11.O 12.s N ttx 18.2 65* 737 RC l&B I PENI Bil.7 -- PENRI'/DIS.S 12-O 26.6 t tzzx 25.1 i tcn 737'RC lA{ I BTSrl -+67G2 t2.o 27.O Stzsx 29.1 st)% 737'RC 28 1&2 2Bt tg + 28110 12.O 13.3

rrx 15.4 il zsth 73r Rc 2A{

1&2 B7S4 < 67G6 1o.0 11.5 O rs* 13.6 3696 ACAS AltsrC B 0 ACACBBDIS.S - ACACBBDIS.B 2.O 2.2 I ror 2.2

roq6 ACAS AfirC A o

54Rl + 54(ll 1.5 1.9 Fnx 1.E n% ACAS C$hd B o AGACBBDIS.2 + ACACBBDIS. 3 1.5 1.8 F zox 2.2 fr rzr ACAS Cyllnd A 0 549 - 5iO 2.O 2.6 i soe6 2.3 15% BATP'AFWP RC B.B o BA2BDlS.4 -. AG2B[ lS.4 60.o to.2 b ttx 8:t.4 i gee6 BATP'AFII'UP RC A"A 0 ilo2 < 14P.2 60.o 6a.E ba* E0.1 34% CCP RC 1B.B I CCPi B.T '-. CCP'l'B.9 25.0 p,.2 F zg* 30.8 fl ttx CCP RC lA"A 1 58Dt < 58D.2 25.0 3:1.7 0 go* 33.1 3gt6 CCP RC 2B.B 2 CCPRCT -. CGPRCS 25.O 31.3 8 zsx 36.9 0 ea* CCP RC 24,.,4 2 58E.2 -,58F2 %.o 29.9 lmx 34.9 40% CCS rlx C (r52) 0 18+19 9,200.0 6,m4.0 Uz.sat 5,&18.6 Dzpx CCS l'lxA"A(146) I lGlD.+ 19 7100 HSm 4mo LocA 8.(x18.1 I tse6 5.7(B.O 43% CCS Flx C (t.04) o 1098 + l09C 3,4(n.0 6,qro.7 ccs lu A4 (14i1) 1 100 --r 1038 0.0 o.0 CCS Hx A-A (148) 1 10:lD - 19 1.370.0 0.0 lgo0stcd o.o holded ccs HI Bd (146) 2 l(F < tO7 7100 HSm 40m LocA 3,9&l.E O tas 4.357.8 E9t CCS l'lx AA (143) 1 1CE).-r tGB 1.370.0 ts 016 1.370.0 H$6 CCS )0( B"A (143) 2 lGAa 168 sfir0 3,Xn.7 CCS'AFVUP RC B-B o CCSAFWI 8.16 -- CCSAFW1 8.17 rm.0 124.O frnx 118.5 ) rex CCS'AFWP RC AFA o 56T5 - 55F 102.0 1A..6 I m*. 138.5 sr CRDMC 1B.B I 10Hl < 1(N1 124.O 131.9 V6gt N'A NRqd CRDIIC IA"A 1 il)H.-o 50J 124.O 159.1 Fm N'A NRqd CRMrc lt}B I CRDDT + CRD[XI 124.O 177.1 Slgx N'A NRqd cRDrnc lc"A I CRDCI -. CRDC2 124.O t3il.E Hax ttlrA ilR@ BRDirc 28 2 2.1OHl -* 2.1OJ1 121.O N'A NRqd 175.8 Broken CRDiIC 2A,A 2 Z50H - 2.5O1 124.O N'A NRqd 169.2 Broken DRDnic 2t) 2 2.GRDDI'* 2.CRDDa 124.O N'A NRqd 179.1 Brcken CRDl,lC 2C.A 2 2.CRDCi...r 2.CRDC2 121.O N'A NRd 147.1 Broken CSP RC 18 t BOF9 -+ 6EF11 28.0 31.3 NRqd 52.8 S egeo CSP RC IA"A I B5lr,l2 _,66N2 28.0 35.5 NRqd 3e.6 41.96 CSP RC 2B.B 2 CSPRC9 - CSPRCII 2&0 30.1 Son 45.8 NRqd CSP RC zqnA 2 65M.6 - 65}$4 28.0 36.3 F so* 34.9 NRqd c88 rfi 18 1 13.1 + 28.1 5.200.0 0.0 ilRqd 7.0{6.3 irt DSS tlx 1A4 I 53 -r 50A 4200.0 0.0 NRqd 6,28.7.e M CSS r0( 28 2 CS2Boi + CS2B03 5,200.0 5,365.4 Ug.rB* 0.0 NRqd BSS tS( 2A-A 2 53.2 -. CS2AOI 5.200.0 5,1V8.2 !sn 0.0 NR@ EER RC &B o 578.1 -- 57C.1. 3U).0 357.3

ree6 3,1.7 *r*

EBR RC A.A o 57B + 55H 3(xr.o 383.2 F zlx 3{1.4 1496 EDG TBT 0 DGIBB.4 -r DG1BB.6 6m.0 776.0

rgn 792.7 Fzu,x EtlG lAld o

lSEt.- 4EF 650.0 887.9 t sz* EiB.O n% EDG IS!-B o DGiB8.2 -. DG1B8.S 680.0 795.3 8w Et2.O F zs* EDG IA2"A o lEBl -r 48Fl 6tr1.o 884.1 O g816 637.0 M EDG 281.8 0 DGaBB.4 - DG2BB.6

650I, 79t.6 fizrx m8.8 F ztx EDG 2A1,A 0

fBCl - 48P 650.0 anil.9 7zgx 7q2.5 u% EDG 282 0 DGABB.2 - DG2BB.5 650.O 792.6 Fm 838.8 Dzpx EOG 2A2.,A 0 480t1-+ 48C3 660.0 {t.o D sot6 q)5.4 249,, EGTS RC B-B 0 EGT:IED3S.4 + EGTZBDIS.S r0.0 13.6 h sor6 16.0 $ ott EGTS RC A"A 0 ilx12< S{W 10.0 r8.5 t aot 21.2 112?t, LCC TB 1 lODl - 10El 3(E.O 30i1.4 & -1e6 N'A NRqd tOC 1A'A t 50D.+ $Qf 306.0 3:t8.9 I rr* N'A NRqd LCC 1B,B I LC\\rCDl

LO/GD2 3[E.O 311.9 b%

N'A NRqd Lcc tcd t LCVCCI.+ LC\\lCGZ 306.0 3f,r5.2 Ue* N'A NRqd Thle Pagp Rephced by Retnsbn 019-

Calcu lation MDQ00006720080 U1 Appendix 17 -Table A17.2 Page 12 ol 1t TaDle Al7.* Hlgh Gotl Docry Heat Lord I Thrce ERCU, nrmsr, GCS HX Adltl3ted fiOn A17.2: Hhh Corr Docstr He.t Lord I Thruc ERCW pumpo, CCS ]lX Golnpm.nl Unlt Lhr Rrqu Ul ll8m, U2 LOGA LoTA Gr.. lt00 Crr t!00 Irrgln UI LOCA' Ul Htm LOTA Gm lt00 Gmo lt00 taryln Cocrponcnt U!ili Unk R.{d Ut llttn, U2 LOGA LOTB Croo l{0O @re t{OO trrEEn UI LOCA' lJzH3ttt LoTB Ger lC00 Grto ltd ]lrrgftr LCC 28 2 2.10D1 - 2.10E1 306.0 N'A NRqd 356.2 I rex LCC 2A.A 2 2.500 + 2.50E 306.0 N'A NBqd w.7 13j6 LCC 2D 2 2.LG\\/CDl - 2.LCVCD2 306.0 itA NRqd 364.8

rg06 LCC 2GA 2

2.LCVCCI -* 2.LCVCC2 306.0 N'A NRqd 3:18.0 1ffi MCR RC B 0 l&8 + 15.t0 240.0 33E.5 t ttx szs.2 S sz* MCR RC A"A o 55G -r 55D 21p..O 448.8 t ano n1.1 '17% PC RC 18 I PCCIB.T -. PCC1B.9 15.0 33.1 h tzt* 340 F ttg* PC RC IA"A I g7tdtr - 67N2 r5.o 24.6 Sem 21.4 4396 PC RC 2W 2 7n124 -28l25 15.0 16.6 D rr* t9-4 Fsx PC RC 2A.A 2 E7tl.8 - 67M.8 15.0 18.4 fr zgx 21.5 4396 REIR RC1B 1 lRlB.tO -r 11.lC 30.0 u.4 f rsx 42.2' t ltx RBIR RC f A,A I 51.lE + 51.iC 3().0 42.2 S lt* 4.1 3f% RBIR RC 2&8 2 RW@B(X -. tlC fiR$,C2ff!2 -* lRn UC2B03) 30.0 109.0 Brdcen 107.6 Brdcn RBIR RC 2A.A 2 lRt \\rCZlO4 - IRlltfC2AOS nR[imino2..- lR/tlC2A03) 30.0 104.9 'Broftcn 119.9 Broken RCP rfiAC,-2. 1 lOIl + lOSl mol < tozt) I to.o 6il).8 Brdren N'A NRqd RCP tiAc l-l.A I 50V..r 5OS t50t < 502) 1to.o 56r.8 Broken o.o NR@ RCP frAC l.{-8 1 RCP4.E + LG\\tCDDlSi tRcP4.l < RcP4.2) 110.0 489.0 Broken N'A NRqd RCP tlAC l-$A 1 RCP3.8 -r LCVCDIS1 (RCPtl.l -.r RCP3.2) I r0.0 508.2 Broken N/A NRqo RCP MAC 2.2-B 2 2jgV1-2.l0St (zlol - 2.1@-11 110.0 N'A NRqd 101.3 NRqd RCP mAC 2-ld 2 2.50V -. 2.5(Nl (2.s0l -r 2.502) 110.0 itA NRqd 135.3 NRqd RCP MAC 24 2 2.RCP4.8 --r 2.LCVCDDISI e.RCP4.l.- 2.RCP4.2) 110.0 N'A NRqd 1(x.8 ilRqd RCP MAC 2AA 2 2.RCP3.E - 2.LCVCCDISI E.RCP3.1.- 2.RCP3.2) 110.0 N'A NRqd 126.3 NRqd RCP RC 1GB 1 RCP1C.I3 - 60G!8 12.O 13.3 NRqd 12.9 U sr6 RCP RC Dummy NA N'A N'A N'A N'A N'A RHRP RC 18 I BOGf 6.-.66G17 r9.o 3:1.1 S zlx 31.5 C es6 RHRP RC lAd I 85S6 -- 65$8 19.0 27.9 S cns 21.6 2g9*, RHRP RC zB.B 2 RHRPRC9 - RHRPRC9.1 19-O 20.5 VBr 26.5 $ ese6 RIIRP RC 2A"A 2 85S12 + 65S14 19.0 20.3 Uz* 25.6 35% SDBR RC B.B o SDBRB2 -27 560.0 623.9 0 t't* 728.5 O eot SDBR RC A,.A 0 55A3 < SCiE 560.0 73a.3 F srx 680.9 am SFPP'TBBP RC &B 0 SFPTBBT < SFPTBB9 29.0 34.9 7m 33.4 f rsr SFPP'TBBP RC A"A 0 5dJ -.54K1 29..o 41.4 Clsx 38.5 3it!6 SIP RC I&B 1 SlSl B.9 -' 68E10 z2.o 24.8 NRqd 42.4 fr sgb SIP RC 1A-A 1 BSF2 -+ 65G2 aL,o 27.9 NRqd 30.9 4096 SIP RC 28 2 SISPRCS -. SISPRC9 2,.O n.7 Vzrix 2,.5 NRqd stP RC 2A,A 2 BSFS - 65G18 a2.o 25.8

ttx 27.7 NRqd Shalner 18 o

48O -- 4801 4!n.0 4!n.o U oeo 450.0 k 016 Strainer 1tu4 0 44 0 < ((lQ1 4tio.0 450.0 V oq6 450.0 096 Slra0ner 284 0 4AO...4A'01 450.0 450.O U org 450.0 Ftn6 Stralner 2A-A o f4BO - 41iAO2 450.0 450.O Hor 450.0 0?6 UCC 18 1 1201 - 12L1 112E1+ 12Fl) 23.0 50.3 Eroln 0.0 NRqd ucc lAd I 52O + 52L t52E.+ 52Fl 23.O 50.4 Brclren 0.0 NRqd ucc rD 1 UC\\rC1D.lO.+ 1All ruClrCl D.3 --r UC\\lCl D.4l 23.O 49.0 Broksr o.o ilRqd ucc lcd 1 UClrClC.lO "+ Sff tUC:lrCl C.3 + tlCVCl C.4) 8.0 101.0 Broken 0.0 NRqd t cc 2B-B 2 2.1N1 +2.12L1 IZ12E1.,* 2.12F11 23.0 0.o NRqd 59.0 Brdcen UCC 2A.A 2 2.520 -2.5flL 12,flE+2.52F1 23.0 0.0 NRqC 64.5 Brdccn UCC 2D 2 2.t CVC!D.1O.-r 21!ti (zuorcl D.3 - 2.UCVCl O.4) 23.O 0.0 NRqd 53.5 Erolten ucc 2c"A 2 z.UCVClC.lO + 2.5?( (2.UG1/CI C.3'- 2. UC\\rC1C.4) 23.O oo NRqd E5.9 Broken Bruke 1-10548 lOAl -* 10Bi N'A N'A N'A 't{rA N'A Brdto 2-l054AnA 2.50A.- 2.5083 N'A N'A N'A N'A N'A Bmke 1-1054D lOAl -' 1OB2 N'A N'A N'A lrlrA tarA Bmfte z-lOEi4CLA 2.5OA --r 2.5085 N'A N'A N'A N'A N'A Broke 2-1648 2-t0Al - 2.t(El t{rA N'A N'A itA N'A &ofte l-torSittAnA 50A - 5@3 N'A N'A 1{rA N'A N'A Brdte 2-104lD 2.10A1.-c210Ei2 N'A 1{A N'A ]IUA UA Brolte l-t0A]CrA 80A.- 5085 N'A N'A N'A N'A N'A Scrn Wgh P 28 o BPtlo < BP32 10.o 10.7

Htx, 10.0 L o!.

Scrn Wsh P lAnA 0 AP25 -0ffi7 r0.0 13.5 C go* 13.6 36% Scrn Weh P 1BA o BP:IO< BPlrl 10.o 10.4 H 4vo 9.E 9 -2x ScrnVltrh P2I'o. o AP25 -.AP29 r0.0 9.8 t*,x 9.8 -29[, sAc Arlg'c A 0 SACA1 < SACA3 sr.0 o.0 N'A 0.0 N'A SAC AfierC A 0 SACA.I + SACA.3 54.0 0.0 N'A 0.0 N'A . Thig Page Repfacetl by Revialon O19-

Calculation M DQ0000672008034 1 Appendix 17 -Table A17.2 Page 13 of 1 Teblr A17.2: Hhh Coru Dccry lfeat Loed I Thme ERCW pumps, CcS HI A{iulbd fetb N?.9, Hbh Cort Docrr l{.il lo.d t Thne ERCW Pumpt, CCS }fr Goeipoltutl thn UnT nfd lX Hgm, lr2LocA lrIA Clrl!00 Crr lt00 ilrOln ur LocA' Ul lltor LoIA CrlclS0 C.!o lt00 trda Coopomnt Unll Lt* ncqt ut Htm, U2 LOCA brB Croc la00 Cu ta00 tlrrgln ut 1g6nl U2ll8llr lrlB crr lt00 CrD ta0l Xlltln SAC Cylird A o SACA2 - SACA4 N'A N'A 1{rA N'A N'A SAC Cylind A 0 SATCA2 -r SAICA4 N'A MA N'A il,A N'A SAC AfiolC B o SACB.I - 8ACB.22 54.0 0.0 N'A 0.0 N'A SAC Afu'C B o SACB.T + SACB.22 54.0 o.o N'A 0.0 N'A SAC Cylind B o SAC8.2... SACB.4 N'A N'A MA MA MA SAC Cylind B 0 SACB.2 - SACB.4 N'A N'A N'A N'A N/A SAC AfterC C 0 SACG.I.-r SACC.22 54.0 0.0 N'A o.o N/A SAC AfiErC C 0 SACC.i -- SACC.22 54.0 0.0 N'A 0.0 N'A SAC Cyllnd C 0 SACC2 + $ACC.4 N'A N/A N'A lrlrA il,4 SAC Cyllrd C 0 SACC.2 -+ SIXGG.4 N'A N'A N'A N'A N'A sAC D 0 SACD.2 - SAGC.24 96.3 134.5 h cot fia.7 t ga* SAC D o SACO.2 -. SAGC.24 s.3 133.7 0 seet 126.1 31!6 SAC B Hoadr 88irl + 68t$2 N'A 134.5 N'A ,2a.7 N'A SArC A Headar 89 + ssA N'A 133.7 N'A 126.1 MA SPLY ClrlTilT C(XILERS 2.1081.1 -) 2.1081.2 MA N'A MA 633.1 N'A SPLY CNTMT COOLERS

2. LWCCSUP1 - 2.LCI/CCSUP2 N'A N'A N'A 611.4 N'A SPLY CNTUT COOLERT}

2. LC1/CDSUPI - 2. LC.\\/CDSUP!

N'A N'A il,4 ila.7 N'A sPr-Y cNTilr coo.ERS 2.5081,2.5082 N'A N'A N'A w.2 N'A SPTY CNTiIT COOLERS 108r.1 ) 1081.2 N'A 1.115.1 N'A N'A N'A SPLY CNTMT COOLERS 50Bl + 5082 N'A 1,05e.7 IrlrA N'A N'A SPLY Cl,lIllT COOLERS LCVCDSUP1 - LCVCDSI P2 MA 977.9 N'A MA l.lrA SPLY CT.ITMT COOLERS LCVCCSUPI.- LCI/CCSUP2 N'A $7.2 N'A N'A N/A t Graaterthen 30% lbrr rnargin A Betrrlaen z}Yoend 30% f,orr margin E) Be$fleen l0% and 2$!/o0ow rnargln \\ Betnueen O16 ard 1096 f,ou margin t Leeg than o% fiorn margFn Notes:

1. Caree 1300, 1400, i 500, 1600 congider loee d dqrnslrGam dam and broken coobrt.

2. All casos conrider 93% PumF.

Thlr Pago Replaced by Revicion 019.

ENCLOSURE2 CCS FIow Model Mode 4 - RHR Cooling

Table A11.3: 90% Pumpe I Ttaln lnB Component Train Link Req'd Gare 8G - Unit { HSmtllnlt 2 LOCA, C,28, Tnaln B Flow (gpm) Gace 8C - Traln B, C, 28, targln Case 8D - Unlt I Hsrnrunft 2 LOCA, 1&B, 28, Trafn B FIow (gpm) Caao 8D - Traln B, 1B8, 2B.,, tlargln Cent Chr Purnp 1B-B B 189

190 28.0

.2 fl 29o/o 35.6 dA 27o/o CCP 1B-B Lube Cooler B

2718 - 289 20.0 23.8 EP 19o/o 23.6 + 18To CCP 1B-B Gear Gooler B 272 - 273 8.0 12.4 t 55% 12.O fiVo Cent Chr Pump 2B-B B U2189 -- U2190 2g.o 35.0 A{ 25o/o 34.5 8 23o/o CCP 2&B Lube Cooler B U2271B--* U2269 20.0 24.1 21o/o 23.9 + 2Wo CCP 2B-B Gear Cooler B U2272-U273 8.0 10.9 tl fiolo 10.6 33% CS Pump Oil HX 1&B B 203 +244 2.O 7.3 fr$Yo 7.O S ?fio/o CS Pumo Oil HX 2B-B B U?2OS-U220r 2.0 7.4 27OVo 7.2 s z@oh Radiation i/bnitor 0-RE-90-123 B 180C--+ 180D 21OB + 210A 6.0 6.0 Bvh 6.0 Iu ff/o RHR HX 1BB B 206 - 2Ol 5,(X)0.0 5361.4 g 7o/o 5333.4 B ro/o RHR HX 2B-B B U2f:W+U22OT 5,(N)0.0 5680.1 + 14o/o 5653.2 +B% RHR Pmp Seal Water 1B-B B 199 + 200 10.0 14.5 fr 45o/o 14.4 f 44o/o RHR Pmp Sea! Water 2&B B U2199 -* U22OO 10.0 13.8 S 3i}o/o 13.6 S 30% SI Pump 1B-B B 1% -'195 15.0 21.8 t 45Yo 21.O tM SI Pump 2B-B B U2194 -+ U2195 15.0 20.1 S ilo/o 19.4 A z*/o Ca lcu latio n M DQ00W7 O2OO9O2O0 Appendix 11 This page added by revision 009. Page 7 of7

ENCLOSURE2 GCS Heat Exchanger Data Sheet

0nc ['f: I I Ij(ltl h,l/rf'JC t: O f UIJ ll lffiiinot:r, ----J r;'{TTErlIii c; r, ri,', lg, r !l_] r(t.AciIttrtTTl "Vtft/.1-L CrJtF JLtrr,{,'5i}'t V tCE I OTU r llll'l,t,t'tr rT'? l DESlill r;ollt). F -CI;]orG.r-.i:l -Tr:5n:ol-0Tlr1n2; 207/l;11 c0ltDlTl0il-P,n5 lc TmloE 2a6 / tt9 coND I i'I -tj-:,] x i ru ?.2 l / c,i: otr A Tr-L.llqt':i m it SIIELL SIDC I L'I'E SIt)L SIII LL SIDI: .I'UL{tJ SIDE SIIELL SIDi: 1 1ti,I St Di: F LU ltr [ ],{t'tln ttlG tl/r'l'E R I'AT E R WATE R t,lirT E R v,AI E ii r.J.,\\T r:rr. TOT/I L t Lt, lD. Ltl/l{ll lr, 5oD, ooc 6, 0oo,00o Ir, 500,000 6,ooo,ooo 6, ooc, oco t,o3o,ccc Lloul0, l-l:i il R l,too;oco (',000,000 \\,500, ooo E,oQq ooo 6.ooc.ooo 8,_r4_J_, olq V/rPOfi, l-ti/l lR lFl.IEb-t t n's;. L R ;-t I R n;m.';(), co itD E r'l s F t) f Tr-r,,rxrut,ri I I 6,5/95 SStloi.l I 0g.)/95 8st95.7 I l0/95 8Stg6.2 I sntaFrc cRAvrr\\: I vLsc*'^r, r r' (L tot,t ttJ ). cP lToi.'r.,ucr n' rrv r r r..:u I D l .16\\7 .3615 ,3638 350E .3639 .3609 P/TSSES I I I l I VEI..OCIl'Y, FTiS!:.C T-2.95 .u3 PRESSUII; AT iN LE'[. PSI l,tt [ssuftE DttoP. i'si ,{ 3.8 I l.tt 3.8 lg,7

6. !t FOU L II'JG I\\ ES I51'A I.JCE

. 0005 .002 .0005 .002 . ooc5 c02 COI{ST tT IJ CT ION OF ON E S H F L I-Pt--qS.. PSI - - D[SlG!'J,'T ESl' i Jse/zzq-t iN I Elvil'] o; NSI.IE COOE CLASS coNr{Ecr'r0N5 6lzE & FACII(G) OUT OTI!ER G/TSKET & JCIlJI'STYLE J.0e/-lit9 200 sEC. lll, cl. 3 zl{il x 150/i l.ll{RF Ztf'x liO,i l{i{!iF irrTlSc-t.-'tljtF-- -1" thrcadcd cp!9. vent E Iillilrcedccl cPl9'. rrenr-L drain "8nGF;tlr:- ltct- -:TZy on-c137-<+- TUBE To T.s. Jotitr--. Rel le-l: evu.ulc<l-- IIII'INGENIENT Pl.ATf. - -Yi.i-ru.rs

o.-E{[o LErrG'rt{

slrcLL '. o.---68:tl-_

o. D.

--0!.0'1--ruBE plrctr-'-!375-1' r-L-l BArrrts cltoss rypE --ll-sen.cJic -j0'9:-.- --. ; I oNG TYI'E-N I L-tTElGllT.L0S.emi,ry...').lr!oo0.-.rir,.L-.2.l5.,ooo.-tlUt.,l)l'.E ar-D tTElGllT.L0S.Et.{i,TY...').lrt0o0.-.iittL-.2.l0.t00.0.-tlUt.,l)l'.E

131[::f

^ r*ini:= ---:]rnli:!,n-l j-r.',f-- ['-t'*l: Irrlil-lEE i+-: iitil=# Cl I /rN l'J lrL Sr'.513 - ;"0 25 ltc:ittilti.Fttt. I l -- cil/rNt.JtrL I sri5t6-:!0 1.625 lrc:irtit alrr'$-,iqyl,r-i.-E f-[5ll,lr',un --tt-t) -Lo11!.i ti."e-.1' -!loY1:rr1: t-lr-c.3!.ef.'-qU JU.sLrur rr.'\\r (;()rir'.

pER DCA'S: lwo l_.__J.Ii:lll,__Ljl:Ll_,:,::_1....:ji.::-

zsoxrjtioAr)rvny po.d34_or_o [fI3*::mry:-f!1*-=pl=**+ cnrlr)Ei{.ru.J. ucro.l P0063s-0r-.t l_::_h__1.. J__:.

,o.sr:ilr.'.t r cn,r..,r- *^*

hgl:.-_lli:l.T _ 250:l t,noAr)\\\\,nY Poo634-oI-o l-J=13:fi'trt: cn t$t)E i{. [.1. J. uc 10.1 P00635-01-0.-t-. l_____:: --;;i.-f* E---l----- t)/r i t: I tt t'JG 12

c,*J\\ EAT EXI lAIrtC l!Q D/r'i A [;l lI E'f rr.1----t,ulflTrmT-r0unr- 'r '._'--- $Efr vlcL F " tol' NT ' F'- TYPE so. l-1. t'E n sl{ E [- [- JOt] sl t E Lt-s. lN 5i'- ll I ES/Pn lin L. Ttt/in ct-nss

..--r-

,SO. FT. Pt ll ljl.llT ctTC -d.-r!-- PE N FOTIN'IA NCI O T UN iT urrffiil cotiD lr I 0l.l B c0ilt) I l-I ol.t c COI:OITIOtI i) F-lri-T,. ivr]Ir:.drcf + OVEIT/lLL COtF., CLEA'{/Sf nVICE gIUrll6-tr'[1 r FT'2 5? I tr7.6 x I Q1_1!1".jd. ) .!) v. l0 (R,-r.rd. ) (t t.lr) (t.0) (t.o)=l I.11 miio{# j?B. jDJ_l-_gI(,!_. o)..'2 8. ?- ?09 / 505 lt..(,)jlJt(!,0-)-1! 2 06 1 t,B7 a.u SHELL SIDE l UBE SIDE sltELL sto'i-TUTJE SIDE SH&, L L SI t,) E TU i.r l_ stD E f-t rItr) hl{ f F-l{ll.lc U'AT E R T'AT I R I,AT r: i( !,AT E P. \\.1/rT [: P. IIfi T [: i{ TOTAL F LU lD, LBIHR l, 500, ooo 5, ooo, ooo ll, 500. !99_ 6, ooo, ooo q.:Qgrgqq q-Aq,oQo LrourD. Lil/fln tr,50o,ooo rul lr.-590. 00.0- -9199!*9!g _!L500--()oQ_ 6,_ag!-_E9.9-vnPon. L B/l'lll htoN.cDi.t D's. L t)/ll R VAPT)R'D OTi CO'(DT }JSEt) TEI.'iP. I;J/OL'T C'P 106.8/ g5 B5/93.E ilr2.9/ I l0 8i/109.6 I 08,3 /95 8r/ e,: SPECIF IC G ttA VITY vrscosriV ri tcru tD). cP COl.ilriiCT I v iT'r' i L iCu ai) PASSES I I I I I I VELOCIT\\'. TTlSEC 2.20 3.62 2.22

3. 53 2.20 3.6?

PRESSUTi E AT IN LET, PSI PPESSURE DNOP, PSI ll.ir 3.80 ll.2 3.7 L-ru -:-9.9 FOU L lt*JG ll ESISTANCE .0005 .002 .0005 .002 .0005 ...gE cot{sTfiucilci{ QF Ql{E sHEtt P' :., PSI - - DESlGI.I/TEST Du-..jN TEf.iP oF ASt\\iE COOE CLASS CONNECTIONS (SIZE & FACIt.IGI -E TUBE SIDE lhtP ING EIfiE NT PLATE LENGTH AD NO.- O. D. GUAGE

l. D.

CROSS ]'YPE EMPTY FULL IINTEHINL O. D! TUBE P]TCH SPACiNC SHELL SIDE TUBE TO TUBES S}IE LL BAF F LES T'{EIGIIT. JO INT LB S. cl{n r{r{ E L CllANltI l. COVtr Il

LONG TYPE BUNDLE PA II]'

T. S, - lxl:D ]..S. - r l-(^T ING Cllo:$it;\\i I LE tC *C fr,Vi l.E MNTE TT IN L I ll!...'lf.l OTHE R GASI(ET &.tOINT STYLE CORN. ALLO\\YANCE T] lK..llJ. I I.'BES SIIEI L SItILL Ci)\\,t:ti orrrr.n ISSU E

ilAfIKS n I'n'r) f,X$

f sI' I ?titt JOSCl,ll ( nT COllP. 2500 llnon D\\t,nY c^hlDEN, N. J. 0810.1 ENG !

(lat lEn T EXI in NG I 11 Dn rA Sl lE rT -;-...t,. TYPE !.. SO. FT, PTII 5!IILL SI IELLS, ltl 5[tllt.$/Pn nn L. -l?E so. FT. frEn LrrJll' T[Mn (:t./rSS PtrlfOllMn tr'CE ()F Ut'JlT ,.rr'I RATION ttr'l() 0E ffiri'om corro tt t ct,'l c 37.9 x l0 Rcqd. 9.9 x lot' (n*qd.) t-T ffil .o)=9.5 l?..7 1.0)il.0 =l?.7 lgr/\\to lB5/382 l' 'ExCllnllGt:u, I,JTU IIIII Lr. t ll;n C IO ll I ovEI{ALL COE Ii.. CLEAN/5EnVlcE trTU r llR't *tF'1 x FT'Z i'LUID El.lI E 11 l i',G TOTAL F LUID. L[}i HN LIOUtD, LB/} IN vnPCn, LP/l'ltt hlolt-cot{D's. LBil {R VAPOR'D OR COt'lD Ei'ISED I'U BE S ID t: SHE LL SIDT: I,'AT E R 3, 000, 000 -jm 3,000, oco TU t:E SIL)T. TE'.,iP, IN/OUT "i= -5 SI'ECIF lC Gfi/rVlTY \\rtscoslTY (L rOl.J lr)), CP CCI.IDUCTIVtTi' ( L !OU ID} PASSES VELOCI'I'Y. FT/SEC Pn ESSUB E AT lr\\ LET, PSI PNESSURE DROP, T'SI I t ING R ESISTAI.ICE EOU L: TUIIE SIDE T'AT I P. 4,oco,ooo Ir, 000, ()00 SI{ELL SIDE SHELL SIDE , 5oo, ooo },AT I N I I B.U L.r_l _35/ vr?. llea-a ,-[,, ;., PSI - - DESIGN/TEST SHE LL S]DE TUBE SIDE 0u-.jN TEI\\4P o[= -a-- f--- AS[4E CODE CLASS COT{FJECTIONS 6rzE & FACthtGl IN OUT OTHE II GASKET & JOIt\\:T STYLE conn. ALLotl'nNcE TUSE TO TUBES SI IE LL ENFFLES TYEIGHT. T.S. JOINT IhIPINGEMENT PLATE

t. O.-

O. D. -TUBE FlTcll-A O CNOSS ]'YPE 'SPNCING

LOi{GTYPET - -..,.

L8S. EMPTY FULL BUNT'L E -e-- PATIT ITATE H IA L THK.-1N. PA IIT MNI EII IAL I l'11\\.'l[', TUIiES T S.. FIXED SIIF I.L 'r'.s..FLoullJ!_-r sll[.tL covEn clt()5s tln l'l L l: -1 CI IANNE L I.ONG I}N F LI: cl lAt..JtJ I L ct) \\, [: fi crt il[ n cLtAttKs .- F F JOSEPII ON T CONP. 2500 trlloAD\\VAY cA[4 D I N, hl..t. 0s 1 i ISSUC 08104 AP[t'O tsT l rti0}}

v t e Letter Sequence Request
TAC:MF6376, SFDP Clarifications (Approved, Closed)
Initiation Request, Request, Request, Request, Request, Request Acceptance, Acceptance Administration Withholding Request Acceptance Questions Answers 17 December 2014 3 August 2015 Results Approval, Approval Other: ML15189A059, ML15189A060, ML15247A405, ML15247A409
MONTHYEAR2015-07-10 [Table View]

CNL-15-147, Responses to NRC Acceptance Review Questions Regarding Essential Raw Cooling Water and Component Cooling System License Amendment Request

Text

Subject:

References:

Enclosures:

1.0 Rrrpole

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