Text

Response to a Request for Additional Information (RAI Dtd August 2, 2005) in Support of License Amendment Request Nos. 302 and 173, Extended Power Uprate
	ML052550373
Person / Time
Site:	Beaver Valley
Issue date:	09/06/2005
From:	Lash J; FirstEnergy Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-05-140
	Download: ML052550373 (113)
	v • d • e

FENOC Beaver Valley Power Station P.O. Box 4 FirstEnergy Nuclear Operating Company Shippingport, PA 15077-0004 Jantes H. Lash 724-682-7773 Director, Site Operations September 6, 2005 L-05-140 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001

Subject:

Beaver Valley Power Station, Unit Nos. I and 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Response to a Request for Additional Information (RAI dated August 2, 2005) in Support of License Amendment Request Nos. 302 and 173, Extended Power Uprate By letter dated August 2, 2005, the U.S. Nuclear Regulatory Commission (NRC) issued a request for additional information (RAI) pertaining to FirstEnergy Nuclear Operating Company (FENOC) License Amendment Request (LAR) Nos. 302 and 173 (Reference 1). These LARs propose an Extended Power Uprate (EPU) for Beaver Valley Power Station (BVPS) Unit Nos. 1 and 2. The EPU LAR proposes increasing the licensed power level approximately 8 percent above the current licensed power level.

Enclosure 1 contains the non-proprietary FENOC responses to all of the August 2, 2005 RAI questions except question number 4. The response to question number 4 is not included in this enclosure because it contains proprietary information.

Enclosure 2 contains the proprietary FENOC response to question number 4 of the August 2, 2005 RAI. The proprietary information in Enclosure 2 has been identified with brackets.

Enclosure 3 contains the non-proprietary FENOC response to question number 4 of the August 2, 2005 RAI. The proprietary information in Enclosure 3 has been identified with brackets and deleted.

As the response to RAI question number 4 in Enclosure 2 contains information proprietary to Westinghouse Electric Company LLC, it is supported by an affidavit signed by Westinghouse, the owner of the information. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission

Beaver Valley Powver Station, Unit Nos. 1 and 2 Response to a Request for Additional Information in Support of License Amendment Request Nos. 302 and 173, Extended Power Uprate L-05-140 Page 2 and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.390 of the Commission's regulations.

Accordingly, it is respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR 2.390 of the Commission's regulations.

Correspondence with respect to the copyright or proprietary aspects of the items listed above or the supporting Westinghouse affidavit should reference Westinghouse letter CAW-05-2046 and should be addressed to B. F. Maurer, Acting Manager, Regulatory Compliance and Plant Licensing, Westinghouse Electric Company LLC, P. 0. Box 355, Pittsburgh, Pennsylvania 15230-0355.

No new regulatory commitments are contained in this submittal. If you have questions or require additional information, please contact Mr. Henry L. Hegrat, Supervisor -

Licensing, at 330-315-6944.

I declare under penalty of perjury that the foregoing is true and correct. Executed on September 6 2005.

Sincerely, mes H. Lash

Enclosures:

1. Non-Proprietary responses to all RAI questions except number 4

2. Proprietary response to RAI question number 4

3. Non-Proprietary response to RAI question number 4

4. Affidavit

References:

1. FENOC Letter L-04-125, License Amendment Request 302 and 173, dated October 4, 2004.

c: Mr. T. G. Colburn, NRR Senior Project Manager Mr. P. C. Cataldo, NRC Senior Resident Inspector Mr. S. J. Collins, NRC Region I Administrator Mr. D. A. Allard, Director BRP/DEP Mr. L. E. Ryan (BRP/DEP)

L-05-140 Enclosure 1 REQUEST FOR ADDITIONAL INFORMATION RELATED TO FIRSTENERGY NUCLEAR OPERATING COMPANY (FENOC)

BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 (BVPS-1 AND 2)

EXTENDED POWER UPRATE (EPU)

DOCKET NOS. 50-334 AND 50-412 By letter dated October 4, 2004, as supplemented February 28, May 26, June 14, and July 8, 2005, Agencywide Documents Access and Management System (ADAMS)

Accession Nos. ML042920300, ML051530376, ML051670270, and ML051940575, FENOC (the licensee) proposed changes to the BVPS-1 and 2 operating licenses to increase the maximum authorized power level from 2689 to 2900 megawatts thermal rated thermal power or approximately 8 percent. The Nuclear Regulatory Commission (NRC) staff has reviewed the licensee's application against the guidelines in the EPU review standard (RS-001) and determined that it will need the additional information identified below to complete its review.

Question

1. Section 10.16.1.2 of the risk assessment (Reference 2), states: "A review of the engineering change packages associated with the EPU including containment conversion was performed to determine their effect on systems and associated equipment that are important to plant risk."

a. Are the BVPS-1 auxiliary feedwater cavitating venturis and main feedwater (MFW) fast-acting isolation valves related to EPU?

Response

The BVPS-1 auxiliary feedwater cavitating venturis and main feedwater fast-acting isolation valves were installed to support the BVPS-1 containment conversion design modification License Amendment Requests (LAR 317 & 190), and these components are related to the extended power uprate (EPU).

As noted on page 1-4 of Enclosure 2 of LAR 302 & 173 (L-04-125), the containment conversion from a sub-atmospheric to an atmospheric containment design, including related modifications such as the addition of feedwater isolation valves and auxiliary feedwater flow limiting venturis for BVPS-1 are required to support the implementation of the EPU analyses.

L-05-140 Enclosure 1 Page 2 of 34 Question

b. For EPU-related change packages, please provide the details of these reviews for BVPS-1 and 2, including the effect of each modification on the probability risk assessment (PRA) model.

Response

An evaluation was performed as a two-step screening process. The end result determined whether there is a significant impact on risk due to a plant modification. The two steps are outlined below and shown on Figure 1-1. In each step, if the criterion can be answered in the negative for a given component, that component can be eliminated from further consideration, as it is considered to have no impact or a negligible impact on risk.

Step 1: Is the modified system or component currently modeled in the PRA, or not modeled and considered potentially important to plant risk? - Modifications to components that are currently included in the PRA model will be evaluated for risk impact.

In the event a component is not included in the PRA model, yet the component is determined to be potentially important to plant risk, and therefore should be included in the PRA model, the component will be evaluated for risk impact. Potential risk impact for components not included in the PRA model are determined by engineering judgment.

Step 2: Modification meets guidelines in Standard Review Plan 19.0:

Does the change impact the system performance in a potentially negative or non-conservative manner?

Does the change impact the system design in such a way as to alter system reliability models?

Does the change impact the support function of the system in such a way as to alter the dependencies in the model?

If the answer to all of these criteria is no, then there is no expected impact on system function or component reliability due to the plant modification.

The process resulted in the majority of the plant modifications being screened as not modeled in the PRA, or not important to risk. Only seven plant modifications passed the first screen. Those modifications are:

BVPS-1 Installation of Main Feedwater (MFW) Fast Acting Feedwater Valves

BVPS-1 Installation of Auxiliary Feedwater (AFW) Cavitating Venturis

Extended Power Uprate Charging System Rethrottling (BVPS-1 and BVPS-2)

Charging Pump Rotating Assembly Replacement (BVPS-1 and BVPS-2)

Replacement Steam Generator Level Transmitters (BVPS-1)

Feedwater Valve Replacement (BVPS-2)

Replacement Steam Generators (BVPS-1)

L-05-140 Enclosure 1 Page 3 of 34 A review of the above seven modifications was performed. It was determined that these modifications were to be made in order to maintain or improve the performance of equipment under EPU conditions. This will ensure that the plant systems and equipment will continue to be operated within their design constraints. Therefore, it was concluded that the failure rates of the affected components would not change with the implementation of EPU. A brief description of the evaluations performed for each of the seven modifications is provided below.

The MFW fast-acting feedwater valves and AFW cavitating venturis were considered to be potentially important to risk, as they were new components that were not modeled in the current PRA and may impact the function of the MFW and AFW systems, respectively.

Thus, these components were added to the BVPS-1 PRA model. Since similar components were modeled in the BVPS-2 PRA model, their failure rates were assumed to be applicable to BVPS-1 also. Results from the re-evaluation, as addressed in response to RAI question 3, indicate that these components are not significant contributors to risk.

The fast-acting feedwater valves have a Fussell-Vesely of 1.05E-07 each, and the cavitating venturis have a Fussell-Vesely of 1.90E-09 each.

The charging system modifications (rethrottling and rotating assembly replacement) were included in the thermal-hydraulic Modular Accident Analysis Program (MAAP) to evaluate their impact on the PRA model success criteria at EPU conditions. It was concluded that these modifications have no impact on the success criteria due to the EPU, as all the pre-EPU modeling success criteria remained valid for the post-EPU conditions (one auxiliary feedwater pump delivering flow to one steam generator provided enough heat removal capability at BVPS-1, even with the AFW cavitating venturis installed, to prevent core damage).

The replacement steam generator (RSG) level transmitters at BVPS-1 are not explicitly modeled in the PRA, and will not impact any modeled component or success criteria. The feedwater valve replacements at BVPS-2 are considered to be a one-for-one replacement for PRA modeling purposes, and also will not impact any modeled component or success criteria. Therefore, these modifications were not considered further.

The RSG was addressed by a re-calculation of the steam generator tube rupture (SGTR) initiating event frequency to account for the improved Alloy 690 material used for the replacement steam generator U-tubes. The methodology for this re-calculation is provided in the response to RAI question 4. The RSG SGTR initiating event frequency was calculated to be 6.96E-04 /year per steam generator versus 1.48E-03 per steam generator in the original steam generator model. The contribution to core damage frequency (CDF) due to SGTRs is 1.71 E-07 /year per steam generator for the replacement steam generator EPU model. This contribution is based on the re-evaluation as addressed in RAI question 3. The contribution to CDF from SGTRs for the original steam generator EPU model is 3.93E-07 /year per steam generator. Thus, it can be seen that both the SGTR initiating frequency and the contribution to CDF decrease with the replacement steam generator.

L-05-140 Enclosure 1 Page 4 of 34 Figure 1-1 Is the modified system or component currently YES modeled in the PRA?

NO0l Is the modification considered potentially Further evaluation YES important to plant risk? of plant modification for risk impact is NO required.

Does the change impact the system performance in YES a potentially negative or non-conservative manner?

NO Does the change impact the system design in such a way as to alter system YES reliability models?

NO I Does the change impact the support function of the YES system in such a way as to alter the dependencies in the model?

NOD IF Modification can be screened from post-EPU PRA model, since there is no expected Impact on system functions or component reliability.

L-05-140 Enclosure 1 Page 5 of 34 Question

2. Section 10.16.1.4 of Reference 2, discusses the impact of EPU conversion on the human reliability analysis (HRA). The major impact is that the time available to perform some operator actions had decreased. In some cases, the base PRA model used a conservative estimate of the time available, which is taken in the analysis to bound the post-EPU time. The NRC staff notes that use of bounding times can mask the actual change in risk, although such practice should result in a bounding estimate of risk. The following clarifications and additional information are needed to facilitate determining the overall impact of EPU on the HRA.

Question

a. For both units, please provide the detailed HRA for all human interactions

("operator actions") that (1) have a Fussell-Vesely importance measure greater than 0.005 or a risk-achievement worth greater than 2, or (2)were modified to represent the post-EPU plant. Include whether the time available is considered "bounding" or is best estimate for pre- and post-EPU conditions.

Response

The following tables provide the Fussell-Vesely importance measures, risk achievement worth, and basis for the time available to perform the operator action used in the HRA for all BVPS-1 and BVPS-2 human interactions that:

(1) have a Fussell-Vesely importance measure greater than 0.005 or a risk achievement worth greater than 2.0 for the pre-EPU and post-EPU conditions, or (2) were modified to represent the post-EPU plant.

It should be noted that the post-EPU importance measures are based on the realistic human error probability (HEP) values that were reassessed using MAAP results to determine a best estimate of the time available, and the requantified PRA model used to address RAI question 3.

Table 2-1 identifies the BVPS-1 pre-EPU operator actions that have either a Fussell-Vesely importance greater than 0.005, or a risk achievement worth of greater than 2.0. All of these pre-EPU human actions were evaluated using best estimate hand calculations to determine the time available to perform the action.

L-05-140 Enclosure 1 Page 6 of 34 Table 2-1. BVPS-1 Pre-EPU Risk Significant Operator Action Importance Measures Basic Fussell- Risk Time Event Description Vesely Achievement Available Importance Worth Basis Operators setup portable fans & Best OPRBV3 open doors to cool Emergency 1.38E-01 2.62E+00 Estimate

__________Switchgqear.

Operator cools down &

OPRCD3 depressurizes the RCS using 7.88E-03 2.54E+00 Best OPC3 atmospheric steam dumps or 78E3Estimate RHR valve during a SGTR.

Operator depressurizes RCS to LHSI entry conditions by using Best OPRCD6 pressurizer PORVs; given a 5.02E-02 1.96E+00 Estimate Small Break LOCA and failure of HHSI.

Operator depressurizes RCS to LHSI entry conditions by using Best OPRCD7 pressurizer PORVs; given a 4.76E-02 1.31 E+00 Estimate Small Break LOCA and failure of HHSI and AC Orange power.

Operator initiates Bleed & Feed I

OPROB2 when AFW fails, given that 1.55E-02 2.13E+00 Best OPO2 DAFW and MFW restoration was 15E2 23+O Estimate not attempted.

OPROCI Operator trips the RCPs during a 8.16E-03 2.70E+00 Best

_____loss of all CCR. Estimate Operator depressurizes RCS to OPOi OPROD1 RHR and LHSI entry conditions b~~~lngpr~sieizer~~~~~ns 24E3 2.44E-03 23+OBest 2.53E+00 OLtjmst by using pressurizer PORVs or Estimate sprays; cooldown is successful.

OPROS6 Operator manually initiates safety 2.44E-03 3.99E+00 Besti injection given failure of SSPS. ______Estimate OPRSL1 Operator identifies ruptured S/G 5.30E-03 2.54E+00 Best

______and initiates isolation. Estimate ORI3 OPRSL3 Operator open S/G locally safety gags relief a stuck valve. 23E0 235E-02 11E00Best 11OE+00 Estimate Operator manually aligns OPRWAI Auxiliary River Water pump when 5.1 7E-03 1.6E00Best main RW pumps fail given that Estimate Offsite Power is available.

Operator aligns makeup to the Best OPRWM1 RWST, given a SGTR with 4.70E-02 6.75E+00 Estimate secondary leakage. Estimate

L-05-140 Enclosure 1 Page 7 of 34 Table 2-2 identifies the BVPS-2 pre-EPU operator actions that have either a Fussell-Vesely importance greater than 0.005, or a risk achievement worth of greater than 2.0. All of these pre-EPU human actions were evaluated using a hand calculation best estimate time available to perform the action.

Table 2-2. SVPS-2 Pre-EPU Risk Sianificant Onerator Action Imnortance Measures Basic Fussell- Risk Time Event Description Vesely Achievement Available Importance Worth Basis Operator depressurizes RCS Best OPRCD3 using atmospheric steam dumps - 1.50E-03 2.03E+00 Estimate SGTR Estimate Operator depressurizes RCS to OPRCD6 LHSI entry conditions by using 2.48E 02 1.31 E+00 Best pressurizer PORVs given a Small .E- . Estimate Break LOCA and failure of HHSI.

Operator initiates Bleed & Feed, Best OPROB1 after attempting to realign MFW 6.46E-02 1.66E+01 Estimate OPROB2 Operator initiates Bleed & Feed, 3.28E-02 1.89E+00 Best OPO2 MEW restoration not attempted' 32E0I.8E0 Estimate OPRODI Operator LHSIIRHSdepressurizes entry conditions 1.23E-03 1_____________0 2.03E+00 Best Estimate OPROF2OP 2 Operator

-no Si realigns main feedwater 1.38E-03 13E3 5.06E+00 50E0 Best Estimate OPROS6OPO6 Operator manually actuates AFW following transient 4.24E-03 _

5.23E+00 Best Estimate OPOIOPROT1Operator manually trips reactor within 1 minute 2.36E-03 2.88E+00 Best Estimate OPRSL1 Operator identifies ruptured S/G 5.69E-03 2.03E+00 Best OPRand initiates isolation to Estimate OPW 1 Operator aligns makeup to RWST 2.19E-02 4.61 E+00 Best OPW 1 - SGTR with secondary leakage ______________Estimate Table 2-3 identifies the BVPS-1 post-EPU operator actions that have either a Fussell-Vesely importance greater than 0.005, or a risk achievement worth of greater than 2.0. These importance measures are based on the reassessment of the HEP values and requantification of the post-EPU PRA model used to address the issues raised in RAI question 3. All of these post-EPU human actions were reassessed using the MAAP results for the time available to perform the action, and are considered best estimates.

L-05-140 Enclosure 1 Page 8 of 34 Table 2-3. BVPS-1 Post-EPU Risk Significant Operator Action Importance Measures Basic Fussell- Risk Time Event Description Vesely Achievement Available Importance Worth Basis Operator depressurizes the RCS to 400 psig by dumping steam through the intact steam Best OPRCD3 generator atmospheric steam 1.05E-02 3.48E+00 Estimate dumps to depressurize and cool down the secondary side

____ ____ (SGTR).

Operator depressurizes the RCS to 400 psig by locally Best OPRCD5 manipulating the steam generator 5.90E-03 1.22E+00 esti atmospheric steam dumps to Estimate relieve steam during a SBO.

Operator depressurizes the RCS to 400 psig by dumping steam through the steam generator Best OPRCD6 atmospheric steam dumps to 1.43E-01 4.09E+00 Estimate depressurize and cool down the secondary side (SGTR with HHSI has failed).

Operator depressurizes the RCS to 400 psig by locally manipulating the steam generator Best OPRCD7 atmospheric steam dumps to 1.55E-01 2.14E+00 Estimate relief steam, given HHSI failure and loss of emergency AC

_____ _____ oran ge. _ _ _ _ _ _

Operators provide borated makeup water to the RWST OPRMU5 initially from the spent fuel pool, 1.02E-02 2.63E+00 Best and, in the long term, from Estimate blending operations following an ISLOCA.

Operator starts charginglHHSI OPROA1 pumps and aligns an appropriate 4.1 1E-04 2.06E+00 Best OPOI flow path for boron injection after Estimate an ATWS event.

OPROC1 Operator trips RCP during loss of 2.12E-02 5.40E+00 Best OPOI CCR Estimate OPROC2 OPO2 Operator trips RCP during loss of all seal cooling. 5.30E-03 53E3 2.10E+00 20+0 est Estimate Operator depressurizes RCS to Best OPRODI RHS entry conditions using 3.53E-03 3.48E+00 Estimate pressurizer spray/PORVs. Estimate

L-05-140 Enclosure 1 Page 9 of 34 Table 2-3. BVPS-1 Post-EPU Risk Significant Operator Act on Importance Measures Basic Fussell- Risk Time Event Description Vesely Achievement Available Importance Worth Basis Operator starts diesel driven Best OPROF6 AFW pump and manually 9.66E-03 1.49E+00 Estimate controls MFW bypass valve. Estimate Operators protect RSS pumps by OPROP1 stopping them (QS failure) 1.27E-02 1.22E+00 Best restrtig s sfficentEstimate whn tere water in the sump.

Operator manually actuates safety injection and verifies operation of certain safety equipment on loss of SSPS due OPROS1 to actuation relay failure given a 8.78E-03 2.14E+00 Best transient initiating event that Estimate leads to Si conditions. On failure of manual safety injection actuation, the operator manually aligns the safety equipment.

Operator starts AFW given failure OPROS6 of SSPS for sequences in which 1.21 E-02 1.18E+01 Best there is no safety injection; e.g., Estimate turbine trip sequences.

Operator identifies the ruptured steam generator, and isolates or Best OPRSL1 verifies closed all flow paths to 8.58E-03 3.49E+00 Estimate and from that steam generator, following an SGTR event.

Operators locally gag the stuck- Best -

OPRSL3 open steam relief valves during 3.80E-02 1.17E+00 Estimate the SGTR event.

Operator manually starts and OPRWAI aligns auxiliary river water pumps 3.03E-02 4.85E+00 Best to the required river water header Estimate given no LOSP.

Operator supplies borated makeup water to the RWST OPRWM1 initially from the spent fuel pool, 7.17E-02 1.03E+01 Best OPW1 and, in the long term, from Estimate blending operations during an SGTR event.

L-05-140 Enclosure 1 Page 10 of 34 Table 2-4 identifies the BVPS-2 post-EPU operator actions that have either a Fussell-Vesely importance greater than 0.005, or a risk achievement worth of greater than 2.0. These importance measures are based on the reassessment of the HEP values and requantification of the post-EPU PRA model used to address the issues raised in RAI question 3. All of these post-EPU human actions were reassessed using the MAAP results for the time available to perform the action, and are considered best estimates.

Table 2-4. BVPS-2 Post-EPU Risk Significant Operator Action Importance Measures Basic Fussell- Risk Time Event Description Vesely Achievement Available Importance Worth Basis Operator depressurizes the Reactor Coolant System (RCS) to 400 psig by dumping steam OPRCD3 through the intact steam generator 1.22E-03 2.01 E+00 Best atmospheric steam dumps to Estimate depressurize and cool down the secondary side (SGTR).

Operator depressurizes the Reactor Coolant System (RCS) to 400 psig by dumping steam through the steam generator Best OPRCD6 atmospheric steam dumps to 2.51 E-02 1.30E+00 Estimate depressurize and cool down the secondary side (small LOCA with HHSI failed).

Not impacted by EPU.

Operator cross-ties station instrument air to containment Best~

OPRICI instrument air.t .04E-02 I.20E+OO Estimate Not impacted by EPU.

Operators initiate bleed-and-feed operation by initiating safety injection, opening the PORVs, Best OPROB1 reopening the PORV block valves, 6.94E-02 1.69E+01 Estimate and verifying HHSI pump operation.

Not impacted by EPU.

Operators initiate bleed-and-feed operation by initiating safety injection, opening the PORVs, reopening the PORV block valves, B OPROB2 and verifying HHSI pump 3.49E-02 1.88E+00 Estimate operation. Actions take place after the operators fail to attempt to restore MFW.

Not impacted by EPU.

L-05-140 Enclosure 1 Page 11 of 34 Table 2-4. BVPS-2 Post-EPU Risk Significan Operator Acti n Importance Measures Basic Fussell- Risk Time Event Description Vesely Achievement Available Importance Worth Basis Operator depressurizes RCS to Residual Heat Removal System (RHS) entry conditions after dumping steam via the atmospheric steam dumps to cool Best OPRODi down the RCS, and to 1.OSE-03 2.OOE+0O Estimate depressurize the RCS by using pressurizer spray/PORVs following a steam generator tube rupture (SGTR) event.

Operator opens main feed bypass OPROF2 valves following a partial 191E03 529E+00 Best feedwater isolation event after a Estimate plant trip.

Operator starts AFW given failure of SSPS for sequences in which Best OPROS6 there is no safety injection; for 4.23E-03 5.23E+00 Estimate example, turbine trip sequences.

Not impacted by EPU.

Operator pushes the manual reactor trip buttons after the Solid State Protection System (SSPS) Best OPROT1 fails to automatically actuate 2.53E-03 2.87E+00 Estimate reactor trip in response to a plant trip condition.

Not impacted by EPU.

Operator identifies the ruptured steam generator, and isolates or Best OPRSL1 verifies closed all flow paths to 3.73E-03 2.01 E+00 Estimate and from that steam generator, following an SGTR event.

Operators locally gag the stuck- Best OPRSL3 open steam relief valves during an 1.48E-02 1.OQE+00 Estimate SGTR event.

Operator supplies borated makeup water to the RWST initially from the spent fuel pool, Best OPRWM1 and in the long term, with makeup 1.91 E-02 4.19E+00 Estimate from service water during an SGTR event.

Not impacted by EPU.

L-05-140 Enclosure 1 Page 12 of 34 Table 2-5 identifies the remaining BVPS-1 post-EPU operator actions that were modified using realistic HEPs to represent the post-EPU plant, but did not have a Fussell-Vesely importance greater than 0.005, or a risk achievement worth of greater than 2.0. These importance measures are based on the reassessment of the HEP values and requantification of the post-EPU PRA model used to address the issues raised in RAI question 3. All of these post-EPU human actions were reassessed using the MAAP results for the time available to perform the action, and are considered best estimates.

Table 2-5. BVPS-1 Post-EPU Non-Risk Significant Operator Action Importance Measures Basic Fussell- Risk Time Event Description Vesely Achievement Available Importance Worth Basis Operator depressurizes the RCS to 400 psig by dumping steam through the steam generator atmospheric steam dumps to OPRCD4 depressurize and cool down the secondary side (SGTR given AC 1.36E-04 1.OOE+00 Best orange power has failed, and operators have to locally manipulate the steam generator atmospheric steam dumps to cooldown.)

Operator manually aligns power supply for the standby HHSI Best OPRHH1 pump, starts and aligns the pump 1.52E-03 1.48E+00 Estimate to provide the necessary flow after a small LOCA event.

OPRHH2 Operators fail to properly monitor Best plant parameters and prematurely NIA 1.OOE+00 Estimate secure the safety injection system.

Operators align main feedwater or OPROF1 the dedicated auxiliary feed pump Best given the auxiliary feedwater was 8.75E-05 1.66E+00 Estimate successful, but makeup to the PPDWST failed.

Operators manually initiate recirculation mode of operation by starting the RSS pumps, aligning OPROR1 power supplies to appropriate Best RSS equipment, resetting safety I.92E-06 1.OOE+00 Estimate injection system and verifying RW flow to RSS headers, following a small LOCA event.

Operators align outside OPROR2 recirculation spray trains A or B to Best the LHSI flow path for high 5.49E-05 1.02E+00 Estimate pressure recirculation, given that both LHSI supply trains fail.

L-05-140 Enclosure I Page 13 of 34 Table 2-5. BVPS-1 Post-EPU Non-Risk Signifi ant Operator Action Importance Measures Basic Fussell- Risk Time Event Description Vesely Achievement Available Importance Worth Basis Operator manually actuates safety injection and verifies operation of OPROS2 certain safety equipment on small Best LOCA or steam line break. On 2.65E-03 1.34E+00 Estimate failure of manual safety injection actuation, the operator manually aligns the safety equipment.

Operator manually actuates safety injection and verifies operation of OPROS3 certain safety equipment on Best medium LOCA. On failure of 2.17E-04 1.01 E+00 Estimate manual safety injection actuation, the operator manually aligns the safety equipment.

Operators locally close the steam OPRSL2 generator steam valves given that Best these valves cannot be closed 1.55E-04 1.03E+00 Estimate remotely during an SGTR accident.

Table 2-6 identifies the remaining BVPS-2 post-EPU operator actions that were modified using realistic HEPs to represent the post-EPU plant, but did not have a Fussell-Vesely importance greater than 0.005, or a risk achievement worth of greater than 2.0. These importance measures are based on the reassessment of the HEP values and requantification of the post-EPU PRA model used to address the issues raised in RAI question 3. All of these post-EPU human actions were reassessed using the MAAP results for the time available to perform the action, and are considered best estimates.

Table 2-6. BVPS-2 Post-EPU Non-Risk Significant Operator Action Importance Measures Basic Fussell- Risk Time Event Description Vesely Achievement Available Importance Worth Basis Operator depressurizes the Reactor Coolant System (RCS) to 400 psig by dumping steam Best OPRCDI through the steam generator 2.77E-05 1.03E+00 Estimate atmospheric steam dumps to depressurize and cool down the secondary side (small LOCA).

This is the same as CD1 except that AC Orange power has failed OPRCD2 and operators have to locally 1.t0E+00 B.esE+00 Best manipulate the steam generator 0OE0 .E+ Estimate atmospheric steam dumps to cool down.

L-05-140 Enclosure 1 Page 14 of 34 Table 2-6. BVPS-2 Post-EPU Non-Risk Significant Operator Action Importance Measurps Basic Fussell- Risk Time Event Description Vesely Achievement Available Importance Worth Basis Operator depressurizes the Reactor Coolant System (RCS) to 400 psig by dumping steam through the steam generator atmospheric steam dumps to OPC4 depressurize and cool down the 5.27E-06 1.00E+00 Best OPRCD4 secondary side (SGTR, AC Estimate Orange power has failed, and operators have to locally manipulate the steam generator atmospheric steam dumps to cool

______ ___ down)._ _ _ _ _ _ _

Operator manually aligns power supply for the standby HHSI Best OPRHH1 pump, and starts and aligns the 1.76E-04 1.07E+00 Estimate pump to provide the necessary flow after a small LOCA event.

Operators fail to properly monitor OPRHH2 plant parameters and prematurely 1.12E-04 1.25E+00 Best secure the safety injection system. Estimate Operators provide borated makeup water to the RWST initially from the spent fuel pool, Best OPRMU1 and in the long term, with makeup 0.OOE+00 1.OOE+00 Est from service water following a stmate transient-initiated small LOCA or SGTR.

This is the same as MUl except Best OPRMU2 that the actions follow a small 1.14E-03 1.21 E+00 est LOCA event. Estimate This is the same as MUI except OPRMU3 that the actions follow a medium 1.37E-05 1.OOE+00 Best LOCA event. Estimate Operators manually initiate recirculation mode of operation by starting the Recirculation Spray System (RSS) pumps, aligning power supplies to appropriate Best OPRORi RSS equipment, resetting safety 1.39E-04 1.13E+00 Estimate injection system, and verifying service water flow to RSS headers, following a small LOCA event.

L-05-140 Enclosure 1 Page 15 of 34 Table 2-6. BVPS-2 Post-EPU Non-Risk Significant Operator Action Importance Measures Basic Fussell- Risk Time Event Description Vesely Achievement Available Importance Worth Basis Operator manually actuates safety injection and verifies operation of certain safety equipment on loss of both trains of SSPS due to actuation relay failure. On failure OPO1 of manual safety injection 3.0E0 12E 0 Best OPROSI actuation, the operator manually Estimate aligns the safety equipment.

Though there is no LOCA present, a valid safety injection condition has occurred; for example, steamline break.

Operator manually actuates safety injection and verifies operation of certain safety equipment on loss of both trains of SSPS due to Best OPROS2 actuation relay failure. On failure 9.46E-04 1.07E+00 Estimate of manual safety injection actuation, the operator manually aligns the safety equipment.

Following a small LOCA Operator manually actuates safety injection and verifies operation of certain safety equipment on loss of both trains of SSPS due to OPROS3 actuation relay failure. On failure 4.17E-05 1.OOE+00 est of manual safety injection Estimate actuation, the operator manually aligns the safety equipment.

Following a medium LOCA OPRPRI Operator secures safety injection 11Best before PORVs are challenged. 1.71 E03 Estimate Operators locally close the steam generator steam valves given that Best OPRSL2 these valves cannot be closed 1.97E-04 1.06E+00 Estimate remotely during an SGTR accident.

All of the operator actions identified in the Tables 2-1 through 2-6 meet the criteria of either having a Fussell-Vesely importance measure greater than 0.005 or a risk achievement worth greater than 2, or were modified to represent the post-EPU plant using best estimate times to develop realistic HEPs (see response to RAI question 3). The human reliability analysis for all of these operator actions used the success likelihood index methodology (SLIM). As such, the SLIM process evaluates groups of human actions. Therefore, all human actions contained in the SLIM grouping are included in with the details of the operator actions identified in Tables 2-1 through 2-6.

L-05-140 Enclosure 1 Page 16 of 34 The details of the HRA for the operator actions are provided in the attached SLIM worksheets (included as Attachments 1 - 4 to Enclosure 1), which provide the rankings, weightings, and HEP mean values for each human interaction within the group. For BVPS-1, all pre-EPU human action SLIM worksheets are provided in Attachment 1, while Attachment 2 provides the BVPS-1 post-EPU human action SLIM worksheets which were reassessed in response to RAI question 3. Attachments 3 and 4 provide the SLIM worksheets for the pre-EPU and post-EPU reassessed human actions for BVPS-2, respectively.

Question

b. Table 10.1 6-5 provides post-EPU importance measures for selected operator actions. (1) Which unit PRA model was used to generate these importance measures? (2) Are the operator actions in this table, which are of the form "OPR*," the same as the corresponding actions in Table 10.16-2, which are designated "ZHE*" (where "*" represents an alphanumeric string).

Response

The first two sheets of Table 10.16-5 (L-05-104 Enclosure 1, pages 21 and 22 of 32) were generated using the BVPS-1 EPU PRA model. The second two sheets of Table 10.16-5 (L-05-104 Enclosure 1, pages 23 and 24 of 32) were generated using the BVPS-2 EPU PRA model.

The operator actions listed in Table 10.16-5 (UOPR*" designators) are the basic event identifiers used in the top event fault tree models. The operator actions listed in Table 10.16-2 ("ZHE*" designators) are the RISKMAN database HEP distribution identifiers used to quantify the basic events. Typically, these correspond directly to each other (OPRAF1 and ZHEAF1 are the same action). However, there are some cases where they do not correspond directly to each other. The following list includes the exceptions to the rule.

BVPS-1:

OPRCC3 is quantified using ZHECC1 OPRDF1 is quantified using ZHEOF1 OPRHH3 is quantified using ZHEHH1 OPRHH4 is quantified using 1.0 OPRNA1 is quantified using 1.OOE-02

L-05-140 Enclosure 1 Page 17 of 34 BVPS-2:

OPRCC3 is quantified using ZHECC1 OPRHH3 is quantified using ZHEHH1 OPRPR2 is quantified using ZHEPII OPRMU4 is quantified using 1.0 OPROS4 is quantified using 1.0 OPRPR1 is quantified using 1.0 OPRRI2 is quantified using 1.0 OPRSL3 is quantified using 1.0 OPRXT3 is quantified using 1.0 Question

c. Table 10.1 6-1 gives pre- and post-EPU times to core damage for station blackout scenarios. Why does this time increase on BVPS-1 and decrease on BVPS-2 for the "182 gpm, successful cooldown/depressurization, primary plant demineralized water storage tank make-up available" case?

Response

The increase in time to core damage for the BVPS-1, 182 gpm reactor coolant pump (RCP) seal LOCA with successful cooldown/depressurization and primary plant demineralized water storage tank (PPDWST) make-up available case is primarily due to changes in the primary system water mass used in the MAAP parameter file for the pre- to post-EPU/ replacement steam generators (RSG) conditions.

This key difference in the BVPS-1 MAAP inputs is that the initial primary system water mass (excluding the pressurizer) for the EPU model is 388,127 lbs. vs. 382,073 lbs. for the pre-EPU model MAAP analysis. Thus, the EPU model has about 1.5% more water mass in the primary system. This initial mass difference is due to a slightly larger primary side volume for the RSG's as compared to the original steam generators (OSG). The total primary side volume of one steam generator is 1136 ft3 for the RSG and 1087 ft3 for the OSG.

The impact of this change is subtle and does not appear to have a significant impact on thermal-hydraulic (T/H) behavior. Both the pre- and post- EPU cases behave similarly for the first 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months except for a time shift due to differences in time of seal binding failure (30 minutes for the pre-EPU case and 13 minutes for the post-EPU case). Around 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months , the two cases have different pressurizer behavior and the T/H results begin to diverge. Thus, there appears to be some beneficial impact from the RSGs due to an increased primary side initial inventory.

L-05-140 Enclosure 1 Page 18 of 34 Moreover, the effects of the increased inventory are more pronounced for the 182 gpm with successful cooldown/depressurization and PPDWST make-up available case, where the RCS inventory loss out the RCP seal LOCA is the governing circumstance to core uncovery, as opposed to the 21 gpm break sizes and PPDWST depletion cases where decay heat removal capability governs the time to core uncovery.

As expected, since the BVPS-2 RCS volume remained essentially the same for the pre- to post-EPU MAAP analysis, all BVPS-2 EPU cases provided in Table 10.16-1 resulted in a decrease in the time to core damage, due to the increase in decay heat associated with the power uprate.

Question

d. Under the discussion of "general transients," it states: "Thus, with the RSG [replacement steam generators] there is less margin for successful completion of the plant-specific feed and bleed procedure ... initiated at 0.495 hours0.00573 days 0.138 hours 8.184524e-4 weeks 1.883475e-4 months ...." Does the time available for this action change under EPU conditions? What is the human error probability (HEP) for this action, both pre- and post-EPU? Why was this action not included in Table 10.16-2 or 10.16-5?

Response

The general transient success criteria discussion presented in LAR 302 & 173 (L-05-104) was based on a loss of all feedwater (both main and auxiliary), with credit for operators to initiate feed and bleed at 13% wide range SG level per the plant procedures. This stemmed from a Westinghouse Owner's Group issue regarding the required component success criteria for feed and bleed implementation (number of power operated relief valves (PORVs) and high head safety injection (HHSI) pumps). To address this concern for EPU conditions, a MAAP analysis was performed assuming that one HHSI pump injects and one PORV was opened once the replacement steam generator reached the 13% wide range level, which occurred at 0.495 hours0.00573 days 0.138 hours 8.184524e-4 weeks 1.883475e-4 months . The results of this analysis showed that even at EPU conditions the feed and bleed component success criteria did not change from the current plant model (one HHSI pump and one PORV).

The timing used for the operator action to initiate feed and bleed developed for the human reliability analysis (HRA) was based on the maximum time that operators have available in order to successfully implement feed and bleed. In the thermal-hydraulic hand calculations developed for the Individual Plant Examination (IPE) human action accident scenarios, the time for feed and bleed implementation was based on the time for the PORVs to lift prior to steam generator dryout. This was estimated to occur 5 minutes prior to dryout, or at about 58 minutes following a reactor trip.

Since this time was shorter than the corresponding time of 63 minutes in a similar EPU MAAP analysis (a station blackout scenario with a 21 gpm RCP seal LOCA and loss of all feedwater), the IPE time value was bounding. Therefore, the HEPs used in the current PRA models (BVPS-1: 1.22E-03 for OPROB1, and 1.39E-02 for OPROB2; BVPS-2:

4.34E-03 for OB1, and 3.79E-02 for OB2) were bounding so the values were not changed for the EPU. As such, Tables 10.16-2 and 10.16-5, which listed operators actions that have changed for the EPU analyses, did not include these actions.

L-05-140 Enclosure 1 Page 19 of 34 Question

e. Note 2 of Table 10.16-2 explains that the reduction in time available for a number of the operator actions is due to adopting a new reactor coolant pump seal loss-of-coolant accident model. Is this considered an EPU change?

Response

The RCP seal LOCA expected time of occurrence, due to seal popping or binding failures, was assumed to occur at 13 minutes in the post-EPU PRA models. This assumption was not a result of the EPU, but was made in order to have the PRA models reflect the most recent RCP seal LOCA issues that were approved by the NRC in their acceptance of WCAP-15603-A, Revision 1.

Question

f. Note 3 of Table 10.16-2 refers to changes in HRA because the pre-EPU model did not credit resetting containment isolation phase B. Is this considered an EPU change?

Response

As noted in Note 3 of Table 10.16-2, the current (pre-EPU) HEP analyses takes credit for the operators resetting the containment isolation phase 'B' (CIB) signal and stopping the quench spray pumps, whereas the post-EPU HEP analyses does not.

The assumption of not resetting the CIB signal is not considered part of the EPU change but was done in order to maximize the impact of the EPU on the HEP by minimizing the time to transfer to safety injection recirculation mode. This timing was of interest for operator actions ZHECD1 and ZHECD2, where the operators are trying to depressurize the RCS below 400 psig. If core damage occurs due to additional equipment failures during the recirculation phase, the RCS would be at low pressure at the time of vessel melt-through. It is also of interest for operator actions ZHEMU1 and ZHEMU2, where the time to deplete the refueling water storage tank (RWST) is of relevance.

The operators actions to reset the CIB signal and stop quench spray flow are in the current plant procedures and will continue to be in the respective post-EPU emergency operating procedures.

Question

g. Note 4 of Table 10.16-2 says that ZHEIAI is considered a "guaranteed success since the diesel air compressor will auto-start." Is this change due to a change to the plant equipment? Is it related to the EPU?

Response

The change in the diesel air compressor starting signal from manual to automatic was due to a physical plant modification that was implemented by ECP-02-0541. This modification installed a backup train of instrument air, comprised of a 1500 scfm diesel powered, oil free, rotary screw air compressor, which auto-starts upon a low system air pressure signal.

L-05-140 Enclosure 1 Page 20 of 34 This backup train of instrument air was not related to the EPU modifications, but rather was performed to increase the reliability of the station air supply.

Question

h. Table 10.16-5 shows the Fussell-Vesely importance of operator action OPRIA1, "Given LOSP [loss of offsite power], operators locally start the diesel air compressor," as 6.13E-04. Is this the same operator action as ZHEIAI in Table 10.16-2? (It has the same description.) If "yes", how was the Fussell-Vesely determined, given that the HEP for ZHEIA1 is given as 0.0?

Response

Operator action ZHEIA1 is the same operator action as OPRIA1. ZHEIA1 is the RISKMAN database variable for the HEP and OPRIA1 is the PRA basic event for the operator action. ZHEIA1 is the operator action to manually start the diesel air compressor, and was evaluated using the time of the first RCP seal damage, given a loss of all seal cooling. As discussed in the response to RAI question 2.e, and shown in Table 10.16-2, this timing was changed from 60 minutes to 13 minutes for the post-EPU HRA. As such, it resulted in an increase in the HEP from 5.87E-03 to 1.18E-02.

However, as noted in the response to RAI question 2.g, there was a currently installed non-EPU change to auto-start the diesel air compressor. To represent this change in the post-EPU PRA model, the database variable ZHEIA1 was to be set to "guaranteed success" to accurately reflect the current plant conditions that would also be present following the EPU. This was considered necessary, since the post-EPU condition would have resulted in an increase in the HEP for the operator action to manually start the diesel air compressor, had it not already been changed to an auto-start feature.

It was later discovered (post-submiftal) that the change to make ZHEIA1 a "guaranteed success" was not incorporated into the post-EPU PRA model, and that the post-EPU adjusted value without the auto-start feature was used (1.18E-02). As such, a Fussell-Vesely importance value was calculated in the RISKMAN quantification and reported in Section 10.16 of Reference 2. However, as noted in the response to RAI question 2.g this change to the diesel air compressor starting circuit is not EPU related, so the HEP was set back to its pre-EPU normal value of 5.87E-03 used in the re-quantification to respond to RAI question 3.b.

It was also noted during this subsequent review that some of the other numbers listed in Table 10.6-2 of L-05-104 Enclosure I were not correctly identified. These include the following:

For BVPS-1, the true value of operator action ZHEIC2 that was used to quantify the pre-EPU (current) PRA model is 2.99E-03, not 2.73E-03.

For BVPS-2, the correct time available to complete the operator action used in the evaluation of ZHECD1 was 5.95 hours0.0011 days 0.0264 hours 1.570767e-4 weeks 3.61475e-5 months , not 12.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

For BVPS-2, the correct time available to complete the operator action used in the evaluation of ZHECD2 was 5.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months , not 12.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

L-05-140 Enclosure 1 Page 21 of 34 Question

i. Section 10.15 of Reference I states: "A review of operating procedures!

emergency operating procedures/training potentially impacted by EPU will be completed ...." How was the full impact of the EPU on the human reliability analysis determined if operating procedure changes have not yet been identified?

Response

The full impact of the EPU on the human reliability analysis will be addressed during the PRA model update process following the EPU implementation. However, in order to address the impact of the EPU on the operator actions analyzed in the LAR, it was assumed that only the timings and stress levels could be significantly impacted by the EPU, and that the indications, proceduralized steps and operator actions would essentially remain unaffected. The basis for this assumption is provided below.

Application of the success likelihood index methodology (SLIM) to quantify the event-level dynamic operator actions in the plant response model of a PRA has been adopted at BVPS. It is based on the assumption that the HEP in a particular situation depends on the combined effects of a relatively small set of performance-shaping factors (PSF) that influence the operators' ability to perform the action successfully. The PSFs were selected to describe the range of problems that the operators face. They were chosen to relate the impact of the following:

The scenario in which the action must be accomplished. These include plant/operator interface and indications from instrumentation; adequacy of time to accomplish the action; preceding and concurrent actions; and the complexity of the task.

The psychological and cognitive condition of the operators during the scenario. This includes stress; training and experience relative to the action; and procedures or other operational aids available to the operators, and their performance up to the current point in the scenario.

Based on these PSFs, it was assumed that the scenario based plant/operator interface and indications, preceding and concurrent actions, and task complexity would not be significantly impacted enough by the EPU to warrant a change in their ranking.

Additionally, for the psychological and cognitive condition of the operators during the scenario, it was assumed that only the stress rankings of the operator actions that had significantly less time to complete due to the EPU conditions would be impacted.

L-05-140 Enclosure I Page 22 of 34 Question

j. Are there any additional operator actions that are considered in the model for estimating large early release frequency (LERF)? Please provide a listing of any operator actions unique to LERF and an assessment of the impact of the EPU on the corresponding HEPs.

Response

All of the operator actions developed for the BVPS PRA models are contained in the plant model (Level 1)event trees used to calculate the core damage frequency, including actions for containment isolation and other actions important for estimating release frequencies. This approach, used in the BVPS PRA models, was selected for the following reasons:

All active systems, including the containment engineered safeguards, are included in the plant model event tree because their dependencies on support systems, such as electrical power and service water, can be determined more easily in the plant model event trees. This avoids the dependency tracking problems associated with placing certain active containment systems into the Level 2 containment event trees (CETs).

The prescribed boundary separates the phenomenological CET from the plant model event trees that deal only with active systems and operator actions with a well-defined interface.

The prescribed boundary facilitates a clean separation between analyses of likelihood (as measured by frequency) and uncertainty (as measured by probability).

This clean separation between plant model and CETs allows an optimization of both the plant analysis and the containment analysis, while at the same time providing needed flexibility in the modeling process. However, in doing so, all of the plant model information on the operability status of active systems important to the timing and magnitude of the release of radioactive materials must be passed into the CET when linked to the Level 1 event trees. This required that, in addition to representing the systems and functions that are important to keeping the core cooled, the plant model event trees had to also address active systems and functions important to containment isolation, containment heat removal, and removal of radioactivity from the containment atmosphere.

As such, there are no additional operator actions considered in the PRA models for estimating large early release frequency (LERF), and the Level 2 analyses are strictly based on containment phenomenology or events that have occurred during the core damage process. However, the operator actions that are modeled would have different importance measures based on their contribution to either CDF or LERF.

L-05-140 Enclosure 1 Page 23 of 34 Question

3. Please provide an assessment of the increase in risk if only the EPU is considered.

For example, the impact of containment conversion, BVPS-1 replacement steam generators, BVPS-1 AFW cavitating venturis and MFW fast-acting isolation valves should not be included unless they are required for the EPU. Note that this can be done either by having non-EPU changes in both the base model and the post-EPU model or in neither.

The NRC staff would prefer that this assessment use realistic HEPs for both the pre-EPU and post-EPU analysis (where these would change) to avoid masking of the actual change in risk; refer to question 2, above. However, if bounding HEP numbers are employed, justify that the final risk metric is bounding with respect to those HEPs.

The following risk metrics should be provided for both BVPS-1 and 2:

a. Internal events core damage frequency (CDF) and LERF.

b. CDF and LERF from internal fires.

Response

As noted in Section 1.1.2 of Enclosure 2 of LAR 302 & 173, L-04-125, the principal modifications planned to support implementation of the EPU LAR analyses include:

Containment conversion from a sub-atmospheric to an atmospheric design basis including related modifications such as the addition of (fast-acting) feedwater isolation valves and auxiliary feedwater flow limiting (cavitating) venturis for BVPS-1

Replacement charging/safety injection pump rotating assemblies

Replacement steam generators for BVPS-1 Since the above modifications are required to support the EPU, they were considered necessary and either explicitly or implicitly included in the EPU risk analysis (as addressed in the response to RAI question 1.b) in order to accurately determine the risk impact associated with the EPU.

Consequently, the only changes that were made to the post-EPU PRA models that were not associated with the EPU, were changes to the HEPs resulting from:

The change in timing of the RCP seal binding failure (see response to RAI question 2.e.)

Using conservative times to SI recirculation phase or RWST depletion by not crediting the resetting the CIB signal and stopping quench spray flow (see response to RAI question 2.f.)

Crediting the auto-start of the diesel air compressor by setting the HEP to zero (see response to RAI question 2.g.)

L-05-140 Enclosure 1 Page 24 of 34 Since the first two bulleted items above are not associated with the EPU, the impacted HEPs were reanalyzed excluding these changes, and instead used the pre-EPU PRA model assumptions. That is, the start of the increased RCP seal LOCA was assumed to occur at 60 minutes (based on NUREG-1 150) instead of the 13 minutes suggested in WCAP-15603-A, Revision 1, and credit was given for resetting the CIB signal and stopping quench spray flow, As noted in the response to RAI question 2.h, the third bulleted item was not included in the post-EPU PRA model, so the operator action to manually start the diesel air compressor was evaluated in the LAR 302 and 173 submittal using the post-EPU HEP, which reflected the change in timing of the RCP seal binding failure. In response to this RAI, the HEP for this operator action was set back to the pre-EPU value, since it removed the effects of non-EPU changes, as addressed below.

All of the operator actions impacted by excluding these non-EPU changes and using realistic HEPs developed from the MAAP result best estimate timings, when considering only the EPU related modifications, are presented in Table 3-1. This table complements Table 10.16-2 of Reference 2 to complete the full post-EPU HRA. This re-evaluation resulted in several changes, as outlined below:

In response to RAI question 2.e, since the new RCP seal LOCA model is not related to the EPU, all operator action times available were changed back to the pre-EPU model times available.

In response to RAI question 2.f, the HRA for the post-EPU model will use the operator action times available while taking credit for resetting the CIB signal and securing the quench spray system, as was done in the pre-EPU model.

In response to RAI question 2.g, the operator action OPRIA1 is no longer set to "guaranteed success," since the change to the diesel air compressor is not related to the EPU.

The HRA no longer uses the "bounding" operator action time available. Realistic timings are used, which resulted in decreasing many of the human error rates.

Table 3-1: Operator Action Human Error Probabilities Human Action Description Time Available PSF -

pre-EPU HEP -

pre-EPU 1Time Available PSF -

post- EPU HEP - post-EPU I pre-EPU post-EPU BVPS-11 OPROS2 - Operator manually actuates 0.67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months Time - 5 9.19E-03 0.94 hours0.00109 days 0.0261 hours 1.554233e-4 weeks 3.5767e-5 months Time - 3 7.68E-03 safety injection and verifies operation of certain safety equipment on small LOCA or steam line break. On failure of manual safety injection actuation, the operator manually aligns the safety equipment.

OPROS3 - Operator manually actuates 0.15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months Time -6 2.77E-02 0.35 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months Time - 4 1.90E-02 safety injection and verifies operation of certain safety equipment on medium LOCA.

On failure of manual safety injection actuation, the operator manually aligns the safety equipment.

L-05-140 Enclosure 1 Page 25 of 34 Table 3-1: Operator Action Human Error Probabilities Human Action Description Time PSF - HEP - Time PSF - HEP - post-Available pre-EPU pre-EPU Available post- EPU EPU

_ pre-EPUpost-EPU OPRHH1 - Operator manually aligns power 0.67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months Time - 4 3.87E-03 0.94 hours0.00109 days 0.0261 hours 1.554233e-4 weeks 3.5767e-5 months Time - 2 3.13E-03 supply for the standby HHSI pump, starts and aligns the pump to provide the necessary Dow after a small LOCA event.

OPRHH2 - Operators fail to properly monitor 2.21 hours2.430556e-4 days 0.00583 hours 3.472222e-5 weeks 7.9905e-6 months Time - 3 7.15E-04 13.91 Time - 1 5.77E-04 plant parameters and prematurely secure the hours safety injection system.

OPROF1 - Operators align main feedwater 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Time - I 1.58E-04 10.34 Time - 0 1.32E-04 or the dedicated auxiliary feed pump given hours the auxiliary feedwater was successful, but makeup to the PPDWST failed.

OPROR1 - Operators manually initiate 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Time - 2 2.01E-03 2.82 hours9.490741e-4 days 0.0228 hours 1.35582e-4 weeks 3.1201e-5 months Time - 1 1.88E-03 recirculation mode of operation by starting the RSS pumps, aligning power supplies to appropriate RSS equipment, resetting safety injection system and verifying RW flow to RSS headers, following a small LOCA event.

OPROR2 - Operators align outside 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Time - 2 2.85E-03 2.82 hours9.490741e-4 days 0.0228 hours 1.35582e-4 weeks 3.1201e-5 months Time - 1 2.60E-03 recirculation spray trains A or B to the LHSI flow path for high pressure recirculation.

given that both LHSI supply trains fail.

OPRODI - Operator depressurizes RCS to 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months lime - 1 1.58E-03 >24 hours Time - 0 1.42E-03 RHS entry conditions using pressurizer spray/PORVs.

OPRSL2 - Operators locally close the steam 9.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Time - 2 5.52E-03 17.99 Time - I 4.96E-03 generator steam valves given that these hours valves cannot be closed remotely during an SGTR accident.

OPRCD3 - Operator depressurizes the RCS 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months Time - 5 5.12E-03 > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Time - 2 4.19E-03 to 400 psig by dumping steam through the intact steam generator atmospheric steam dumps to depressurize and cool down the secondary side (SGTR)

OPRCD4 - Operator depressurizes the RCS 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months Time - 5 8.29E-02 > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Time - 1 5.10E-02 to 400 psig by dumping steam through the steam generator atmospheric steam dumps to depressurize and cool down the secondary side (SGTR given AC orange power has failed, and operators have to locally manipulate the steam generator atmospheric steam dumps to cooldown.)

L-05-140 Enclosure 1 Page 26 of 34 Table 3-1: Onerator Action Human Error Probabilities Human Action Description Time PSF - HEP - Time PSF - HEP - post-Available pre-EPU pre-EPU Available post- EPU EPU pre-EPU post-EPU OPRCD6 - Operator depressurizes the RCS 0.83 hours9.606481e-4 days 0.0231 hours 1.372354e-4 weeks 3.15815e-5 months Time - 3 4.99E-02 1.02 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Time - 2 4.40E-02 to 400 psig by dumping steam through the steam generator atmospheric steam dumps to depressurize and cool down the secondary side (SGTR with HHSI has failed).

OPRCD7 - Operator depressurizes the RCS 0.83 hours9.606481e-4 days 0.0231 hours 1.372354e-4 weeks 3.15815e-5 months Time - 5 1.35E-01 1.02 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Time - 4 1.20E-01 to 400 psig by locally manipulating the steam generator atmospheric steam dumps to relief steam, given HHSI failure and loss of emergency AC orange.

OPRWM1 - Operator supplies borated 21 hours2.430556e-4 days 0.00583 hours 3.472222e-5 weeks 7.9905e-6 months Time - 1 8.40E-03 30.46 Time - 0 7.68E-03 makeup water to the RWST initially from the hours spent fuel pool, and, in the long term, from blending operations during an SGTR event.

OPRWA1 - Operator manually starts and 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Time - 5 7.80E-03 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Time - 5 7.80E-03 aligns auxiliary river water pumps to the (was 13 required river water header given no LOSP. minutes due to RCP seal leakage)

OPRIAI - Given LOSP, operators locally start 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Time - 1 5.84E-03 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Time - 1 5.84E-03 the diesel air compressor .

OPRIC2 - Operators cross-tie station 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Time - 5 2.99E-03 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Time - 5 2.99E-03 instrument air to containment Instrument air (was 13 by locally opening manual valve IA-90. minutes due to RCP seal leakage)

OPRCD1 - Operator depressurizes the RCS 5.95 hours0.0011 days 0.0264 hours 1.570767e-4 weeks 3.61475e-5 months Time - 2 1.71E-03 6.63 hours7.291667e-4 days 0.0175 hours 1.041667e-4 weeks 2.39715e-5 months Time - 2 1.71E-03 to 400 psig by dumping steam through the (was 1.23 (time steam generator atmospheric steam dumps hours due difference to depressurize and cool down the secondary to CIB did not side (small LOCA). setpoint) justify a change in PSF)

OPRCD2 - Same as OPRCD1 except that AC 5.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months Time - 2 2.58E-03 11.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Time -2 2.58E-03 orange power has failed and operators have (was 2.02 (time to locally manipulate the steam generator hours due difference atmospheric steam dumps to cooldown. to CIB did not setpoint) justify a change in PSF)

OPRMU1 - Operators provide borated 4.03 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Time - 1 8.40E-03 4.03 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Time - 1 8.40E-03 makeup water to the RWST initially from the (was 0.46 spent fuel pool, and, in the long term, from hours due blending operations following a steam to CIB generator tube rupture event. setpoint)

L-05-140 Enclosure 1 Page 27 of 34 Table 3-1: Operator Action Human Error Probabilities {

Human Action Description Time PSF - HEP - Time PSF - HEP - post-Available pre-EPU pre-EPU Available post- EPU EPU pre-EPU post-EPU OPRMU2 - Same as OPRMU1 except that 1.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months Time - 3 1.01E-02 1.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months Time - 3 1.01 E-02 the actions follow a small LOCA event. (was 0.46 hours5.324074e-4 days 0.0128 hours 7.60582e-5 weeks 1.7503e-5 months due to CIB setpoint) _

BVPS-2 OPROS2 - Operator manually actuates 0.67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months Time - 4 1.71 E-02 0.94 hours0.00109 days 0.0261 hours 1.554233e-4 weeks 3.5767e-5 months Time - 2 1.33E-02 safety Injection and verifies operation of certain safety equipment on loss of both trains of SSPS due to actuation relay failure.

On failure of manual safety injection actuation, the operator manually aligns the safety equipment. Following a small LOCA OPROS3 - Operator manually actuates 0.15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months Time -5 2.20E-02 0.28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months lime - 3 1.71E-02 safety injection and verifies operation of certain safety equipment on loss of both trains of SSPS due to actuation relay failure.

On failure of manual safety injection actuation, the operator manually aligns the safety equipment. Following a medium LOCA OPRHH1 - Operator manually aligns power 0.67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months Time - 4 3.29E-03 0.94 hours0.00109 days 0.0261 hours 1.554233e-4 weeks 3.5767e-5 months Time - 2 2.49E-03 supply for the standby HHSI pump, and starts and aligns the pump to provide the necessary flow after a small LOCA event.

OPRHH2 - Operators fail to properly monitor 5.56 hours6.481481e-4 days 0.0156 hours 9.259259e-5 weeks 2.1308e-5 months Time - 3 5.87E-04 19.62 Time - I 4.44E-04 plant parameters and prematurely secure the hours safety injection system.

OPROR1 - Operators manually initiate 0.95 hours0.0011 days 0.0264 hours 1.570767e-4 weeks 3.61475e-5 months Time - 2 1.38E-03 9.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Time - 0 1.05E-03 recirculation mode of operation by starting the Recirculation Spray System (RSS) pumps, aligning power supplies to appropriate RSS equipment, resetting safety injection system, and verifying service water flow to RSS headers, following a small LOCA event.

OPROD1 - Operator depressurizes RCS to 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months Time - 1 1.20E-03 > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Time -0 1.04E-03 Residual Heat Removal System (RHS) entry conditions after dumping steam via the atmospheric steam dumps to cool down the RCS, and to depressurize the RCS by using pressurizer spraylPORVs following a steam generator tube rupture (SGTR) event.

OPRSL1 - Operator identifies the ruptured 0.93 hours0.00108 days 0.0258 hours 1.537698e-4 weeks 3.53865e-5 months lime - 7 5.25E-03 1.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Time - 5 3.63E-03 steam generator, and isolates or verifies closed all flow paths to and from that steam generator, following an SGTR event.

L-05-140 Enclosure 1 Page 28 of 34 Table 3-1: Operator Action Human Error Probabilities l Human Action Description Time PSF - HEP - Time PSF - HEP - post-Available pre-EPU pre-EPU Available post- EPU EPU pre-EPU post-EPU OPRSL2- Operators locally close the steam 11.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Time - 2 4.33E-03 > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Time - 0 3.28E-03 generator steam valves given that these valves cannot be closed remotely during an SGTR accident.

OPRSL3 - Operators locally gag the stuck- 11.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Time - 1 1.35E-01 > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Time -0 1.18E-01 open steam relief valves during an SGTR (Assigned (Assigned event. 1.0) 1.0)

OPRSL4- Operator isolates ruptured steam 0.83 hours9.606481e-4 days 0.0231 hours 1.372354e-4 weeks 3.15815e-5 months Time - 7 3.41E-02 1.22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months Time - 5 2.66E-02 generator given HHSI failed.

(Not used in PRA models)

OPRSL5 - Operator isolates ruptured steam 0.83 hours9.606481e-4 days 0.0231 hours 1.372354e-4 weeks 3.15815e-5 months Time - 8 1.09E-02 1.22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months Time - 6 7.53E-03 generator given one train of emergency AC power and HHSI failed.

(Not used in PRA models)

OPRCD3- Operator depressurizes the 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months Time - 1 1.46E-03 > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Time - 0 1.21 E-03 Reactor Coolant System (RCS) to 400 psig by dumping steam through the intact steam generator atmospheric steam dumps to depressurize and cool down the secondary side (SGTR).

OPRCD4 - Operator depressurizes the 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months Time - 4 1.04E-02 > 24 hours Time - 0 4.99E-03 Reactor Coolant System (RCS) to 400 psig by dumping steam through the steam generator atmospheric steam dumps to depressurize and cool down the secondary side (SGTR, AC Orange power has failed, and operators have to locally manipulate the steam generator atmospheric steam dumps to cool down).

OPRMU1 - Operators provide borated 1.14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months Time -3 5.97E-03 2.58 hours6.712963e-4 days 0.0161 hours 9.589947e-5 weeks 2.2069e-5 months Time - 2 5.45E-03 makeup water to the RWST initially from the spent fuel pool, and in the long term, with makeup from service water following a transient-initiated small LOCA or SGTR.

OPRMU2 - This is the same as OPRMU1 1.01 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Time - 3 5.97E-03 2.58 hours6.712963e-4 days 0.0161 hours 9.589947e-5 weeks 2.2069e-5 months Time - 2 5.45E-03 except that the actions follow a small LOCA event.

OPRMU3 - This is the same as OPRMU1 1.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Time - 7 8.60E-03 2.67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months Time - 5 7.17E-03 except that the actions follow a medium LOCA event.

OPRMU4 -This is the same as OPRMU1 0.54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months Time - 9 1.03E-02 1.11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months Time -7 8.60E-03 except that the actions follow a large LOCA (Assigned (Assigned event. 1.0) - 1.0)

L-05-140 Enclosure 1 Page 29 of 34 Table 3-1: Operator Action Human Error Probabilities Human Action Description Time PSF - HEP - Time PSF - HEP - post-Available pre-EPU pre-EPU Available post- EPU EPU pre-EPU post-EPU OPRPR1 - Operator secures safety injection 15 Time - 9 3.44 E-02 33 minutes Time - 8 2.65E-02 before PORVs are challenged. minutes (Assigned (Assigned I 1.0) 1.0)

OPRCD1 - Operator depressurizes the 5.95 hours0.0011 days 0.0264 hours 1.570767e-4 weeks 3.61475e-5 months Time - 3 9.1OE-04 6.63 hours7.291667e-4 days 0.0175 hours 1.041667e-4 weeks 2.39715e-5 months Time - 1 6.88E-04 Reactor Coolant System (RCS) to 400 psig (was 1.04 by dumping steam through the steam hours due generator atmospheric steam dumps to to CIB depressurize and cool down the secondary setpoint) side (small LOCA).

OPRCD2 - This is the same as OPRCD1 5.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months Time - 3 4.93E-03 11.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Time - 1 3.73E-03 except that AC Orange power has failed and (was 3.62 operators have to locally manipulate the due to CIB steam generator atmospheric steam dumps setpoint) to cool down.

OPRWA1 - Operator manually stops the EDG 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Time - 6 7.93E-02 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Time - 6 7.93E-02 and racks the spare service water (SWS) (was 13 pump onto the bus prior to restarting the EDG minutes during a loss of offsite power. due to RCP seal leakage)

OPRCC1 - Operator starts the manual 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Time - 2 3.31E-03 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Time - 2 3.31E-03 standby component cooling pump (CCP) on (was 13 loss of the operating and the automatic minutes standby CCPs, to restore component cooling due to water (CCW) flow to the RCP thermal RCP seal barriers. leakage)

OPRTB1 - Operator cross-ties station 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Time - 1 7.92E-04 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Time - 1 7.92E-04 instrument air to containment instrument air. (was 13 minutes due to RCP seal leakage)

OPRTB2 - Operator resets containment 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Time - 1 1.12E-02 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Time - 1 1.12E-02 isolation Phase A (CIA) and restores (was 13 containment instrument air. minutes due to RCP seal leakage)

The BVPS-1 and BVPS-2 post-EPU models were requantified using the above realistic operator action HEPs and removing the non-EPU associated modifications. The results from the requantification of the BVPS-1 and BVPS-2 post-EPU PRA models are presented in Tables 3-2 and 3-3, respectively.

L-05-140 Enclosure 1 Page 30 of 34 Table 3-2. BVPS-1 Pre-EPU and Post-EPU Core Damage Frequency Pre-EPU CDF Post-EPU CDF Delta CDF

(/year) (/year) (/year)

Internal 7.45E-06 6.53E-06 -9.15E-07 Events Fire 4.60E-06 4.59E-06 -1.44E-08 External 1.63E-05 1.63E-05 -1.50E-08 Events Total 2.37E-05 2.28E-05 -9.31 E-07 Table 3-3. BVPS-2 Pre-EPU and Post-EPU Core Damage Frequency Pre-EPU CDF Post-EPU CDF . Delta CDF

(/year) (/year) (/year)

Internal 2.01 E-05 2.01 E-05 -6.OOE-09 Events Fire 5.29E-06 5.29E-06 -1.20E-09 External 1.48E-05 1.48E-05 -2.00E-09 Events Total 3.49E-05 3.49E-05 -8.OOE-09 In many instances, the best-estimate HEPs improved (the HEP decreased) as a result of the new analyses using MAAP results versus hand calculations. As a result, the BVPS-1 and BVPS-2 post-EPU PRA models indicate a decrease or no change in CDF, as shown above in Tables 3-2 and 3-3. The HEPs did not impact the BVPS-1 and BVPS-2 LERF values. Therefore, LERF remains as reported in Section 10.16 of Reference 2.

In addition to the change in timing of the RCP seal binding failure affecting some of the above reanalyzed HEPs, the post-EPU station blackout (SBO) MAAP analyses also assumed that the start of the increased RCP seal leakage started at 13 minutes, as opposed to the 30 minutes used in the pre-EPU MAAP analyses (based on WCAP-15603, Revision 0). The time to core damage from these pre- and post-EPU SBO MAAP analyses were used in the electric power recovery models.

For the pre-EPU SBO MAAP analyses, the impact of the change in the onset of the increased seal LOCA from 30 minutes to 13 minutes on the time to core damage was evaluated to assess the NRC concerns in approving WCAP-15603, Revision 1A. The results of this sensitivity assessment did not lead to any significant changes in the time to core damage. Thus, it was concluded that the time to core damage provided in the current, pre-EPU seal LOCA sequences, using the 30-minute timing, was sufficient to access the electric power recovery models.

L-05-140 Enclosure 1 Page 31 of 34 The impact of this change on the post-EPU PRA model was also assessed by performing sensitivity analyses. For the post-EPU SBO MAAP sensitivity analyses, the onset of the increased seal LOCA changed from 13 minutes back to 30 minutes. The results of this sensitivity assessment did not lead to any significant changes in the time to core damage.

Thus, it was concluded, over the spectrum of seal binding failure sizes, that the core damage timing difference between the pre-EPU and EPU models is due largely to the EPU design changes and not the start of the increased RCP seal leakage.

Moreover, there is an insignificant impact on CDF from the non-electric power recovery split fractions developed using the electric power recovery model whose time to core damage decreased by more than one minute from the change in timing of the RCP seal binding failure. All of these split fractions had Fussell-Vesely importance values less than 2E-04 and risk achievement worths less than 1.01. This shows that the impact of the time change in the RCP seal binding failure from 13 minutes to 30 minutes, or vice versa, on CDF is insignificant. Additionally, since over 99% of the LERF contribution is attributed to interfacing system LOCAs and SGTRs, the impact of this timing change on LERF is also expected to be insignificant.

Question

5. What is the expected impact of EPU on the probability of consequential loss of offsite power (LOOP)? For each unit, provide the contribution to the total CDF from consequential LOOP events in the current model. Provide the same information for operation at EPU conditions, or provide a sensitivity analysis showing how CDF would change assuming the probability of consequential LOOP increases after EPU.

Response

The probability of a consequential LOOP is 2.66E-04 at both BVPS-1 and BVPS-2, and is not expected to be impacted by the EPU.

Studies were performed to evaluate the impact of BVPS EPU operation on the transmission system grid stability. The results of these studies yield generally comparable results to that obtained from the previous pre-EPU study. In addition, the 345 kV and 138 kV switchyards were also evaluated. This evaluation concluded equipment and components associated with the 345 kV and 138 kV overhead lines between the station and the switchyards are adequate under EPU conditions. The equipment and components in the 345 kV and 138 kV switchyards are also adequate under EPU conditions. As such, the plant response following a unit trip will be essentially the same following the EPU as it currently is modeled.

The contribution to the total CDF from consequential LOOP events for the current PRA models and EPU PRA models for both BVPS-1 and BVPS-2 are provided below:

BVPS-1:

Current PRA model = 2.62E-03 (0.26%)

EPU PRA model = 1.95E-03 (0.20%)

L-05-140 Enclosure I Page 32 of 34 BVPS-2:

Current PRA model = 1.22E-02 (1.22%)

EPU PRA model = 1.25E-02 (1.25%)

The slight decrease in the consequential LOOP contribution to the total CDF at BVPS-1 is attributed to the reduction in CDF due to the steam generator replacement, since there were several SGTR sequences involving consequential LOOPs. The consequential LOOP contributions to the total CDF at BVPS-2 remains essentially the same for both the current pre-EPU and post-EPU conditions.

Question

6. The PRA results in the EPU risk assessment (Reference 2) were compared with those provided in a response to the NRC staff's questions on a recent license amendment request for extending the emergency diesel generator (EDG) allowed outage time (AOT) (Reference 3). The table below compares the Information.

EDG AOT (Ref. 3) EPU (Ref. 2)

Beaver Valley Unit I PRA Model Designator BVI REV3 BVI REV3 Date Updated 912003 9/2003 CDF (per year) 2.34E-5 7.45E-6 LERF (per year) 1.03E-6 1.03E-6 Beaver Valley Unit 2 PRA Model Designator BV2 REV3B BV2 REV3D Date Updated 512003 5/2003 CDF (per year) 3.27E-5 2.01 E-5 LERF (per year) 1.12E-6 1.12E-6 Question

a. What has changed in the BVPS-1 and BVPS-2 PRA models since the Reference 3 letter?

Response

The BVPS-1 and BVPS-2 baseline PRA models used in the EDG AOT analyses are the same as the BVPS-1 and BVPS-2 baseline PRA models used in the EPU analyses.

There were some changes associated with the EDG AOT PRA models for Case 1,which were noted in LAR 306 and 176, L-04-072 (dated May 26, 2004), Section 4.3.2, Page 15.

These consisted of the following:

L-05-140 Enclosure 1 Page 33 of 34 "Case 1 modeled the current EDG unavailability. This sensitivity case was run by changing the EDG unavailability from 2.5%, which is the current value used in the BVPS-1 and BVPS-2 baseline PRA models, to the present mean unavailability of the EDG under the current AOT or 0.77% (Unit 1) and 0.348% (Unit 2)."

The EPU baseline PRA models used the 2.5% EDG unavailability value. Additionally, the EPU PRA model include all of the modifications identified in Section 10.16.1.6 of L-05-104 Enclosure 1 (page 17 of 32). It should also be noted that BV2REV3B is the current model revision of record at BVPS-2; however, BV2REV3D was used in both the EDG AOT and EPU analyses, which removed common cause failures from the 4KV transformers.

Question

b. Explain why BVPS-1 CDF has dropped significantly and BVPS-2 CDF has dropped somewhat compared to the Reference 3 values.

Response

The EPU CDF values in the comparison table provided with this RAI question are incorrect.

As stated in Section 10.16.1.6 of L-05-104 Enclosure 1 (page 18 of 32), "...the effect of the BVPS-1 EPU was to decrease the internal events CDF from 7.45E-06 per year to 6.85E-06 per year. This section also states that "...the effect of the BVPS-2 EPU was to increase the internal events CDF from 2.01 E-05 per year to 2.02E-05 per year..."

Moreover, the EPU CDF values provided in the comparison table are based on point estimate values and only include the core damage frequency associated with internal initiating events. The EDG AOT CDF values provided in the comparison table represents the total core damage frequency, including both internal and external initiating events.

Using the PRA baseline models and the information provided in Reference 3 for Case 1 (Tables 5 and 9 for BVPS-1 and BVPS-2, respectively), a better breakdown comparison between the Baseline PRA CDF, EDG AOT CDF, and EPU CDF are provided in Tables 6-1 and 6-2:

Table 6-1. BVPS-1 l BASELINE PRA EDG AOT EPU (Ref. 2)

MODELS (Ref. 3) ________._)

Internal Events 7.45E-06 7.13E-06 6.85E-06 CDF Fire CDF 4.60E-06 4.69E-06 4.61 E-06 Seismic CDF 1.17E-05 1.17E-05 1.17E-05 Total CDF 2.37E-05 2.35E-05 2.31 E-05

L-0-14Enlsr L-05-140 Enclosure 1 Page 34 of 34

[ Table 6-2. BVPS-2 BASELINE PRA EDG AOT EPU (Ref. 2)

__ _ MODELS

_ _ _ (Ref. 3) l ___(ef_2 _

Internal Events 2.01 E-05 1.86E-05 2.02E-05 CDF Fire CDF 5.29E-06 4.71 E-06 5.30E-06 Seismic CDF 9.54E-06 9.58E-06 9.54E-06 Total CDF 3.49E-05 3.29E-05 3.51 E-05 Based on the above tables, the reduction in BVPS-1 total EPU CDF is insignificant when compared to the total AOT CDF, and is mostly attributed to the reduction in the SGTR initiating event frequency.

It should also be mentioned that Reference 3, Case 1 modeled the current EDG unavailability, as opposed to the baseline PRA model unavailability of 2.5%. This sensitivity case was run by changing the EDG unavailability from 2.5%, to the present mean unavailability of the EDG under the current AOT or 0.77% (BVPS-1) and 0.348%

(BVPS-2). These changes in EDG unavailability account for the differences in the internal events CDF as stated in Section 10.16.1.6 of L-05-104 Enclosure 1 (7.13E-06 vs. 7.45E-06 for BVPS-1, and 1.86E-05 vs. 2.01 E-05 for BVPS-2).

REFERENCES:

1. Letter from L. William Pearce, FirstEnergy Nuclear Operating Company, to U.S.

Nuclear Regulatory Commission, "Beaver Valley Power Station, Unit No. I and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412.

License No. NPF-73 License Amendment Request Nos. 302 and 173," L-04-125, October 4, 2004. (ADAMS Accession No. ML042920300)

2. Letter from L. William Pearce, FirstEnergy Nuclear Operating Company, to U.S.

Nuclear Regulatory Commission, "Beaver Valley Power Station, Unit Nos. I and 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No.

NPF-73 Probabilistic Safety Review for License Amendment Request Nos. 302 and 173," L-05-104, June 14, 2005. (ADAMS Accession No. ML051670270)

3. Letter from L. William Pearce, FirstEnergy Nuclear Operating Company, to U.S.

Nuclear Regulatory Commission, "Beaver Valley Power Station, Unit No. I and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Response to Request for Additional Information in Support of LAR Nos. 306 and 176 Emergency Diesel Generator Allowed Outage Time Extension," L-04-141, October 29, 2004. (ADAMS Accession No. ML043070444)

L-05-140 Enclosure 1, Attachmen6t 1 Page 1 of 16 Attachment 1 to RAI 2.a.

BVPS-1 Pre-EPU SLIM Worksheets

L-05-140 Enclosure 1, Attachment 1 Page 2 of 16 BEAVER VALLEY UNIT I - GROUP I HUMAN ACTIONS EVALUATION P0RFCFMAWNCESHAPINGFACTOR5 Pt RFCRMANCESHAPINGFACTCRS C P C P t P 0 R I P 0 R N R M 0 T N R M 0 T T E P C R T E P C R E C L E A S E C L E A S R E E 0 I T R E E D I T F D X U N T R F D X U N T R A I I R I I E S A I I R I I E M C N T E N M S U C N T E N M S U E G Y S a E S M E a Y S G E 5 U INPUTTORISKMANFcR NormPSFVP1thts 0.13 o03 0.13 0.31 0.13 006 0.13 1.00 MRSTRI IBfLON 13'ERATORACTnQNS PSFRANKINGS FU HER Lt.CG(H81) OPERATCRACrtPNS PSF VEIGHTS RANGEFACT0R MEOIAN tO tO la 10 1t 10 10 10 9.93E01 .00008 McOM 5 5 S 3 5 2 5 4.18t 2.01E-03 -2.6970 2HEDR1 0 0 0 S 0 0 0 7.5 9.49604 a 2 9 2 a S a 5.063 5.12E-03 .2.2911 ZHWD3 5 S S t0 S 5 5 40 7.5 2.42603 8 4 6 5 a I S 5.25 6.25E-03 -2.2042 2EMU5 S S S t0 S 0 S 35 7.5 2.95603 MINAHR 0 0 0 0 0 0 0 0 2.29605 -4.6394 NYMAtUZ PSF 0.13 0.13 0.13 0.31 0.13 006 0.13 VG1TS CAUSIRA1INTASKS PSFRANKINGS FU tHR LOW6HER)

MAXHER 10 10 la 10 10 10 1t 10 1.00E00 0.0000 DC24ERF1(1) 5 5 5 3 S 2 4.188 2.00E03 -2.6990 MIN"RE 0 0 0 0 0 0 0 0 239E.05 0 4.6tM NOTE Rogreson Qjt put:

Cor6t.d .4 63941 (I RANKINGSARElTHSEFCR SIMILAR StdErrotYE 0 002418 ACTCNINSV1(ZHBRI) RSquared 0 999999 No.o servatlone tr 3 Degruvotffhedorn XCodfnd nt() 0.4630592 Stdi6ro Coa. 0.0003404 Figure 1: BVPS-1 Pre-EPU SLIM Worksheet Group I

L-05-140 Enclosure 1, Attachment 1 Page 3 of 16 BEAVER VALLEY UNIT I - GROUP 2 HUMAN ACTIONS EVALUATION PERFCRUANCESHAPINGFACTCRS PERFCRAMANC0ESHAPINOFACTCRS C P C P I P 0 R I P 0 R N R U 0 T N R U 0 T T E P C R T E P C R E C E E A S E C L E A s R E E D I T R E E D 1 T F 0 X U N T Ft F 0 X U N T R A I I R I I E S A I I R I I E C N T E N U S U C N T E N U S LU Uu E a Y S 0 E 8 U E 0 Y S a E S IWuTTORMsKMANFCI NomPSFVi9gI 00o 000 0.33 0.33 o 00 0 0 050 too HERDISTRIBUTICN OPERA~T0RACTI045 PSFRANKNMS FU HER LOG(HER) 10PI0ATCRACTIONS P5F rMoHTS RANGEFACTCR MEDIAN MAXMER 10 10 10 10 10 10 10 10 . 9 99S01 -00003 a 5 8 5 2 1 4 6.583 0.405-03 -2 0757 0 a 5 5 0 0 0 10 7.5 307E-03 D4OMU2 S e S s 2 3 4 5.75 t010-02 .1 074 0 0 5 5 0 0 0 10 5 6 23-03 ZHECR2 7 7 a 3 5 2 S 4 583 2 SE-03 .2 s45s Z510R2 0 0 5 5 0 0 0 10 7.s 134E-03 a 5 a 5 2 1 4 5 503 ; 8 40S03 . 0757 DIEMIA 0 0 5 5 0 0 0 10 7.5 3 7"03 7 1 7 5 3 3 S 5.333 6 4103 21032 ZNeO0 5 0 10 10 5 5 5 40 75 303E-03 7 1 7 5 3 5 5 s0e7 o19&03 .20345 Di0=2 5 0 10 10 5 5 5 40 7.5 4 34-03 UJNHIER 0 0 0 0 0 0 0 0 2D0&000 .4 03 NORMALUZPSF 008 000 033 033 008 008 005 COGHTS CALISRATIONTASKS PStRANKINOS FUI HER LOOtHER)

UAXHM 10 10 10 10 10 10 10 1o 100E.00 00000 PLANT.XCFBP0I(1) 7 1 7 5 3 3 3 5333 6 40r,03 .2.*103 MtNHE 0 0 0 0 0 0 0 0 2000-05 -4000 NOTE2

.4 MT7

(?) RANKINGSARETHOOEEIIRSIMILAR StdE,rofYEd 0 000789 ACTlION0NSVI(bl0GS) ftSq...4 No of Ob--fl00 13 D~g'...oIFr.dom XCo.0tlef."'.(s) 0.4800007 Std~rref Coo. 0 0001115 Figure 2: BVPS-1 Pre-EPU SLIM Worksheet Group 2

L-05-140 Enclosure 1, Attachment I Page 4 of 16 BEAVER VALLEY UNIT 1 - GROUP 3 HUMAN ACTIONS EVALUATION PERFCRMANCESHAPINGFACTCRS PERFORMANCESHAPINGFACTOQS C P C P I P 0 R N R u 0 T N R u 0 T T E P C T E P C R E C L E E C L E A S R E E 0 T3 R E E 0 I T F D X U N T R F D X U N T R A I I R I E A I I R I I E C N T E N u S u C N T E N u a S U

E a r S Ct E S E a Y S 0 E S NPLITTORISKMANFCR NowmPSFWqiM4* 0.o2 0.t2 0.10 010 0 07 0 24 0 24 100 HERDtSThSUnON OPERATCRACTKINS PSFRANKIN FLI HER LCCIHeR) OPERATCRACTONS PSFVYEHT0 RANGFACTCR MEDLAN MAXHER 10 10 10 10 10 10 10 10 9 30t01 -00285 ZHECO2 2 a a 5 7 2 4 4 241 2 503 -2 s0e8 5 S S S s 10 10 45 7S 1228-03 ZHDNt 2

2 2 4 6 a 3 48 8 1-03 -+/-7300 S S s S S 10 10 45 78 9 02804 ZHEREe 1 2 S 9

7 7 o 121 1 77r02 -17538 ZHERMl 5 5 5 5 5 10 10 S 100002 ZHEFLt 7 7 0 9

S a 7 245 .18e-02 42008 5 5 s S 0 10 10 40 S 388302 ZHEPLt DiEuL2 7 7 9 9 a a a 7.103 4 3E-02 .13212 S S S S 0 ID 10 40 S Z0sE-02 ZHEFL3 7 7 9 9 a S 0 7 102 4 83802 .t3102 ZHEOU 5 5 0 5 0 10 10 40 5 209902 ZHE4C3 a 9 S 2

e a 6 S4S 3 70802 -14312 ZHe3C2 5 5 0 0 5 l0 10 21 0 +/-30S-02 MINHER 0 0 0 0 0 0 0 0 3 32E00 .4 4742 NORVALeEDPSF 02 0t. 010 0.1 007 024 024 MGMT CALtBRATICNTASKS PSFRAN0K84NS FI HEQ LOG HER)

MAXHER 10 10 10 10 to 10 10 10 t1E000 0 0000 STPHEOS01 4 2 a 10 10 a 2 5 322 1 0E-02 .17447 FERMIQE7 a 7 a a a 5 0 0 089 U2202 -18794 u INHER 0 0 0 0 0 0 0 0 3 00-00 -4 522 Roomm"o08pI*

COont -4 47420 StdErofYEt 0338130 Rt~qwond No 8Obwvsioms 4 Ogn.of FrAodo- 2 XC..fftlelI(s) 0444575 StdE,r.fC"o. 00470447 Figure 3: BVPS-1 Pre-EPU SLIM Worksheet Group 3

L-05-140 Enclosure 1, Attachment 1 Page 5 of 16 BEAVER VALLEY UNIT I - GROUP 4 HUMAN ACTIONS EVALUATION PFRFCRMANCEtSAPINMFACTCRS PBRFCRMAANCESHAPINGFACTORS C P C P I P 0 R I P 0 R N R u 0 T N R M 0 T T E P C R T E P C R E C L E A S E C L E A S R E E 0 I T R E E D I T F 0 X U N T It F D X U N T R A I I R I I E A I I R I I E S C N T E N u S U C N T E N M s U E 0 y S a E S u E G Y J G E a u INPUTTORtSKMANFCR NrmwPSFights 013 0.11 e3 0n OI 013 0.11 030 100 KMIOISTRhUT0N cPSRATeRACTI(IS PSFRAWNKNG FU MM LOG(HER) PERATORACTIONS PSFHEKHTS RANCEFACTOR MEDLAN MAX4R 10 10 10 10 10 10 10 10 s1$5E01 -0 0387 2 1 2 2 4 0 5 2 83 2.56E-04 -30885 tHEHC1 0 0 0 0 0 0 6 10 9060-05 ZHKPRI 2 2 2 2 3 0 6 3.1J0 3 53E04 J 4541 0 0 0 0 0 0 0 40 10 t33C-04 D410-I

2 9 a

5 10 7.t04 a 29-02 .10o10 0 6 0 0 0 0 10 6 51UE-02 40 ZfflU3

6 8 5 6 5 a e 553 1 OE-02 -t7451 DHEMU3 6 0 0 0 0 0 10 0 t11002 a 6 6 5 a 7 6 7.302 4 52E-02 .13449 DIEW4 6 0 0 0 0 0 10 40 0 2 We002 ZHAU4t 2 6 3 2 4 1 7 4.1S1 122E-03 -2 144 ZDMl 6 6 0 0 0 0 10 7.5 s 7$E-04 2 0 2 0 2 2 7 1S1 3w0E-04 -34065 DiA1 6 6 0 0 6 0 10 10 1406-04 D4WT1 0 10 1 2 3 1 6 3601 66E0-04 -3 1072 ZHEOTI 6 0 0 0 5 0 ID 30 10 2 S5E04 MIN140 0 0 0 0 0 0 0 0 102E-05 .4 960S NORUAtUEDPSF 0.13 61 6t013 Oil1 01is 0.11 0.30 V4GITS CALI9RATIONTASKS PSFRANKN4GS FU HER L0CPERJ MAXHMR 10 10 10 10 10 10 tO 10 I OOE-00 0w000 STPHERC4 2 6 3 0 6 I 6 4 661 9 s2E04 .3 0079 FERMIHEMT3 4 a 3 3 3 S 3 3.447 1,151-03 -26393 MINHER 0 0 0 0 0 0 0 0 9 20e-os - 0362 R9,g.W."OOp:

CtganI .4 sssS4 SldErf olIYE 0.42486 RSqfwrd 0 901802 ND olfO wM44s 4 D0.grnolFr.4m 2 XCoeffIchle(s) 04s08057 St d Err ofCD . 0 0475508 Figure 4: BVPS-1 Pre-EPU SLIM Worksheet Group 4

L-05-140 Enclosure 1, Attachment I Page 6 of 16 BEAVER VALLEY UNIT I - GROUP 5 HUMAN ACTIONS EVALUATION PEWFORMANCESWWPINOVACTCRS PERFORM11E5HAPINOSACTORS C P C P I P O a I P 0 R N R N 0 T N R 0 T T E P C R T E P C R E C L E A E C L C A R E E 0 I R E E 0 I I7 F D X U N 7 ft F 0 X U N T ft A I I R I 9 A I I ft I I C N T I N U C N T Ct ft U N U E 0 Y S a ft P ft 9 E a Y

0 E hPUrT~ORISKrANFOR 8..P6FVW4. OIS a's aa aA a all 1 a.O H1ROSTR15UTION OPERATORACTION5 PSFRANKSNO FU HER LOOHEM OPERATORACTIO50 PSF VEIGHTS5 RANOSfACTOR MENAN IlAXHFtR 10 ID 10 10 10 10 10 10 957501 .00012 ZHECC1 2 5 8 7 2 2 5 4 27 421503 .13751 2HECCI 5 5 5 5 5 5 25 75 MG1M3 2 4 7 7 2 4 6 4803 592 203 .11597 ZHECC2 DeC= 5

5

5 9 25 79 3 27E-03 ZHE=2 1 2 4 I 2403 22.04 .32041 5 * *

5 5f 10 2 345.04 ZHEHH 25 i 7 S S 2 4 6 422M 365-03 .2 AM T75 1 25-.03 2HEHH2 Of * *

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5 5 9 6 5 25 78 506104 3 *64 1S5.03 2"01911 5 5 5 5 5 5 2 3 f 2 .21O7 75 747E-04 ZHEOC1 5

5 5 9 5 31 ZHEPKI O 0 1 5 3 2 5 1279 5052E04 .32U2 e0 207-04 ZHEPII Of * * *

5 3 2 5 2429 381604 .3 032 ZHEP0r 25 10 240604 DMRl 8 9 5 0 5 8 9 1 2 S S

2 5 5255 OOr02 .199al 25 5 *2S203 ZHERE5 5 5 5 5 4 5 2 2

5

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2 5 5 0 5 4 57 0 24C 0. .2 2803 5 5 5 5 9f O MH2AI 25 75 2 45-03 ZHECFI N I 5 2 3594 285103 .25515 5

0 5 5 O 5 25 7T t33-03 ZHEIA 4A705 04003 .2 2337 5 * *

5 0 30 7T5 27E103 ZHEUU 4 4 5 4 4 I S 425 175603 .2227 DIDA2 25 75 1795-03 4 1 3t 7 7 4 3 4 I 2 4422 4420. -23142 ZHEIA4 5 * *

5 0 0 79 2010.03 ZHEOS5 2 4 2 5 2 0 2 2617 91104 .3 091 5

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0 0f 0 25 2HEPNA 8 5 N 9 8 7 9 8231 1975.01 .0 700 ZHEPNA 3 t0604 35 1641651 o 0 a 0 50305 .4 211 NOR2A015PBF o0a 015 0oa 0o 015 o0 014 MO4M5 CALIVRAT11NTASKS PSFRAUXNGS FU HER toa(5mm MAXHER 10 10 l0 10 10 tO 10 10 3 O1E-04 a0000 MIPM=oo 6 5 I 6 5 6 9 6975 423-02 .3060 STPHEOML5 2 4 5 2 2 4 4 3067 213-03 .2074 STPHEOO01 3 3 6 4 4 2 4 277 231503 .2E364 MINHER 0 0 0 0 0 0 0 06 5.W04 .-432

.42165 Sld&, dYE4 0098 RtS4-'s N C..454b -1 i . - 997053 4 03 5 R.g ... dF.. d XileNdw~(* 0 42Y1417 Fu45,dcB.V . 00 S W e Figure 5: BVPS-1 Pre-EPU SLIM Worksheet Group 5

L-05-140 Enclosure 1, Attachment 1 Page 7 of 16 BEAVER VAALLEY UNIT I - GROUP 6 HUMAN ACTIONS EVALUATION PE9FORMANCESHAPINGFACTCRS P00FCRMANCESNAPGFACTMS C P C P I P 0 R I P 0 R N R U 0 T N R U 0 T T E P C R T E P C R E C L E A S E C L E A S R E E D I T R E E D I T f 0 X U N T R F 0 X U N T R A I I R I I E S A I I R I I E S C N T E N U S U C N T E N U S U E 0 Y S E S U E a r s a E S U INPUTTORiSKUANFKR NornmPSFN0b4, c00 000 000 000 000 00 O000 t00 HE 0 ISTRUBITON OPE6RATCAC1a"S PSFRANKINGS FLI HR LOCItER) OPERATrRACTI1NS PSF VICGHTS RANOEFACTOR MUiAN UMAMER la 1a la iO to tO io tO 909i01 -00007 ZHESLI 0 6 e

3 3 5 45 3 3000 .1247tS 2HESL1 0 5 0 0 0 5 0 75 tSo&0O ZHETI 4 5 2 5 3 7 5 5 t 59002 .17967 ZHETI 0 5 0 0 0 5 0 5 9 87003 MINHER 0 0 0 0 0 0 0 0 321S0-0 .44930 NCRUALeEDPSF 000 050 000 000 000 050 000 VAESGKTS CALIBRAAICNTASKS PSFRANKNiPS FU HER LOIHER)

UMAXhER 10 0 0 iO iO 10 0o i0 100.0 0000 STP HMEDLI 3 4 5 3 3 4 a 4 2.is3E .26e71 DMRX4(l) a 6 a 5 3 3 5 45 3 200.03 .24049 MINHE 0 0 0 0 0 0 0 O 3 20005 .4 *949 NOTe R,g.mo.0ndpW:

Co.,0wn .4 49301 1RANKXMARETHSWEPORSIUILAR

(/ S1d ErrotYES 0 02329 AC1ICNINSV1(DIESLI) RSqrwtd 0 metsa No olCtoruallooo 4 D.g.ooofFrooem 2 XCoeftliehs.() 0 4492201 SIdErrofCoeo. 0 003357 Figure 6: BVPS-1 Pre-EPU SLIM Worksheet Group 6

L-05-140 Enclosure 1, Attachment 1 Page 8 of 16 BI IEAVER VALLEY UNIT I - GROUP 7 HUMAN ACTIONS EVALUATION PERFORMANCESRAPiNGFACTCRS P0RFC0WANCESiAPiNGFACTCRS C P C P I P 0 R I P 0 R N R U 0 T N R U 0 T T E P C R T E P C R E C L E A S E C L E A S R E E D I T R E E 0 I T F D X U N T R F D X U N T R A I I R I I E S A I I R I I E S C N T E N M 5 U C N T E N U S U E a Y 8 G 6 S US E 0 Y 5 0 E S U INPUTTORISKMANFCR Nown PSFY*Igtvs 010 025 0.10 0.10 0.10 010 025 tOO ERDiSTmiGU1iON OPERATORACTIONS PSFRANKNGS FU ilER LO00lR) CPERATCRACTiCNS PSFVYEKGfTS RANCEFACTCR MEDIAN MAXH00 10 10 10 10 10 10 10 10 909-01 .0 0005 7ZECI1 2 5 3 3 5 2 3 35 2 230-03 2 0512 2HEC11 0 5 0 0 0 0 5 10 75 t15F-03 715000 I 6 S 5 7 2 S 00 t040-02 .1703 2HECD5 5 10 5 5 5 5 10 '5 5 120-02 84E002 2 9 3 2 4 I a 545 t3°F02 .10000 ZDEM2 5 10 5 5 5 5 10 45 5 8*

4303 MINHER 0 0 0 0 0 0 0 0 5 3SF-05 .4 0t0i NORIALU2PSF 0.10 025 0.10 010 010 010 025 vTS3 CALIERATIONTASKS PSFRANSiNGS FU iRER LO(lHMR)

MAXHER 10 10 10 tO 10 10 10 1O 1000.00 00000 STPHE i002 4 3 a 4 7 2 8 0 05 a 0E0-03 -20555 OPRA.5(1) 2 9 3 2 4 I a 5045 1 E-02 .20W0 DCz42EBt 5 7 7 6 a 4 a *55 5 49-02 .12004 MiN RER 0 0 0 0 0 a 0 0 9 WF-05 .4 0458 NOTE Req.0on.0,ApA:

Co.A km .407055 (1)RANKNGSME lROSEFOR SWiLAR StdDro YEst ACTIMNSVI(78E4082) RSqauw.d 0 09483 Ne ofObwvstloos I D.7g..sof Fr"doo XCoofficit.t(s) 040750V StdErroCof. 0 0150732 Figure 7: BVPS-1 Pre-EPU SLIM Worksheet Group 7

L-05-140 Enclosure 1, Attachment 1 Page 9 of 16 BEAVER VALLEY UNIT I - GROUP 8 HUMAN ACTIONS EVALUATION PERFOCRMANCESHAPINGFACTC61S PER1C6MMANCESHAPINGFACTCRS C P C P I P 0 R I P 0 R N R H 0 T N R U 0 T T E P C R T E P C R E C L E A E C L E A S R E E D R E E 0 I T F 0 X U N T R F 0 X U N T R A I I R I I E A I I R I I E S C N T E N E S U C N T E N U S U E a Y S a E S E a Y S 0 E S U INPUT'TORISKbANFCR Norm PSF*19Ms 0.13 0.13 o01o 010 o0I 031 011 100 HERDIS7RSUICO CPERATCRACTfONS PSFRANKENGS FU MER LO1HER) OPERATCRACTIaNS PSF V6IGT RANC2FACTC MEDMAN MAXHER 10 10 10 10 10 10 10 10 6 066.01 -0o001 2 3 3 5 7 4 3 2671 234-03 .2 0305 ZHEFL4 00 0 0 0 0 0 7.5 1 1003 HErT2 4 3 2 3 3 5 3 2 657 17S105 .2 7075 ZHET12 0 0o 0 o 5 0 10 7.5 6 076E04 ZHEVA2 a a a 7 7 7 s 64'A 2720-2 .15053 ZHEWA2 00 0 0 0 10 0 5 1 6sE002 3 3 3 4 T 2 2 3126 1006-0S -2see ZHSEV2 31 7.5 4 741-04 ZHESW 264EV3 5 7 7 0

6 6 7.71 7.11-02 .A79 5 4 41602 ZHESW 6 a 3 4 7 6 5 5057 676023 -2.171 26IESV4 5 5 5 s 10s 5 7.5 3 26E-03 Z"=1 2 5 0 3 0 2 4 2 607 171-03 *2 7675 ZHEMIl 0 5 0 0 0 10 5 40 7.0 6 07-04 ZMECT 2 a 6 7 2 6 0 5014 06e76.0 .21706 ZHECTI O 0 0 0 0 10 5 40 7.5 316-03 ZH46A3 0 0 a 4 4 10 5 671U 366.02 .4245 Z4HEA3 0 5 0 6 0 10 5 40 6 2 206.02 ZHE211 1 0 1 0 0 5 7 2 6 0 16-04 -32285 ZHER11 5 6 5 0 00 0 0s 10 s 5 10 2 22E.04 aamc2 2 0 4 s 4 5 4 4 21 2 09E-03 -20246 2EIC2 s 5 0 6 0 10 5 30 7.5 1600 ZHEICI a 7 a 2 a 2 3 4 129 2 746.02 *2.520 ZHEIC1 20 7.s 12tCE03 UINHER o o 0 0 0 0 0 0 42 4E.05 .43022 N130MAWMPSF 0.13 0.13 010 010 0.11 0.31 011 VOCHM CALIBRAMCNTASKS PSFRANKINGS FU HER LCqHER)

MAXHER 10 10 10 10 10 10 10 10 1 00E.00 0 0000 FERMIHERS 2 7 2 3 2 4 3 829 1750-03 .2.7570 SnP HKOM01 4 3 a 1o 10 6 0 071 1 *OE.02 .17447 H INHER 0 0 0 0 0 0 0 0 4 60E605 -4 372 Regol"WO"Mpit:

Co..l .4.32210 Stdb4i*MYE RSquo.vd 0 090309 No of CbwvUIo1" D9geq... Fr.dom 2 XC.o.? icIek(s) 043004 SdbEfoICooI. 00081103 Figure 8: BVPS-1 Pre-EPU SLIM Worksheet Group 8

L-05-140 Enclosure 1, Attachment 1 Page 10 of 16 BEAVER VW'LLEY UNIT I . GROUP 9 HUMAN ACTIONS EVALUATION PERFCRMANCE SHAPINGFACTORS PERFORMANCESHAPINGFACTORS C P C P I P o R I P O R N R U 0 T N R U 0 T T E P C R T E P C R E C L E A S E C L E A S R E E D I T R E E 0 I T F 0 X U N T A F 0 X U N T R A I I R I I E S A I I R I I E S C N T E N 84 S U C N T E N M S U8 E a Y S 0 E S u E 0 Y S G E S U INPUTTORtSKMANFOR NormPSFW8igI 000 017 017 017 017 017 017 100 HERDISTRIBUTDN OPERATORACT)"S PSFRANKNGS FLI HER L(x0HER) MPERATCRACTIONS PSF WEIGHTS RANrEFACT3R MbEIAN MAXHER 10 10 to 10 10 1O 10 10 9s8E-0 -0W08 ZHEC0C 2 9 5 3 7 3 9 o 4 96002 .13022 2HMD5 0 5 5 5 5 5 5 30 5 3 09002 2HEC07 2 9 a 5 S 5 9 7.339 t31001 .0 8004 230007 0 5 5 5 0 5 5 20 3 1 08E01 MtNHER 0 0 0 0 0 0 0 0 5 570-4 . 2242 NORMALOMPSF 0 00 0.17 0.17 0.17 017 017 017 VYAX1TS CALIBRATICNTASKS PSFRANW4nS FLI HER LO(HER)

MAXHER 10 10 10 10 10 10 10 10 1000E00 0.0WO SP HED03 6 5 S e e 6 9 e0e7 4.<10-02 .4580 EPRISHI(I) 2 9 5 3 7 3 9 e 0OO-O1 .10000 MINHER 0 0 a 0 0 0 0 0 S20E-04 -3 240 NOlE nlRConi kpW

.32042 r) RANKPM ARETHOSEFORSIMILAR StdErtoIYEg 0 288942 ACn0N0IN8V1(ZNECD6) RSquvred 0 970575 No. ofrb rmrto1 4 Degmrano Fr..dom 2 XCoetfleInt(s) 0.32o3357 StdErrotCow.f 0 0400552 Figure 9: BVPS-1 Pre-EPU SLIM Worksheet Group 9

L-05-140 Enclosure 1, Attachment 1 Page 11 of 16 BEAVER VALLEY UNIT 1 - GROUP 10 HUMAN ACTIONS EVALUATION PERFCOMANCESHAPiNGFACTCRI t PERfCRMANCESHAPWOFACTCRS C P

C P I P 0 R I P O R N R M 0 T N R M 0 T T E P C R T E P C R E C L E IA S E C

E A S R E E 0 I T R E E D I T F 0 X U N T R F D X U N I R A I I R I I E S A I I R I I E S C N T E N U S U C N T E N M S U E a Y S O E S U 11 Y S a E S U INPUTTORISKUANFCR Now.P8FVWlghts 0.1 0o00 022 022 1on1 022 0.e1 100 HERDiSTR81111M OPERATCRACTK)NS PSFRANKNGS FU RER LOCGlER) CPERATCRACTK1NS PSF 'AEKWS RAiNCEFACTOR MEDIAN MAXHER 10 10 10 10 10 10 10 10 9 99001 -0 0006 ZDEOS3 7 1 7 5 3 6 6 5.778 277E-02 .15575 0HW3S0 5 10 10 5 10 5 40 5 *72002 ZHEM4 7 1 7 5 3 6 a 444 4 88E-02 .0120 DZEOS4 5 0 10 10 5 10 5 45 5 02E-02 M1N8ER 0 0 0 a 0 0 0 0 2 00E-04 .S es8 NORMAL2EDPSF OIl 000 022 0.22 0.11 022 Oil VAGHTS CALIORATINTASKS PSFRANKFIGS FU -HER LOGOHER)

MAXKER 10 10 10 10 10 10 10 to tO00OO 0onoo STPHECR07 5 4 7 4 6 5 a 5 444 2 00E-02 .06e5 MWNHER 0 0 0 0 0 0 0 0 2 05E-04 . 882 Rt0on*W OapiA:

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D.g.o.odFrodom XCo.filI.n(,s) 0 3001144 StdErofCo-. 00800S9 Figure 10: BVPS-1 Pre-EPU SLIM Worksheet Group 10

L-05-140 Enclosure 1, Attachment 1 Page 12 of 16 BEAVER VALLEY UNIT I . GROUP 11 HUMAN ACTIONS EVALUATION PERFcRMANCESHAPNGFACTORS PERFCRIANCESHAPNGFACTCRS C P C P I P 0 R I P 0 R N R u 0 T N R 9 0 T T E P C R T E P C R E C L E A S E C L E A S R E E D I T R E E 0 I T F D x U N I R F 0 X U N T R A I I R I I E S A I I R I I E u C N T E N u S U C N T E N u S U E a Y s a E S u E 0 Y S a E S U NPUTTORISKUANFCR No.- PSF%%IgNt 0 13 0 13 0 26 011 013 o3 0 0 13 100 HFO RISTRIBUTMN CPERATCRACTIONS PSFRANKIN35 FU HER LO(HER) CPERATCRACTIONS POP 09604T3 RANrEFACTCt MEDIAN MAXHER 10 10 10 10 1o 10 10 10 909E1 -oo006 ZHFt5 5 1 5 5 4 1 2 3 979 11s6E04 .3 S00f btF1 1 1 10 1 1 5 5 40 10 594E.0f D4EOP2 5 5 5 5 4 1 3 410t 9E-004 .33 719 DiE2 5 6 10 1 1 0 40 10 7K1E.01 D4He S 6 S S a I 5 4741 4 82E04 .3 3171 aitm $ 1 10 0 1 5 40 10 MENo4 DZEHR4 5 a S 5 4 1 4 4 32 2 7eE-04 .3 5591 2HEKFJ O 1 10 1 5 5 40 10 1 04E-04 D4ECF 5 a 5 e a I 4*745 42r-04 -3 3171 ZFfOFS 5 1 10 1 5 1 40 10 1 1004 2HEX1 9 10 1 4 S 8 7 125E-02 .18036 DZHEXT 0 S 10 0 1 5 5 25 5 711603 UINHER 0 0 0 0 0 0 0 0 4508E07 43114 NCRMALZMPSF o1 013 026 0.1 0.13 0.13 013 WE100rS CALIBRATICONTASKS PSFRANKIN35 FU HER LrtOHER)

MAXHER 10 10 10 10 10 10 10 10 OOE600 0 0000 SEA9BRCKON 0 0 t 0 2 0 0 051t 100E-06 .o0000 MINHER 0 0 0 0 0 0 0 0 100E-07 .63010 RqgrioWnOcP.At:

Co.t. nt .6 31136 Std4olYE t 001023 0 3M sn3 No of Cr vtlwo DorgnevFr-dom XCoWrCl..4(s) 0631081 StdErofCo?. 0001852 Figure 11: BVPS-1 Pre-EPU SLIM Worksheet Group 11

L-05-140 Enclosure 1, Attachment 1 Page 13 of 16 BEIEAVER VALLEY UNIT I . GROUP 12 HUMAN ACTIONS EVALUATION PERFO00OANCESHAPMNQFACTORS PERFMORMANCESHAPINGFACTORS C P C P I P 0 R I P 0 R N R M 0 T N R U 0 T T E P C R T E P C R E C L E A E C L E A S I

R E E 0 I R E E 0 I T F 0 X U N r R F 0 X U N T R A I I R I I E A I I R I I E S C N T E N 5 U C N T E N u a U E G v s 0 E S u E 0 Y S a 0 S M 4PUTTOftISKMANFOR NormPSFVSigNS 022 0.11 022 Oil Oil 0It 011 100 HER0ISTRBUTlCN OPERATCRACTIONS PSFRANKINGS FLU HER LOQHMR) OPERATCRACTICNS PSF 006HDHTS RANCEFACTCR MEDIAN MAXHER 10 10 10 ro 10 10 10 to 32E01 -0 0200 ZHECRS 9 S a 0 2 5 a 6007 327.E02 -14725 ZHECR5 10 5 10 5 5 S S 45 S 2 0osE02 ZHEc04 2 5 9 4 4 5 8 68t0 4206-02 t3754 MECR4 10 S 10 S S S 5 45 S 2 60-02 ZHECSF 9 S 9 4 4 S a 6889 420E.02 .137e4 ZHECSF 10 s 10 5 5 0 S '5 S 206Q02 5050HER 0 0 0 0 0 0 0 0 4 40E-05 .4208 NORMALOMPSF 022 Oil 0 O11 02 Oil OIl 0.11 VOOKI'S CALBRATIONTAsKS PSFRANKNGS FrU NMR LOGIHER)

MAXHER 10 10 10 10 10 10 10 10 100E0O0 00ooo S0IROCKBRe5 a e a e a ea 06O7 140E602 .18539 BIGROCK.2C 4 4 4 4 4 5 4 4.111 100E-03 .30000 SBOUOYAHCT1 2 3 S 0 4 2 2 2.776 1 80E-0 -2 7447 W0NH0R 0 0 0 0 0 0 0 0 3 75E-0 4 -44260 Re9glonOdAput:

Coojnt .4 es2s StdEolof 0YE O 343913 R qoarod o9 076 No of Oborvsllowa DOgo...f Frodom I2 xCoerffient(s) 0 422502 StdErf ofCoeo. 0 o462e92 Figure 12: BVPS-1 Pre-EPU SLIM Worksheet Group 12

L-05-140 Enclosure 1, Attachment 1 Page 14 of 16 BE--AVER VALLEY UNIT I - GROUP 13 HUMAN ACTIONS EVALUATION PERFERMANCESHAPINOFACTCRS PERFcOWANCESHAPFGFAcTcRS C P C P I P 0 R I P 0 R N R U 0 T N R U 0 T T E P C R T E P C R E C L E A S E C L E A R E E D I R E E 0 I F D X U N T R F D X U N T R A I I R I I E S A I I R I I E C N T E N U S U C N T E N M S S U

E a Y S 0 E S U E a Y a 0 E s INPI.T0TRISKMANFCR NOmPSFV*IgA s a00 00De 0 08 008 027 02? 014 too HEROISRIB.UTIONt OPERATCRACr1NS PSFRANKfN1fS FU HER LOG(HER) cPERATOR3ACTIcINS PSF VWE)G7S RANGEFACTCR MEDIAN MAXHER I 10 10 to to 10 10 10 890001 .0 ons ZHEPAE 8 a a 5 S 7 0 7324 5.11E-02 .12812 ZHMCR3 3 3 3 3 10 U0 5 37 0 317E.02 MINHER 0 0 0 0 0 0 0 0 1030-05 .47er7 NORMUAIIWPS 000f 0 00 0 04 0 08 027 0 27 0.14 VWEG4Th CAI~tBRATICNTASKS PSFRANKO4NGS FU HER IOGHER)

MAXHOR Ua U0 tU 10 tO tO 10 10 100IE00 0oODO se3U00AHFt.PH3CR 4 1 3 0 4 4 5 8 40s s000004 3 23" SBOLOYAHFI.A83C 6 e 0 e 4 4 0 4.757 4 0E-03 .2 3000 S103JYAHFLAM0 4 1 3 0 4 2 s 2 040 3 0OE-04 .3 4202 SEDUOAHI'PHIR 4 1 3 0 4 4 5 3 4806 5OE04 s -3 2348 MINHER 0 0 0 a 0 0 0 0 2.00E05 .4 990 R.gresgwOfutpifi:

.4 7r0e 0.132435 RSq.~..d4 o sssoer NDog,.f R-.

40 XCO0ficioi.nl. 0 477510 StdE,,.ICof. 0 0157704 Figure 13: BVPS-1 Pre-EPU SLIM Worksheet Group 13

L-05-140 Enclosure 1, Attachment 1 Page 15 of 16 BEAVE R VALLEY UNIT I - GROUP 14 HUMAN ACTIONS EVALUATION PERFORMANCES0APINGFACTCRS PERFCRUANCESNAP#48FACTORS C P C P I P 0 R I P 0 R N R U 0 T N R U 0 T T E P C R T E P C R E C L E A E C L E A R E E 0 I T8 R E E 0 I T5 F 0 X U N T F 0 X U N T R A I I R I I E S A I I R I I E C N T E N U U C N T E N E S U E a y S a E U E a r a 0 E S it INPUTTORISKUANFCR No- PSF1Aiqs 0.13 0.13 013 013 020 008 0. 3 100 HRDISTRIBUTICN CPERADORACTIMO PSFRAW0NGS FPU HER LOIGIHER) OPERATORACTICNS PSF WEIGHTS RANCEFACTCR MEDIAN MAXHER 10 10 10 ¶0 10 10 1o 10 0900.01 -. 012 ZHMSF a a 8 5 4 4 s 570 6a58E.03 .2.161e DIENSF 5 s 5 s 10 3 s 38 75 3 11i03 MINIHER 0 0 0 0 0 0 0 0 1220.05 4 9123 NORtMAL2DPSF 0n 0.13 0.13 0.13 020 0o0 013 MIEWHTS CALIBRAnoNTASKS PSFRANKE400 Fi 80ER LOQ.HER)

AXHEM 10 10 10 10 10 10 10 10 100.00 0 0000 PLGCAL3.1 a s

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.7oI FF,.dom 4 XCo licI.nt(5) 0489409 Std1f4ofCff. 0 0201059 Figure 14: BVPS-1 Pre-EPU SLIM Worksheet Group 14

L-05-140 Enclosure 1, Attachment I Page 16Of 16 BEAVER VAALLEY UNIT I - GROUP 15 HUMAN ACTIONS EVALUATION PERFORMANCE5HAPINOFACTCRS PERFOSMANCESHAPINGFACTcRS C P C P I P 0 R I P 0 R N R U 0 T N R U 0 T T E P C R T E P C R E C L E A S E C L E A S R E E 0 I T R E E 0 I T F 0 X U N T R F 0 X U N T R A I I R I I E A I I R I I E s u

C N T E N U s U C N T E N U S u E O Y S O E S U E 0 Y S G E S u INPUTTORISKMANMCR Nom.PSFYigo s 011 Oil 022 011 011 022 0.11 100 HOROISTRhIUTION OPERATCRACTIC5S PSFRANKINGS FU Hn1 Lca2HR) MERATCRACTIONS PSF V*IGTH RANCEFACTCR MUDIAN MAXHER 10 10 10 10 10 10 10 10 9 95E-01 0 0022 2HEn2 6 6 10 1 4 0 0 7 e07 12eE.01 .0 tol ZHEIT2 5 5 10 5 5 10 5 45 3 103E.01 UINHER 0 0 0 0 0 0 0 a *54E04 -3s11t NORuALeP5P 011 Oil 022 o.1 0.11 022 0.11 vIEK4S CALURAT1ONTASKS PSFRANKINGS FLI HER LC.H5I4)

MAXHER 10 10 10 10 10 10 10 10 1 00.E00 0.0000 DC2HEI 2 2 1 5 5 3 4 2U89 150E-03 .28239 STPHEOR07 7 5

4 5 a 6 5.444 2080.02 .10819 UINHER 0 0 0 0 0 0 0 0 t75E04 .3.7570 R.9 *o.0ApV:

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L-05-140 Enclosure 1, Attachment 2 Page 1 of 17 Attachment 2 to RAI 2.a.

BVPS-1 Post-EPU SLIM Worksheets

L-05-140 Enclosure 1, Attachment 2 Page 2 of 17 BEAVERVALLEY UNT 1- GROLP I HUVIAN ACLnCNS EVALLIA11CN PUC"ESMRN3 F -CF( PhOWCE StiVMG FWCMU C P C P I P 0 R I P 0 R N R M 0 T N R MO T T E P C R T E PC R E C L E A S E CL E A S R E E D I T R E ED I T F D X U N T R F D X U N T R A I I R I I E S A I I RI I E S C N T E N M S U C N T E N M S U E G Y S G E S M E G Y S G E S M ItNWTRSIMlNFCR N2m PSFYlits 013 013 Q13 031 013 GOB 013 103 IERDSRRIrN CPEPATCR~cnONS PSFFRNNSS FU FER LOGt~M CRPEPTCRAlO PSF v\04TS PFal'FAC MnM 10 10 10 10 10 10 10 10 9901 4QI8 M4FER 5 5 5 3 5 1 5 4t25 iSOM4 -273) 0 0 0 5 0 0 0 5 7.5 88Et MHf33 8 2 9 2 8 2 6 4875 419E 2371 5 5 5 105 5 5 43 7.5 1.3 8 4 8 5 6 1 5 525 625f4 -2232 5 5 5 10 5 0 5 75 2953 MWtER o a 0 0 0 0 0 0 22T1C5 -464 NOZEDPSF Q13 013 Q13 Q31 013 00 013 VfGIns CqJJRATTA9S1 FU FER LWClOM 10 10 10 10 10 10 10 10 GCE4W Qmn NFM1 (1) 5 5 5 3 5 2 5 4183 20Q03 -26 MNFER 0 0 0 0 0 0 0 0 23!E- A43 NAO OdrdYl t1)PAN3SARESF-MCRSMM) 00P,418 fiCNINBWI t2 RSdW N%d Cewfti" 3 t5g d Farn Xod8g) 04 Figure 16: BVPS-1 Post-EPU SLIM Worksheet Group 1

L-05-140 Enclosure 1, Attachment 2 Page 3 of 17 BEAVER VALLEY UNT 1 -GROUP 2 HM4N ACnTMS EVALIJATIN P37IMNE StW"NG FACTMF P31 iE S4- PNG FACTORS C P C P I P 0 R I P 0 R N R M 0 T N R M O T T E P C R T E P C R E C L E A S E C L E A S R E E D I T R E E D I T F 0 X U N T R F D X U N T R A I I R I I E S A I I R I I E S C N T E N M S U C N T E N M S U E G Y S G E S M E G Y S G E S U IN'UTTMRtPSION FOR Nom PSF\iNis OS Go 033 033 QQW QQ US 1.Q0 HIM DSTFaatMCN CIERATCIORACTONS PSFRAWINGS FU HER LO OPERATCORACIKN P3F VaGOS ROE FACTrCR MEDIAN MAAXIFER 10 10 10 10 10 10 10 tO 959M01 -QQ0i3 ZFEMYI 8 5 a 5 2 1 4 583 a4O0 -.2757 0 0 5 5 0 0 0 10 7.5 397E03 ZEli 8 6 8 5 2 3 4 575 1.0tE42 *1.974 0 0 5 5 0 0 0 10 5 623E403 i2H3 ZHEM 7 7 6 3 5 1 5 45 26SW -25B 0 0 5 5 0 0 0 10 7.5 12380 Z2E HEAMI a 5 8 5 2 0 4 55 7.feSS -21149 aEMt 0 0 5 5 0 0 0 10 7.5 atUE3 Diem 7 1 7 5 3 5 3 55 7.1f4 -21149 D2HM 5 0 10 0 5 5 5 40 7.5 5a2E ZHEOU 7 1 7 5 3 3 5 55 7.8E4 -21149 5 0 010 5 5 5 40 7.5 aeE4 MN RR 0 0 0 0 0 0 0 0 2Q *E 4 (13 NRA4LPSF QQ8 GOOQ033 033 QQ8 oce QC8 1 VOHs CAUBATICNSTASS RF HER LOG""

MXFR 10 10 10 10 10 10 10 10 1.Q10 0QQX RAI-XOF9O1 (1) 7 1 7 5 3 3 3 5333 640O3 -2193 MNFER 0 0 0 0 0 0 0 0 2QME05 -4eM RiVl O~btt

.4exE7 (C)PANIISAREI FCR SIMLAR SstdrfdYE91 ACTIONINMM V"1) R Stfm N1 d Obs~y, 3 Cb d Fnwedom 1 XCidWWs) Q4W7 F ig u7S . QQtS115 Sd Figure 17: BVPS-1 Post-EPU SLIM Worksheet Group 2

L-05-140 Enclosure 1, Attachment 2 Page 4 of 17 BEAVER VALLEY UNT 1-GROUP 3 HUMAN ACTIONS EVALUATION P aFM -SKORNG FACTtRS PERFOR CE SlWtNG FACTRS C P C P P o R P o R N R M 0 T N R Mo T T E P C R T E P C R E C L E A S E C L E A S R E E 0 I T R E E D I T F D X U N T F D X U N T R A I I R I I E S A I I R I I E S C N T E N M S U C N T E N M S U E G Y S G E S M E G Y S G E S M 11TT0t RISSnAANFOR NobMPSFVAYt CU12 QU o10 CIO 0.07 024 024 IE 7 wRrDlmcN OPERATOR ACTIONS PSFRA1N074S FU HfER LOO"B) OPERATOR ACTIONS PSF\AtGRTS RANGE FACTOR MEDW MAkXIHR 10 10 10 10 10 10 10 10 9.36E01 -Q0035 ZElD 2 a 8 5 7 2 4 4241 258003 -35B 5 5 5 5 5 10 10 45 7.5 1.2E3 ZHEM 2 1 2 2 4 4 6 345 1.17E03 -29335 5 5 5 5 5 10 10 45 7.5 s5504 ZHEREB 1 2 a 9 9 8 7 ea32 2.202 .1645 DfEREe 5 5 5 5 5 10 10 45 5 1.40E42 ZHFL1 7 7 9 9 a 6 8 7.345 e18s0E2 -1.208 nffL1 5 5 5 5 0 10 10 40 5 a83E402 ZHFL2 7 7 9 9 a 5 6 7.103 48302 *1.3182 ZHFfL2 5 5 5 5 0 10 10 40 5 zs3E4 ZHEFU ZHOU 7 7 9 9 a 5 8 7.103 4860G2 -1.3182 5 5 5 5 0 10 10 40 5 29E-02 2HE6C3 a 9 8 2 9 e 8 e845 170332 .1.4312 DiC P 5 5 0 0 5 10 10 35 5 z3E402 MN HER 0 0 0 0 0 0 0 0 133-c -44743 C12 012 C10I 10 007 024 024 V EGHTS CAUBA1ToN TA9SK PSFRrAW03S FU HER LCXR MAXKER 10 10 10 10 10 10 10 10 i.QEOO QOn t STP tE1 4 3 a 10 10 a 3 sas2 1.0E.2 .1.7447 FEMt RE7 6 7 a 8 6 5 8 esss 1.32602 -18794 MNIER 0 0 0 0 0 0 0 0 13.OOE- 4529 447420 Rd stdYEst 0Q3a135 Ow7l No d Cbswr"s 4 Doom d Freqi 2 XOCc ff s) Q444575 9d rfCfd. 0047O447 Figure 18: BVPS-1 Post-EPU SLIM Worksheet Group 3

L-05-140 Enclosure 1, Attachment 2 Page 5 of 17 BEAVER VALLEY UNIT 1 - GROUP 4 HUMAN ACTIONS EVALUATION PtERFt E StAt8G FACTVRS PERFOc SKAPIG FACrORS C P C P I P 0 R I P 0 R N R M 0 T N R M 0 T T E P C R T E P C R E C L E A S E C L E A S R E E D R E E D I T F D X U N T R F D X U N T R A I I R I I E S A I I R I I E S C N T E N M S U C N T E N M S U E G Y S a E S M E G Y S 0 E S M ItPUTTORtttAAFOR NonmnPSF t4s 013 011 013 a11 013 0.11 0.30 1.03 twERDSTMcT*

PSFRAWN1S FU H-ER LtG(F{R OPEPATORACTX)NS PSFYVEtoTS RANGEFACTOR LED4N M4X HER 10 10 10 10 10 10 10 10 9.15-01 4.0357 2 1 2 2 4 0 5 283 585-04 435 85 0 0 0 0 0 0 5 5 10 9t6505 DFPRI 2 2 2 2 3 0 6 3106 353E-04 4'4516 0 0 0 0 0 0 5 10 1.33E04 9 2 9 8 8 1 10 7.468 510E-02 12922 D ECD4 5 5 5 5 5 5 10 40 5 118E42 8 6 8 5 8 5 6 8553 1.80602 -1.7451 5 5 5 5 5 5 10 40 5 1.11E-2 8 a 8 5 8 7 8 7.352 4.52E02 *1.3449 5 5 5 5 5 5 10 40 5 288E02 ZD" 2 6 3 2 4 1 7 4.191 122E-03 .29144 3FE-081 5 5 5 5 5 5 10 40 7.5 5750E4 2 0 2 0 3 2 7 31191 3 9E004 -34095 ZHE0Al 5 5 5 5 5 0 10 35 10 1.46E-04 ZHEOT1 0 10 1 2 3 1 a 3.681 6.80604 41672 ZHEOTI 5 0 5 0 5 5 10 30 10 255E04 MN HER 0 0 0 0 0 0 0 0 1 02t-04 *46395 tJZEAADZ PSF 013 011 013 0.11 0.13 0.11 0.30 vWGTaSs C0Ua4A3TIctTA980 PSFRAMNGS FU IER LfN0ER)

MX HER 10 10 10 10 10 10 10 10 1.0DE+40 0.0000 STPHE014 2 8 3 5 6 I 6 4 6t1 9 8254 -30079 FERMttECT3 4 8 3 3 3 3 3 1447 1.15E03 -29393 MNI-ER 0 0 0 0 0 0 0 0 920E-05 4032 MtaS .4g9m4 StdErrd Y Est C8342488 R Stred 0.91802 M-.d Ctset 4 tev of Fman, 2 Figure 19: BVPS-1 Post-EPU SLIM Worksheet Group 4

L-05-140 Enclosure 1, Attachment 2 Page 6 of 17 BEAVER VALLEY UTT I -GROUP 5 HUMAN ACnONS EVALUAImON PEIFaRFACE SHAF1NG FACTM P8U0MAM SR4AWG FARS C P C P P 0 R I P R N R M 0 T N R Mo T T E P C R T E P C R E C L E A S E C L E A S R E E D I T R E E D I T F 0 X U N T R F D X U N T R A I I R I I E S A I I R I I E S C N T E N M S U C N T E N M S U E G Y S G E S M E G Y S G E S M INfUT TO RSMAKMNFOR Norm PWVM" 015 Q15 Q15 W1s Q1s Q11 014 1.0 HERnsTfiunNmW OPERATCR ACfCNS WFRANKNOs FU HER Lcx6; PEATORAnCTK wSF VOWS RA FACTCR MEDAN MAXH9 10 10 10 10 to 10 10 10 997-01 .00012 2 6 6 7 2 2 5 4.37 42103 .23781 DHEt 5 5 5 5 5 5 5 35 7.5 1.93mm 2 6 7 7 2 4 6 4883 M92M03 -21%7 ZDr= 5 5 5 5 5 5 5 35 7.5 3277M03 ZHBfl Z2 1 2 4 1 3 3 3 2403 622354 432081 bl= 5 5 5 5 5 5 5 35 10 234C04 1 7 5 5 2 2 6 40r5 313E-03 -.2549 ZHEW 5 5 5 5 5 5 5 35 7.5 1.49E43 2 2 3 1 3 1 4 2325 S77.4 4239O z2F+ 5 5 5 5 5 5 5 35 10 217EC04 ZM1 awA2C 2 5 4 2 a 2 2 2344 1.55503 *2W 7HE1A 5 5 5 5 5 5 5 35 75 733E04 ZHUMIt 2 3 1 2 8 2 5 1325 1.5203 .28172 ZHBP2 5 5 5 5 5 5 5 35 7.5 7.19EC4 aFEM4 2 3 5 2 5 0 5 a253 1.42603 -28473 7tM 5 5 5 5 5 5 5 35 7.5 71E504 0 0 1 5 3 3 5 239 6E454 42116 ZHMI1 5 5 5 5 5 5 5 35 10 23tE104 0 1 1 5 3 3 5 2539 7.1004 41488 ZFEPKI 5 5 5 5 5 5 5 35 10 287E54 1 2 8 9 9 4 5 5487 124E5- *1.M 2ffRds 5 5 5 5 5 5 5 35 5 7.71E-03 2 2 5 5 4 2 2 1195 134603 -2719 ZHEM~ 5 5 5 5 5 5 5 35 7.5 634E04 2 5 2 3 4 3 4 1292 1.48M03 *2.M ZHESE1 5 5 5 5 5 5 5 35 7.S a97Eo4 7H3MI 3 2 8 5 4 1 8 4.539 425503 -23D49 7aM 5 5 5 5 5 5 5 35 7.5 2345-03 7 10 9 9 10 1 10 s25 184601 Q7353 ZHESL3 5 5 5 5 5 5 5 35 3 1.47E01 5 5 5 4 7 5 4 SOWe 7.BX503 -21077 a-EM 5 5 5 5 5 5 5 35 75 319M03 ZFEWF 8 6 2 5 5 3 5 4.929 723503 21405 7FEAF1 5 5 5 5 5 0 5 30 7.5 342603 ZHMAI 6 1 5 2 6 1 6 1956 28E-03 .25515 D{DEF1 5 5 5 5 5 0 5 30 7.5 1.33E-03 a 6 a 4 4 1 5 4708 5.84503 Z2337 1H~ 5 5 5 5 5s 0 5 30 7.5 2765.03 D E3A2 4 6 5 4 4 1 5 425 17E-03 2427 ZHB 5 5 5 5 5 0 5 30 7.5 1.78E.03 as1A4 7 7 5 3 4 1 3 4422 44203 .23542 2ff3A4 5 5 5 5 5 0 5 30 7.5 Z5E43 2 4 2 5 3 3 2 13c5 1.12-03 -2s514 ZHEW 5 5 5 5 5 0 0 25 7.5 52#4 8 9 a 9 a 7 9 8331 1.9701 -0752 afE*K 5 5 5 5 5 5 5 35 3 1.50t MANHER 0 0 0 0 0 0 0 0o803E- 4.2195 N EM&A=PSF Qt15 015 Q15 Q15 Q15 011 Q14 MtGHTS Figure 20: BVPS-1 Post-EPU SLIM Worksheet Group 5

L-05-140 Enclosure 1,Affachment 2 Page 7 of 17 10 10 10 10 10 10 10 10 1.00E Qu 6 5 6 6 8 6 9 657S 4 : -1355 SrPH31XL3 3 4 5 3 3 4 6 3ag 213603 -26&

srpMm MNHR- 3 3 6 4 4 2 4 3779 231ES -26164 0 0 0 0 0 0 0 0 69OC5 A416 RmOu 421M SiErdYEt Qa RSaui DReadl: 5 3

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Figure 20: BVPS-1 Post-EPU SLIM Worksheet Group 5 (continued)

L-05-140 Enclosure 1, Attachment 2 Page 8 of 17 BEAVERVALLEY UNT 1-GROP 6HUMNACnCNS EVAL.TOCN fFtE9MGFPCF\

C P C P I P 0 R I P0 R N R M 0 T N R M0 T T E P C R T E PC R E C L E A S E CL E A S R E E 0 I T R E ED I T F D X U N T R F D X U N T R A I I R I I E S A I I RI I E S C N T E N M S U C N T E N M S U E G Y S G E S M E G Y S G E S M INvtMR9MPFaR NtmPSFVMA4 LO Q QO Q0 0 mOD O0M OLD tan I-6RDSTRB7CN CPPTCRP£ICNS WSR"NGS I IfR LCIQB3 CECNS PSF VOGWS RINFPCTM MMN MWXfBR 10 10 10 10 10 10 10 10 aBE01 aOQ7 ZHM.1 6 6 6 5 3 3 5 45 339E -4715 0 5 0 0 0 5 0 10 73 1.5E03 am1 aE1T 4 5 2 3 3 7 5 6 l.CE42 -1.7976 0 5 0 0 0 5 0 10 5 987E03 MNI-R 0 0 0 0 0 0 0 0 3,21E5 -4.4E!

N M3PSF LDQlM D NOQLLD QOlM QD VOWG4S C4PJU1AnCNTSA3 PSFRNGS FU KR LC(QB WXR 10 10 10 10 10 10 10 10 lfE.G) Om STPFMm1 3 4 5 3 3 4 6 4 213ED -26716 DCZHr1 1) 6 6 6 5 3 3 5 45 32OR3 0249S MNHR 0 0 0 0 0 0 0 0 3ZE05 449S9 CYd -4.J1M (1) RNOSKEXEFCR9MLAR SdEvrdYEs 0CL AMICNINMI PHL1)

N1 d C bf 4 DqgumdFiwd3i 2 d d 3f . QM7 Figure 21: BVPS-1 Post-EPU SLIM Worksheet Group 6

L-05-140 Enclosure 1, Affachment 2 Page 9 of 17 EAVEVALLEY tNT 1- GMJP 7 HUMVN ATINPS EVAWllTCN PF~tPRNGMWnFXS P C P CP I P 0 R I P 0 R N R M 0 T N R MO T T E P C R T E PC R E C L E A S E CL E A S R E E D I T R E E0 I T F D X U N T R F D X U N T R A I I R I I E S A I I R I I E S C N T E N M S U C N T E N M S U E G Y S G E S M E G Y S G E S M INRW R91~CR NxmPTWit a1O t 0Q5 Q10 010 Q10 010 025 1.m noRDSmBT1 CEATCRRInCNS RF FER LM mP{}) rPRATCRoams WV\3GHTS RANMFACTCR MPVN WXFER 10 10 10 10 10 10 10 10 MmO1 -0l 5 aml 2 5 3 3 5 3 3 36 24UMfl -Z6105 0 5 0 0 0 0 5 10 75 1.16M aH3CD5 1 6 8 5 7 5 8 6.1 25mmti -1sE3 5 105 5 5 5 10 45 5 1i2 ZHXF2 2 9 3 2 4 1 8 545 1XEt2 -1.8960 5 105 5 5 5 10 45 5 WRO MNFER 0 0 0 0 0 0 0 0 35E05 4.0U7 C10 025 a10 C10 Q10 010 Q25 yea-ffs PWRPNGS URI FR Lomm 10 10 10 10 10 10 10 10 1.07E4a oomm 4 3 6 4 7 2 8 50 asao -zm MA-8(6 2 9 3 2 4 1 8 545 1I.OZO -OOM 5 7 7 6 6 4 8 655 54Ti42 -12C4 MNFER 0 0 0 0 0 0 0 0 9005EX 4.0 4.07 (1) RAN3SAMTOMFCRSMUR DdrFrrdYEst 012121 xCNIN EVI = RSnued 0.9m1N W dd Fixhn 5 3

X~fldW. 04.t12 Figure 22: BVPS-1 Post-EPU SLIM Worksheet Group 7

L-05-140 Enclosure 1, Attachment 2 Page 10 of 17 BEAVER VALLEY UNIT 1 - GROUP 8 HUMAN ACTIONS EVALUATION PERFaRMANE SWANG FACTORS PERFORMANCE SHAPING FACTORS C P C P I P 0 R I P 0 R N R M 0 T N R M 0 T T E P C R T E P C R E C L E A S E C L E A S R E E D I T R E E D I T F D X U N T R F D X U N T R A I I R I I E S A I I R I I E S C N T E N M S U C N T E N M S U E 0 Y S a E S U E 0 Y S O E S M INPVTTORISOMAN FOR NormPSFUWIk-h 0.13 0.13 0.10 0.10 0.11 031 0.11 1.0C HER O1STRDqLrON OERATOR ACTIONS PSF RANKNGS FU HER LOG0{ OPERATORACKTNS PiSF VA1DfGTS RANGE FACTOR MEaDAN MAX HER 10 10 10 10 10 10 10 10 996E-01 -0.0018 334 3 3 5 7 4 3 1971 234E0-3 .Z25o0 ZHEF1.4 0 0 0 0 0 5 0 7.5 1.11E-03 H-ETT2 4 3 2 3 3 5 3 3657 1.71E-03 *z7675 0 0 0 0 0 5 0 7.5 8 07E-04 ZFEWA2 a 6 a 7 7 7 5 6.414 2.72E02 .1.5653 ZHEV02 0 0 0 0 0 10 0 10 s 1.69-02 ZHBIW 3 3 3 4 7 2 2 3.129 1.00E-03 2s9980 5 5 5 5 5 10 5 40 7.5 474E-04 DflEV3 5 7 7 9 9 8 8 7.371 7.11E402 1.1479 ZHEEV4 5 5 5 0 5 10 5 35 5 4 41E-2 ZHEBV4 5 a 3 4 7 5 5 5057 897E-03 -21571 5 5 5 5 5 10 5 40 7.5 3 29E-03 DE2 CD1 2 5 8 3 5 2 4 3657 1.7143 -. 7675 HEC71 5 5 5 5 5 10 5 40 7.5 8s07E04 ZHECT1 2 6 6 7 2 a 5 5014 667E.03 2.1758 2HECT1 5 5 5 5 5 10 5 40 7.5 315sE03 2EA3 6 6 6 4 4 10 5 &714 3680.02 -1.4345 5 5 5 5 5 10 5 40 S 2.28E2-6 D1 I 0 1 0 0 5 7 26 5.91E4 32285 5 5 5 5 5 10 5 40 10 22E-04 ZEC2 2 a 4 3 4 5 4 4.214 2.9503 *2524e ZFEIC2 5 5 0 5 5 10 5 35 75 1.41E-03 ZHEICI 6 7 e 2 e 2 3 4.129 2.74E-03 .2.5620 5 5 0 0 0 10 0 20 7.5 1 2s4-03 MINHER 0 0 0 0 0 0 0 0 4.34E0-5 J4360 NORMAUZL PSF 0.13 0.13 0.10 0.10 0.11 0.31 0.11 VVlGHTS CAUE9RATION TASKS PSFRANKINGS FU HER LOG"P)

MAXIER 10 10 10 10 10 10 10 10 1.0ECO 0.eexo FERMI IERSI 2 7 2 3 2 4 5 3.829 1.75603 .27570 STPHES001 4 3 6 10 10 6 3 5.871 1.800E-2 -1.7447 MINHER 0 0 0 0 0 0 0 0 4e E"0 .4.3372 R o

.4.36218 Std Err Yf Est 0.0o5e7e R Squed 0 999309 ND. of O bsioro 4 D0e" of Freedom 2 XCoeftet(s) 0.4364 Sid EafofCdo. 0.0w1103 Figure 23: BVPS-1 Post-EPU SLIM Worksheet Group 8

L-05-140 Enclosure 1, Attachment 2 Page 11 of 17 EAVEVAlUEY(lW 1- G1P 9HlVlNpacsE B/ALINAM11 ESSRCfM94MFXCMS C P C P I P 0 R I PO R N R M O r N R MO T T E P C R T E PC R E C L E A S E CL E A S R E E D I T R E ED I T F D X U N T R F D X U N T R A I I R I I E S A I I RI I E S C N T E N M S U C N T E N M S U E G Y S G E S M E G Y S G E S M RN'1QFCRSTMPFCR Nim PFVftb QQOQ17 017 017 Q17 017 Q17 im FEROSTR3J\C CEkCRBAM FU FER lWalff EATCRSACr PEF vOS R*MF=IER MD MAXFER 10 10 10 10 10 10 10 10 9901 -a0 2H3I5 2 9 5 3 7 2 9 5833 4432 -1.394 0 5 5 5 5 5 5 5 27X-2 2FE7 2 9 8 5 8 4 9 01671501 4Z6 0 5 5 5 5 5 5 3 95sm MNFER 0 0 0 0 0 0 0 0 557EC 42562 NW EFU: 00Q Q17 Q17 Q17 Q17 Q17 017 1 VBBGTS CqPUrI1CNTA9CS 10 10 10 10 10 10 10 10 1.Q QWD O

STPMENK 6 5 6 6 8 6 9 6aw 433t -1.3M5 2 9 5 3 7 3 9 6 1.ME01 *1.CM MNFER~ 0 0 0 0 0 0 0 0 52E0m -34 FtnC~rt 4Zi25 (1) RN3tME MR SdBrdYEt QZM2 cMCNNNIN(A- RSwna Q0R5 NidCOsafs 4 D39emdR8F 2 Xoffdffgs) a7 SdErdW. 00Q Figure 24: BVPS-1 Post-EPU SLIM Worksheet Group 9

L-05-140 Enclosure 1, Attachment 2 Page 12 of 17 SFAVERVALE YLUN1 -GAP 10 HMINACl S EVAWUA11CN FNE }W3FCXFS PU3i" C P C P I P 0 R I P OR N R MO T N R MO T T E P C R T E PC R E C L E A S E CL E A S R E E D I T R E E D I T F D X U N T R F D X U N T R A I I R I I E S A I I RI I E S C N T E N M S U C N T E N M S U E G Y S G E S M E G Y S G E S M INI-TTORSMFCR NnnM FWk1s Q11 Qtt 0l 2 072 Q11 Q22 Q11 I.tO RDtISTRnt1O0N CKRUACR~AMCF8 PSR4nN39S fU FER LO%"T3 CRUCnIC1m6 WGV\SGIS RG*FACrCR MM 10 10 10 10 10 10 10 10 9996M -003M 3ES3 7 1 7 5 3 4 6 5333 1.fC2 -1.7218 ZHlE3- 5 0 10 10 5 10 5 45 5 1.18E2 aim 7 1 7 5 3 8 8 6444 489E42 -1312D 21D34 5 0 10 10 5 10 5 45 5 3Q MNH{R 0 0 0 0 0 0 0 0 ZTEm4 -3xe8 NOA42DWS Q11 00O 0QZ 0Q2 Q11 0QZ 011 I VIEIGHI~SF ma)a ma CAIUDVMCNTA9SG RJ HR jOf3 10 10 10 10 10 10 10 10 1.QE0 0031 5 4 7 4 8 5 6 5444 Z2EM -1.6019 MNFER 0 0 0 0 0 0 0 O zomC4 a am

.at77 WderdYE 001415 RSaei N d.

Dsdmvdi 13 c,,D~ dFre9ii XQ&tda*!O 03Q3 4 SdSrdW. QOMM Figure 25: BVPS-1 Post-EPU SLIM Worksheet Group 10

L-05-140 Enclosure 1, Attachment 2 Page 13 of 17 EEAVERVAUEY UNT 1- GRLP 11 MnAN ACT1CNS EVALUA1IcN PE}ERV~ %MNG FACIR~rS PErTUCE SFWVC FACT C P C P I P 0 R I P 0 R N R M 0 T N R M O T T E P C R T E P C R E C L E A S E C L E A S R E E D I T R E E D I T F D X U N T R F D X U N T R A I I R I I E S A I I R I I E S C N T E N M S U C N T E N M S U E G Y S G E S M E G Y S G E S M INirTOFT0RFOR Nim PSFWkts Q13 Q13 GM Q11 Q13 Q13 013 1co HERtSsltllJrlCN CPEATURA~lCNS PSFPRNMNGS FU WER L KMM CEATCRcnom PSF VOCHTS RPEXFPCTCR bUN WVHR 10 10 10 10 10 10 10 10 99EO 4QXB ZF1 5 5 5 5 4 0 2 3851 1.32.4 aBM3O Z ECF1 5 5 10 5 5 5 5 40 10 494EC5 ZHMF2 5 5 5 5 4 2 3 4Z'4 2ZEC4 463i 5 5 10 5 5 5 5 43 10 86tEt ZFECF3 5 6 5 5 6 2 5 4e2 5SOX4 -aZE5 3EF3 5 5 10 5 5 5 5 43 10 21844 ZHXIF4 5 6 5 5 4 2 4 448 332E4 -3478 5 5 10 5 5 5 5 40 10 12mC4 ZE F4 ZEfF5 5 6 5 5 6 2 5 4W B72 5 4 a235 5 5 10 5 5 5 5 40 10 218E.4

-fX"t 8 9 10 1 4 5 8 7 12X1S02 -18MB 5 5 10 0 5 5 5 35 5 7.91E43 VHBDMS MNWER 0 0 0 0 0 0 0 0 483S 43114 Q13 Q13 Q3 01lt13 013 013 Vn~G~rS CqUEPATINOTA9SK PSF RINS RI FER VM XO MFER 10 10 10 10 10 10 10 1O toxlBaO o=

O0 O0CN 1 0 2 0 0 QS11 1.Q;ECS -60X MNFR0 0 0 0 0 0 0 0 500T 46310

-63t135 SdBxdYEt 0015u23 RSqHW 09t N3 d Fmdmc 3 XCtxilS) Q63tQ8t 9d Erd . amaw Figure 26: BVPS-1 Post-EPU SLIM Worksheet Group 11

L-05-140 Enclosure 1,Attachment 2 Page 14 of 17 BEAVER VALLE( UT1 -GROUP 12 HUMAN ACTIONS EVALUATION FP J 945ANG3FAcrcXs FPffiNM SWING FACXFS C P C P I P 0 R I P 0 R N R M 0 T N R M O T T E P C R T E P C R E C L E A S E C L E A S R E E D I T R E E D I T F D X U N T R F D X U N T R A I I R I I E S A I I R I I E S C N T E N M S U C N T E N M S U E G Y S G E S M E G Y S G E S M INImrTORMOANFCR NnrnmPSNts Q2 a11 Q2 Qll all aQ1 all 10 ER DSTRnJ CN CPEk cnACNs PWRAWN3S FU FER LoCX~ CAT7ATC TKAnB PSF W r 4S RAFM FCTRR EN MAX FIR 10 10 10 10 10 10 10 10 9-01 40M a3 9 8 8 5 2 5 a es7 337EC2 1.475 2H3 10 5 10 5 5 5 5 45 5 7 eOM DB RPA9 5 9 4 4 5 8 a8 42ER2 -1.3784 ZE 10 5 10 5 5 5 5 45 5 2&EM2 ZFEXF 9 5 9 4 4 5 8 658 42X2 -1.3784 aF 10 5 10 5 5 5 5 45 5 2EC2 MNIE 0 0 0 0 a o 0 0 4400 -433 NZEDfF 0.= all Q2 all aii all all VflGITS CAJUEA1ONTASKS PS RAWN3R F F G LKROG M;X 1E 10 10 10 10 10 10 10 10 1.QO GQM fs e8GFROK5 6 5 6 5 e 567 1.42 *14.8M9 OGF(OCL2C 4 4 4 4 4 5 4 4111 1 430f 0

ATh'HCT1 2 3 5 0 4 2 2 2778 1 BZM -27447 MNHR 0 0 0 0 0 0 0 0 37505 -442e S DEfddYE RSDdI a~7 5

ai d h 3

XcOdfidfJ1 S) 043 SE Erd1. Q02 Fig ure 2 :Ps E U LW o Figure 27: BVPS-1 Post-EPU SLIM Worksheet Group 12

L-05-140 Enclosure 1, Attachment 2 Page 15 of 17 AVMERVALLEY UNT 1 -GROUP 13 VAMN ACnCNS EVALULIAON PFOCRaES Wr3 FAC tF P7ranATJC S}W6G FPCaI;S C P C P I P 0 R I P 0 R N R M 0 T N R M O T T E P C R T E P C R E C L E A S E C L E A S R E E D I T R E E D I T F D X U N T R F D X U N T R A I I R I I E S A I I R I I E S C N T E N M S U C N T E N M S U E G Y S G E S M E G Y S G E S M NW~TORISKA%\FCR Nam SFwV~ 002 Q8 008 008 027 027 014 1.02 I-6l DSTRW MT AN CPfPATcCnS PSFFN3S FU MER LO3T~ CFEATCRnAKM PSF VBGHTS PANMFPCTtR NEDMA MSXFER 10 10 10 10 10 10 10 10 9WOEW 400135 ZFPAE 8 6 8 5 8 7 8 7.324 511E42 .1.2912 MME 3 3 3 3 10 10 5 37 317E42 MNHER 0 0 0 0 0 0 0 O 1.6E5 4707 I-OZ PSF 00Q 003 0Q0 QQ3027 027 014 1 Sohr CqAffWTA9S PSFRWNCNS FU HER LOM M5XHER 10 10 10 10 10 10 10 10 1J.01 QOM SEOLAH FRHCR 4 1 3 0 4 4 5 34£ 5TEO4 -32306 SEJO~YMFlHA 6 8 0 8 4 4 6 4757 44DE3 -2:

SEUOYM-FLABWR 4 1 3 0 4 2 5 2946 38E04 -342 SfDi'AHRRfHR 4 1 3 0 4 4 5 34' 58EC4 .236 MN8ER 0 0 0 0 0 0 0 0 2E05 -46M

-4785 WrHfrdYEs Q12345 RStdmt 6

N1d~f8wfr 4

XO1d"S) Q477S16 S9fddC. 00167764 Figure 28: BVPS-1 Post-EPU SLIM Worksheet Group 13

L-05-140 Enclosure 1, Attachment 2 Page 16 of 17 WEAVERVALlEY UT 1- GROP 14 HUIAN ACTICNS EVALWATICN C P C P I P 0 R I P 0 R N R M 0 T N R M O T T E P C R T E P C R E C L E A S E C L E A S R E E D I T R E E D I T F D X U N T R F D X U N T R A I I R I I E S A I I R I I E S C N T E N M S U C N T E N M S U E G Y S G E S M E G Y S G E S M IJnUTTO RSIMM FOR Nml PSW\Nits 013 Q13 013 013 0M QQ8 Q13 1.02 ERcSimeuInw a TCRT)GM W RNSS FU FER LOLXTj rU7ATCRSACU MWXtER 10 10 10 10 10 10 10 10 95MO1 00182 ZFEWf 8 6 8 5 4 4 5 5579 6543 -21819 5 5 5 5 10 3 5 7.5 311E03 MNFER 0 0 0 0 0 0 0 0 122s .4913 NOW= PT 013 013 013 013 03 00Q 013 urGHs CAUBPATMUTAS PS RAMOSS FU hER L KDi MWXHER 10 10 10 10 10 10 10 10 1.0a4tD Q=m FRGCxL1 6 5 6 5 6 5 6 56'8 1.40M -185M R.GCL32 4 4 4 4 4 5 4 4079 1.03 -a=

PLGCPL33 7 6 7 6 7 6 6 65B 2503 -1031 R.GCkL34 9 8 9 9 9 9 9 88-8 1.0301 04a9 MNFER 0 0 0 0 0 0 0 0 1.0Xt05 -*6OX FnO4p+/-

-491225 StErdYEs N%d Cbfrdmkl 6 d Frin 4 Xomwsl(s) 049 StEddOd. Qgsm Figure 29: BVPS-1 Post-EPU SLIM Worksheet Group 14

L-05-140 Enclosure 1, Attachment 2 Page 17 of 17 EEVIRVAllEILNr 1- GUP 15 HIUVNPClICNS EVALIATICN FRXRvVMWYSffNGFAMS PFU}UMCE qjHft'GFiCrCF c P C P I P 0 R I P 0 R N R M O T N R MO T T E P C R T E P C R E C L E A S E CL E A S R E E D I T R E ED I T F D X U N T R F D X U N T R A I I R I I E S A I RI I E S C N T E N M S U C N T E N M S U E G Y S G E S M E G Y S G E S M INUMTRSIMNRR Nrm TVbpt Qlt Q11 OM Q11 a11 022 11 .1W KRE35RaMCN CIERkCRNxMma PT FW4M RJ KR LOiR UaEATCRlCnaz RPZEFA=C MI0N MSXHR 10 10 10 10 10 10 10 10 9SOl -0Q=

-M2 8 9 10 1 4 9 9 7.67 1201 -*0l11 ZH-2 5 5 10 5 5 10 5 45 3 11.701 MNHR 0 0 0 0 0 0 0 0 1.5Ot -38117 N P3 aQ11 Q1 Q12 Q Qall 02 Q11 1 VBOBSM CklOECNJTAS PRINWNM RF HR LCTrE MER 10 10 10 10 10 10 10 101o0E'M Q0M CC3i1 2 2 1 5 5 3 4 2899 1.SZM -29 SIPFW7 7 5 5 4 5 6 6 5444 2C -1.6M19 MN-ER 0 0 0 0 0 0 0 0 t7S04 -a750 48112 SderdYB RSprdi N d iCbwkm 4 DgemsdFmetrr 2 RdBrda. 001=

Figure 30: BVPS-1 Post-EPU SLIM Worksheet Group 15

L-05-140 Enclosure 1, Attachment 3 Page 1 of 11 Attachment 3 to RAI 2.a.

BVPS-2 Pre-EPU SLIM Worksheets

L-05-140 Enclosure 1, Attachment 3 Page 2 of 11 Beaver Valley Unit 2 - Group 1 Human Actions Evaluation PERFCRMANX SHING FACTCRS PERFMAEl ESHAPIN3 FACICRS C P C P I P 0 R I P 0 R N R M 0 T N R M 0 T T E P C R T E P C R E C L E A S E C L E A S R E ED I T R E E D I T F D X U N T R F 0 X U N T R A I I R I I E S A I I R I I E S C N T E N M S U C N T E N M S U E G Y S G E S M E G Y S 0 E S M Ncrm PSFVgb" 0.118 0233 0.11e0.116 0116 0233 0.07 1 OPEATCOR ACTS PSFRA1NGS Ft HER LOG(}ER FSFWSGHTS MAXHER 8 8 a a 8 a 8 8 48C5-01 -3.19E-01 ZF{PRI 2 8 4 2 3 9 6 565 3.44E02 .1.46E400 ZHEPR1 5 10 5 5 5 10 5 45 ZFESM1 5 8 4 5 5 7 5 6.05 5.3SE42 -1278E00 ZHESMI 5 10 5 5 5 10 5 45 DEWAI 7 8 7 5 5 6 5 640 793E-02 -1.10E.00 ZEWNAI 5 10 5 5 5 10 0 40 zA3 7 8 7 5 5 6 5 6.40 7.93S02 -1.19E.00 ZHEWA3 5 10 5 5 5 10 0 40 ZDEV5 7 8 7 7 10 6 6 728 214E01 -6.70E-01 De.NA5 5 10 5 5 5 10 5 45 MANHER 2 2 2 2 2 2 2 2 5.72E44 -3.24E400 NORMA= PSF 0.116 0.2330.116 0.116 0.116 0233 007 VWGHTS CALIA1CNTASKS PSF RANIS FLI HER LOGN(R)

MAXHER a a a 8 a 8 8 8 1.00 0.9E4.00 FERH OE1 4 6 4 4 5 4 4 4 5814 4.31E03 -2.37E800 STPEORM5 7 7 8 5 8 8 6 7.1S28 124E01 907E-1 MN HER 2 2 2 2 2 2 2 2 1.935-03 -39 E800 CatW 4 2167171 StdEn dYEst 04119716 RSqmd 0939482569 Na d Cbwm. 4 Dee ofFrneedo 2 X Ceffidan(s) 0.487245984 Sd Errd Cod. 0 087U3M2 Figure 31: BVPS-2 Pre-EPU SLIM Worksheet Group 1

L-05-140 Enclosure 1,Attachment 3 Page 3 of 11 Beaver Valley Unit 2 - Group 2 Human Actions Evaluation PERFORJ1MAC SHAPING FACTORS PUF AEMSHARNG FACTORS C P C P I P 0 R I P 0 R N R MO T N R M 0 T E P C R T E P C E C L E A S E C L E A S R E E D I T R E E D I T F 0 X U N T R F D X U N T R A I I R I I E S A I I R I I E S C N T E N M S U C N T E N M S U E 0 Y S G E S M E G Y S G E S M NamPSFV¶(kl 0111 0111 om 0111 C111 0222 0.111 1 PERATORACTIN PSFRANINGS FU HER LO(1R) OPERATCRACTONS PSFGHTS WAXHER 10 10 10 10 10 10 10 10 1,54E-M 413E-01 Z1HES1 1 7 7 a 9 3 4 52m 1.04E4-2 -1.9SE40 ZHS1 5 5 10 5 5 10 5 45 zS2 1 8 a 8 9 4 5 61111 1.71E4-2 -1.77E400 ZH42 5 5 10 5 5 10 5 45 ZH158 1 8 8 8 9 5 7 &5559 Z20EC02 A1.0E400 ZHE-S3 5 5 10 5 5 10 5 45 1

1S4 8 8 a 9 8 8 7.3333 3 415.2 . 475E0 33104 5 5 10 5 5 10 5 45 33EsL4 2 8 8 9 9 7 8 7.33 341152 -1.47E-0O ZHEI4 5 5 10 5 5 10 5 45 8HEX72 a 9 10 1 4 9 9 7.e7 4.12E-2 .1.39E.00 2HEMT2 5 5 10 5 5 10 5 45 DEXT4 . 8 9 10 5 4 9 9 81111 52902 *128E40 afXT4 5 5 10 5 5 10 5 45 MN HER 0 0 0 0 0 0 0 0 S44504 -328E.0 N CPAUEPSF 0111 0111 om Q111 0111 e.m Q111 I VMGM~

CGuHRATION TASKS PSFRANMNGS FU 11ER LOG(tER)

MkX HR 10 10 10 10 10 10 10 10 5OOE-01 .3015E DC2E1 2 2 1 5 5 3 4 2 89 1.59603 -Z82E+00 EPaLi(1) 1 a 8 8 9 4 5 61111 zoOE-03 .270E.00 STP HECR07 7 5 5 4 5 e 6 544444 zOBE02 1.68E.00 MN HER 0 0 0 0 0 0 0 0 1.5 3-03 -2 825.4 NOME Re O C -3 2649529 (1) RANRGSARETHOSE FORSWILAR SWETdYESI 089738723 ACTIONINBV2(21E3S2) R Sq.md Qess7s7e8 No d Obsava S Do"" d Frenni 3 XCMoefdes) 0245075073 SW d E d Cod. 0.09333B437 Figure 32: BVPS-2 Pre-EPU SLIM Worksheet Group 2

L-05-140 Enclosure 1,Attachment 3 Page 4 of 11 Beaver Valley Unit 2 - Group 3 Human Actions Evaluation PERFCMAWE SHAPING FACTCRS PEV W SHAWPNGA CTCRS C P C P I P 0 R I P 0 R N R M 0 T N R MO T T E P C R T E P C R E C L E A S E C L E A S R E E D I T R E E D I T F D X U N T R F D X U N T R A I I R I I E S A I I R I I E S C N T E N M S U C N T E N M S U E G Y S G E S M E G Y S G E S M NamPSF'Ats 0.111 00o6 0111 0111 0.1r7 om em 1 CPERATaRAcTnCNs PSFFRANGS FUi HER LOG"P) CERATCRACnCNS PSFVEGHTS MAXHER 10 10 10 10 10 10 10 10 Z16E41 466E-01 ZHEFL2 4 1 8 5 10 8 8 7.1667 &7oE-o2 -1.17E+W Z-EFL2 5 0 5 5 10 10 10 45 ZHERES 1 2 8 9 9 7 7 67222 55e-o2 .125E+0 ZHRES 5 5 5 5 5 10 10 45 MNHER 0 0 0 0 0 0 0 0 347E03 -246E-0 NOCQMALZPSF 0.111 0.056 0.111 0.111 0167 om em VYEKs CAURATIN TASIG PSFRA0NGS FU HER LO(1n MAHER 10 10 10 10 10 10 10 10 1.WOE+00 0O&E+00 STP 0f1 6 4 6 3 10 10 3 6 4444 1.80-02 -1.74E+0W FERM RE7 6 7 6 8 e 5 8 6.50 1.32E-02 -1.88E+00 MINHER 0 0 0 0 0 0 0 0 80a0o3 2.10E0 Regess1 O#

Coftagm -2.45904629 StdErrdYEst 074585100 R Sqiaed 0.0132401 No. d Cbsmabxs 4 Degreeof Freftm 2 xCoe ts) 0Q17s35154 SWErrd CcH. 0.10326328 Figure 33: BVPS-2 Pre-EPU SLIM Worksheet Group 3

L-05-140 Enclosure 1, Attachment 3 Page 5 of 11 Beaver Valley Unit 2 - Group 4 Human Actions Evaluation PERFMVNOE SjNt*3 FACRS PERFOIRANCE SWP NO FACTORS C P C P I P 0 R I P 0 R N R M 0 T N R M 0 T T E P C R T E P C R E C L E A S E C L E A S R E E D I T R E E D I T F D X U N T R F 0 X U N T R A I I R I I E S A I I R I I E S C N T E N M S U C N T E N M S U E G Y S G E S M E G Y S G E S U NamPSFUYM" 0.125 Q1125Q125 Q.1250.125 Q125 025 1 OPEPATcRACTIORS PSFRAMNSS FU HER L0G(1 OPERATOt IACONS PSF VElTS MAXHER 10 10 10 10 10 10 10 10 1.76E-t -7.56E-1 ZIHfUt 2 4 8 4 8 3 8 5.38 597E5-3 22E4W 5 5 5 5 5 5 10 40 ZFU2 2 4 8 4 8 3 8 5.38 5975-03 -222E500 5 5 5 5 5 5 10 40 Wf3 2 4 8 4 6 7 8 58 86043 -207E503 ZFEMN 5 5 5 5 5 5 10 40 ZIEJ4 2 4 8 4 6 9 8 813 1.03502 -1.99EC0 5 5 5 5 5 5 10 40 ZHEVW1 2 5 8 6 8 0 8 5.38 597E-03 .22250 22DM1 5 5 5 5 5 5 10 40 MNHER 0 0 0 0 0 0 0 0 1.17Et!4 .3+935.00 tMAlNPSF 0.125 CQ125Q125 0.125 0.125 Q125 0.25 VYSGHTS CAUJRATIONTASKS PSFRAMNJtGS FU HER LOG"70 MAKFER 10 10 10 10 10 10 10 10 1.00E.1 .1.00 STP HERC4 3 2 1 8 5 6 6 4625 982E-04 -301E.0O TMHUtEt(1) 2 4 8 4 6 4 8 550 624E402 .1iE+0 tERM HECT3 4 6 3 3 3 3 3 350 1.15E-03 -294E+0O MtN FER 0 0 0 0 0 0 0 0 1.00E04 A4 .00E NOTE Regessic Q 1 Owstat -3930Sf70 (1)RA'KNGSARE THOSE FOR SIMIUt Std Err d Y Est 0.6e739M22

/'CTtON INB9 (ElM RSqaed 0.797 NaLcoftservabs 5 Deew d FnWn 3 XCdWldo1(s) 0.317487722 Sd BTdCod. 0.09231806 Figure 34: BVPS-2 Pre-EPU SLIM Worksheet Group 4

L-05-140 Enclosure 1, Attachment 3 Page 6 of 11 Bcavcr Valley Unit 2 -Action Group 5 Human Actions Evaluation PUF M 34 92 V E SqPAP FAC C P C P I P O R I P 0 R N R M O T N R MO T 7 E P C R T C PC C R E C L E A E C

C A R E E0 I R E E 0 I F D X U N T R F 0 X U N 7 ft A I I R I A I I R I I a S C I C N T E N U N T E N U E S U I G Y S a C 0 Y S 0 E 8 U orz ol^s el 0145 nlu ol4 osz OPRATORACn PSFPNT IFU 1HCR . 0" CPEPATORACIIONS o 10 10 10 10 10 10 0720r01 .1 1142 WI41 2 2 2 O 2 201 12 43*7EG0 253 U^XHER 2 2 2 0 2 201 33604 21@S2 6 7 .2 461.02 35 DOW2 2 I 2 2 5 430 2351E45 2 1 7 7 2 4 8 467 5J86-0 4226E02 34 7 2 5 55 5 5 5 51 2 4 5 2 3 4 301 912004 4304E102 8

2140 2 a a 3 4 4 70 48243 231E010 I 1 2* 4 I 3 3 3 242 51E04 2w10 55 7HECSI 7 7 7 7 a 6 614 26E402 .1 GRE.0 2wCSI 7l1 2 2 7 1 3 426 3252E4 -2461.02 25 I e el 1 2 4 e 4 30 32243 2 27 5 3 3 1 2 2 4 257 57-04 4323EC00 721 Y ZDM 2 1 34 a 5 6 45N 1E2003 421.E£02 721 a 2 2 7 a 457 42042 .2Yffl1(V 20 ZFM 2 2I S 2 5 I 5 32J 122E04E `56 2'4 I S 2 3437Ed00 3 2 5 32 122042 zMMI ZHEOFI 2 IO I 2 2 I 5 201 3 37504 35 D21 2 4 2 5 343 122E42 73f OF2 25 2 22 5 3

5 5 265 21200E 35 35 1 47 2 2

2 5 2JG 7010 015 015 01 4 WA 51 51 I15 34 25 Z11 b f 2 2 3 2 5 221 4461.04 -2 IN-CO 212 25 I 1 5 25 9 2 5 513 751E03 -3 35E+G0 34

2 5 2 1 2 220 464E04 .5701024C 21fRE 35 ss 4 2 2 314 150414 134 ZFERE2 DMI0 4-26E.02 OK-CO 4 2 2 314 10E103 ss 5 1 2 268T 76101E Z"M 7 1 2 7 1 5 *414 2603 34 1 6 5 4 2 6 4 57 4 55E03 203 IC 4 34E4CO 10 I 10 602 12E001 DIETM (7IX) I 2 O 1 2 267 71. 73f9m (DEIXI) 214FER I 6. 6 O 0 0 0 45O45 NOMIJZEWPS MNI'TS CSIIDRATON TAEO FU HER [(WF I0 10 10 10 10 10 10 10 9eGEN0 J158E02 T7 HR (1) 2 I 5 2 4 5 S 35 *741E42 TU HSR2O25 2 S 5 3 4 2 5 143 127E.4 sTP W410m 6 6 4 5 e 0 8 657 435 2 .136E100 TM HCI (3) 2

2 3 2 I 4 301 127*.04 4920E00 SPWHEOI 5 3 4 3 3 3 4 367 821 1

STPHOS1N 4 2 2 3 4 4 4 S72 23JE45 .4*7E10 WNHCR 0 0 0 O 0 O 0 a 1 20E44 NW P.V.0. 0j" (t) RAMOMARE T13SEFORSHL.R CO 4 .4344430 ACM INIM (RARI) S34E5 dYII 5.792447245 (3)RVMeCSARE7FQ6EFORS3UR R Sd e 0713M ACr4CNPiW.2I N. d O."" J R;SO ARETFQS FOR53fUR C O^7_d rd 6 ACIICNNqIN (Z1EW) x 021273 433 SMd C&d

0. 010287014 Figure 35: BVPS-2 Pre-EPU SLIM Worksheet Group 5

L-05-140 Enclosure 1, Attachment 3 Page 7 of 11 BeaverValley Unit 2 -Action Group 6 Human Actions Evaluation PECFAMCE SHAWtN FSCTM IPEWORF E SHWAPNG FACTR C P C P I P 0 R I P 0 R N R M 0 T N R M 0 T T E P C R T E P C R E C L E A S E C L E A S R E E D I T R E E D I T F D X U N T R F D X U N T R A I I R I I E S A I I R I I E S C N T E N M S U C N T E N M S U E G Y S G E S M E G Y S G E S M PSFV\eid" Q143 Q143 0.143 Q143 0143 0 02M PfRATfCRACTOS PW RANNGS FLI HER LOG"U OfERATORACTNKS PWVVSGHTS MAXHM 10 10 10 10 10 10 10 10 374E101 -4.27E-01 DEOA1 2 0 2 0 3 2 7 300 3 84E43 .2.42E00 ZE-OA1 5 5 5 5 5 0 10 35 MN IER 0 0 0 0 0 0 0 0 539EW04 a27E+00 NOILIZEDPSF 0143 0143 Q143 0143 0143 QC00286 VWOGRTS CA1JMATIONTASK PWRNS FU HER LOS"T MAX HER 10 10 10 10 10 10 10 10 5(0E41 -301E01 DCZHEOE1 (1) 2 0 2 0 3 2 7 3Q0 1.70E-03 -277E+00 FERt HERE2 3 4 3 3 5 5 8 0488 1.18E42 -1.30 MN ER 0 0 0 0 0 0 0 1 0 1.Q3E403 43 °E° NDTE Regessbnu41Pt (wsw1 -2M3E00.

(1)RAWKNGS ARE nTiSE FOR SMLAR Std Er dY Est 32749E01 ACTION INBW92 gl1) RSwafd 9 5216E011 No cdO usi5= 4 Dxee d Fnexn 20OC0 XwMddeft(s) 02841le745 9d Err d . 0.04503M Figure 36: BVPS-2 Pre-EPU SLIM Worksheet Group 6

L-05-140 Enclosure 1, Attachment 3 Page 8 of 11 BeaverValley Unit 2 -Action Group 7 Human Actions Evaluation PERFMNAEiAIRNG FACTrDS P9EtE SFIAFIfNGFACTO C P C P I P 0 R IP 0 R N R M 0 T N R M 0 T T E P C R T E P C R E C L E A S E C L E A S R E E D I T R E E D N T F D X U N T R F D X U N T R A I I R I I E S A I I R I E S C N T E N M S U C N T E I N M S U E G Y S G E S M E G Y S G E S M Nmn PSFV 1ts G12 G24 G14 0.12 012 G12 G14 1 OPEPATORACnCNS PSFPANNGS RF IER LOG"R) PEATORACTOCNS SNFVAGS AHER 10 10 10 10 10 10 10 10 529Et1 -27E01 D1E= I 5 8 5 8 2 8 5.0Q 1.84E-02 -1.74E+00 21DS 5 10 5 5 5 5 10 45 ZfMt 1 5 7 3 2 5 2 377 7.52E3 .212E+00 ZMCI 5 10 10 5 5 5 5 45 ZHE-A2 3 7 2 2 2 5 6 424 1.04E42 Ag.BE#00 ZHEQA2 5 10 5 5 5 5 5 40 D{IA3 3 8 7 9 9 9 8 7.35 8.67E2 1.Q0E+0O D ELA3 5 10 5 5 5 5 5 40 2HEC2 5 9 5 3 3 7 8 614 378E42 .1.42E0.0 21E2 5 10 5 5 5 5 5 40 ZH-SE3 2 9 1 2 5 1 6 4.35 1.12E42 *1.95E.C0 DfESE3 5 10 5 5 5 5 5 40 Z-ESE4 2 9 2 2 7 1 6 4.73 1.45E42 -1.84E0.0 ZFESE4 5 10 5 5 S 5 5 40 21-Et21v-6) 2 9 1 2 5 1 e 4.35 1.12E4C2 -1.95E.0 21-Em MI 5 10 5 5 5 5 5 40 21-Er3 2 9 2 2 7 1 8 4.73 1.45E402 .1.84E0.0 ZTB3 5 10 5 5 5 5 5 40 UN FER 0 0 0 0 0 0 0 0 573E404 424E.00 N DM WPSF Q122 0243 0135 0122 Q122 Q122 0135 Meaxrs CAUBRATIONTASKS PSF RANS FU FER LO(3GFR MAXIER 10 10 10 10 10 10 10 10 1.QOOE >ODE.0 STP -EX 6 4 2 3 4 7 8 476 8880E43 *205E+0 aR"8(1) 5 9 5 3 3 7 6 5.s 1.QCE2 *200+00 DCZ-EE03 7 5 4 7 6 6 8 e.oo 5.49E-42 -1.2500 MN HER0 0 0 0 0 0 0 0 .OCE43 -alOExl0 NOMl Ressl Ojt ca~ta1 -324218457e (1)RqNNGSARE8ThSEFMRSMILAR St ErrdY Est 0.398545 AMCTON4IN BV (Z-EOP2) R SqAn-e Q51099O Ntad Cbsim 5 DV" d Frned= 3 XCwidas) M2U57372 SWdEsrdc W. 0Q55441061 Figure 37: BVPS-2 Pre-EPU SLIM Worksheet Group 7

L-05-140 Enclosure 1, Attachment 3 Page 9 of 11 Beaver Valley Unit 2 -Action Group 8 Human Actions Evaluation PE3RRAAt SH4AItNFKCTORS PERCRNAJ SWJ1NG FACRS C P C P I P 0 R I P 0 R N R M 0 T N R M 0 T T E P C R T E P C R E C L E A S E C E E A S R E E D I T R E E D I T F D X U N T R F D X U N T R A I I R I I E S A I I R I I E S C N T E N M S U C N T E N M S U E G Y S G E S M E G Y S G E S N Norm PSF at" Q128 0128 0128 0116 0.116 0.25z Q128 I CPERATOR AClONS PSFRAN8NGS FU HER LOM OPERATOR AcnONS PSFVf TS MAXHER 10 10 10 10 10 10 10 10 353E-O1 -453E-O1 ZFECD3 2 3 3 2 2 1 5 238 1.46E-03 -2.84E.00 5 5 5 5 5 10 5 40 Z-ECC4 2 5 8 5 6 4 7 512 1.04E-02 .196+.00 3-1E=

Z4ECD4 5 5 5 5 5 10 S 40 ZFEIAt 1 3 2 5 2 7 3 376 31E503 -241E503 2HEIA1 5 5 5 5 5 10 5 40 ZFEOT1 1 0 1 0 0 5 6 23D 1.37E-03 -280E403 5 5 5 0 5 10 5 35 ZE-REE 1 2 2 6 2 4 5 323 266E-03 Z-57400 2-ER£E 5 5 5 5 5 10 5 40

{1 0 1 0 0 5 7 243 1.51E-03 -2.&04 5 5 5 5 5 10 5 40 D ESE1 (M-ECCt, DEC) 2 4 2 1 4 7 5 4.03 4.75E-03 -Z32E400 ZtESEI tD ECC1, 2HE1 5 5 5 5 5 10 5 40 ZHESLI 2 1 5 2 3 7 6 4.16 525E-03 -2280403 2HELi 5 5 5 5 5 10 5 40 ZFESL5 2 4 5 2 4 8 8 S17 1.09E0-2 *1.56E+C0 ZHESLS 5 5 5 5 5 10 5 40 21EWA2 2 3 7 4 2 5 5 4.15 5.20E-03 -228E000 D-EWA2 5 5 5 5 0 10 5 35 Z-EWA4 2 6 7 7 10 5 6 594 1.80E-02 .1.72E+50 ZHEWA4 5 5 5 5 5 10 S 40 MINH-ER 0 0 0 0 0 0 0 0 2.61E-04 4.3580.E NOR9UZED PSF 0128 0126 0.128 0.116 0116 0258 0.128 WVlG11TS CAIJRATIONTASKS PSFRAWNGS FU HER L1-"

M4XHER 10 10 10 10 10 10 10 10 1.Q6E4W 0.03E*00 STPHECSL1 5 3 4 3 3 3 6 377 213E-03 -2.67+00 FE£M HERS1 2 7 2 3 2 4 6 378 1.75E-03 -276E400 STPHEOSOt 6 4 6 3 10 10 3 6850 1.80-t2 *1.74E403 C 3HOX1 (1) 2 1 5 2 3 7 6 4.16 3.20E-03 -Z45E+.0 MNHER 0 0 0 0 0 0 0 0 1.0SE-03 43.03E4C FR*5iOs OAxt Cw 1t -3583050682 (1)RA*KNGS AREITIOSE FOR SMLAR SWErrd Y Est 0455189834 ACCON INEW2 (ZHELI) RSwared 0Q8675190t3 Na d Cbsmcvlu 6 DCq d FRedon 4 X elid.s) 0.31302434 StdDT dCod. 006t141234 Figure 38: BVPS-2 Pre-EPU SLIM Worksheet Group 8

L-05-140 Enclosure 1, Attachment 3 Page 10 of 11 Beaver Valley Unit 2 -Action Group 9 Human Actions Evaluation PRFOFAIE SAFING FACTO PERFOMWE S9ARNG FCTORS C P C P I P 0 R I P 0 R N R M 0 T N R M 0 T T E P C R T E P C R E C L E A S E C L E A S R E E D I T R E E D I T F D X U N T R F D X U N T R A I I R I I E S A I I R I I E S C N T E N M S U C N T E N M S U E G Y S G E S M E G Y S G E S M NormPSFWat 0 0.176 0.176 Q176 Q176 0118 0175 1 OPERATaRACRCAS PS RAN SS FU FIER LOG"3EI OPERkTcPCRAXE8 PSF VA3GHrS MAXFIER 10 10 10 10 10 10 10 10 (28O1 -22E-01 Z1ED 2 9 3 3 7 3 9 5.82 7.65E42 1.12Edw) 0 5 5 5 5 5 5 30 2}EC07 2 9 8 5 8 4 9 7.35 1.65Et -7.82E401 0 5 5 5 5 5 5 30 zIEW8O 2 4 5 4 5 2 1 359 248E42 41GIE.W ZFECUD5P 0 5 5 5 5 0 5 25 MN KER 0 0 0 0 0 0 0 OO0 4.05E03 *239C00 0 Q176 0178 0176 Q175 0118 0178 CAUERATIONTASiG PSFRANON5 FU FER LOG(E MAXIER 10 1010 10 10 10 10 10 1IE+00 OO0C0 STPWEOO 6 6 6 5 6 8 9 ft.582 4.3SE-2 *1.3$E+00 EPRISM1(1) 2 9 3 3 7 3 9 58235 1ODOt -. 00E+C MNFER 0 0 0 0 0 0 0 0 5C4E-03 230E+00 NO1TE~ RegessciaOutput Omftt1 -a387M1371 (1)RAN0I-3NS ARETIV FORSIMLAR tdErr Y Est 0.3MM95 ACflION INSW2(ZI-E RSqtnmd 09151131 Na&ofCtbswafcs 4 D~mdAEixi, 2 XCefdert(s) 0.219,17541 td ErrdCoe(. 01047187948 Figure 39: BVPS-2 Pre-EPU SLIM Worksheet Group 9

L-05-140 Enclosure 1, Attachment 3 Page 11 of 11 Beaver Valley Unit 2 - Group 10 Human Actions Evaluation PERF0RfNE SF-N3 FACTCRS . PERFORNME SHP NG FACTORS C P C P I P 0 R I P 0 R N R M 0 T N R M 0 T T E P C R T E P C R E C L E A S E C L E A S R E E D I T R E E D I T F D X U N T R F D X U N T R A I I R I I E S A I I R I I E S C N T E N M S U C N T E N M S U E G Y S G E S M E G Y S G E S M Norm PSFWigits 014 014 0.29 0.0m 0.14 014 0.14 1 CPERATORACTONS PSFRA*N2 S FU HER LO(R) OfERATORACTONS PSFWBGHTS MkXHER 10 10 10 10 10 10 10 10 9.96E-01 -1.78E43 ZHEXTI a 9 10 1 4 5 8 7.71 3.56E- *1.45E.00 ZHEXTI 5 5 10 0 5 5 5 35 UN HER 0 0 0 0 0 0 0 0.00 4.67E-07 433E+50 N-E1JEDPSF 014 014 0.29 0.00 014 0.14 .14 CAUSRAT1C4CN TASKS PW RANNGS FLU HER LO3ER MAXFER 10 10 10 10 10 10 10 10 1.00E+00 0.0o SEABROCKON 0 0 1 o 2 0 0 0.5714 1ao0-s 4.exo MN IER 0 0 0 0 0 0 0 0 5s5E-07 4.3010 Reqwson oL(4x CSart 433E+00 Std Errf Y 4.29E-02 RS.mes J9927115 NaLd Csvba 3 DOman ofFmadom 1 X COffides) 0O 09685998 Std Err f Coc. 01 79403158 Figure 40: BVPS-2 Pre-EPU SLIM Worksheet Group 10

L-05-140 Enclosure 1, Attachment 4 Page 1 of 12 Attachment 4 to RAI 2.a.

BVPS-2 Post-EPU SLIM Worksheets

L-05-140 Enclosure 1,Attachment 4 Page 2 of 12 BEAVERVAUEY UNT 2 - GROP 1HUVIAN ACTlONS EVALUATION PETRRE SPINGFACMRS PERFOWE~ 9'A'1NG WrMXS C P C P I P 0 R I P 0 R N R MO T N R MO T T E P C R T E P C R E C L E A S E C L E A S R E E D I T R E E D I T F D X U N T R F D X U N T R A I R I I E S A I I R I I E S C N T E N M S U C NT E N M S U E G Y S G E S M E G Y S G E S M INPlJT7OISnfNFOR NrmPSFlWIUs Q116 0233 11 0116 0116 0233 007 1 KRD0tSTREJBllCN CPERATCRAMCAN PSFRANGNSS FU HER L OQH9G WERATCRnCICNS PSMMAIGM5 RAN FACTOR ELAN MSXKR 8 8 8 8 8 8 8 8 4.80601 -alg-01 ZFR1 2 8 4 2 3 8 6 5,42 26SE-2 .1SE.c 5 10 5 5 5 10 5 45 5 1.64602 ZEf" 5 8 4 5 5 7 5 6.05 53E402 -127E.00 5 10 5 5 5 10 5 45 5 3 HDEAI 7 8 7 5 5 6 5 640 7.gX,2 -1.10E4O) 5 10 5 5 5 10 0 40 5 4.91E42 ZHDM D-EV3 7 8 7 5 5 6 5 6.40 7.90C2 .1.1CE+00 5 10 5 5 5 10 0 40 5 4.91E402 Z)E5 7 8 7 7 10 6 6 728 214601 47a0l ZU5 5 10 5 5 5 10 5 45 3 1.71E-01 MN KR 2 2 2 2 2 2 2 2 572-04 -324E.OD NCRlq PSF Q116 0233 0.118 a118 Q118 0.233 0.07 1 DEGWS CAtlATICNTARG PSFFR*NSOS FU HER LOC-EF~

M&XKR 8 8 8 8 8 8 8 8 1.0X0L 00f0E FEWI CEI 4 6 4 4 5 4 4 4.5814 4.31603 -2.37E40)

STPKCER5 7 7 8 5 8 8 6 7.1628 1.2401 -9.07E-01 MN FER 2 2 2 2 2 2 2 2 1.0063 -34aE.0 FsdCt1O1t r

cm~ta-4.2167171 Sbd0rdYEst Q411087816 RSqaed Q9348YG3 ND. d 4 DegvesodFrayfrn 2 Xlidst(s) Q487245M4 W BTd W. 0037443M Figure 41: BVPS-2 Post-EPU SLIM Worksheet Group I

L-05-140 Enclosure 1, Attachment 4 Page 3 of 12 BEAVERVALLEY UNIT 2 - GROUP 2 HUMAN ACTIONS EVALUATION PERFORMAN6E SHAP1NG FACTORS PERFORMMICE SHAPINGIFACTORS C P C P I P 0 R I P 0 R N R M 0 T N R M 0 T T E P C R T E P C R E C L E A S E C L E A S R E E 0 I T R E E 0 T F D X U N T R F D X U N T R A I I R I I E S A I I R I I S S C N T E N M S U C N T E N M S U E G Y S G E S M E G Y S G E S M 14INPTOMRISCAAN PC Norm PSF\1iet$gs 0.111 0.111 02 olli 0.111 om 0.111 1 HER DISTRILJTON OPERATOR ACTIONS PSF RANIQNGS FLI FER LOG(QER) CPERATOR ACflONS PSF WEIGHTS RANG)E FACTOR MEDItAN MAXHER 10 10 10 10 10 10 10 10 1.54E-01 413641 ZHEOS5 1 7 7 6 9 5 4 5.6567 1.33E-02 -1.885E40 5 5 10 5 5 10 5 45 5 8 26E-03 ZFEOS21 8 8 8 9 2 5 5.6'67 1.33E-02 -1.885E40 5 5 10 5 5 10 5 45 5 8 28E-03 ZHEOS3 1 8 8 8 9 3 7 6.1111 1.71E-02 -1.77E400 ZHEOS3 5 5 10 5 5 10 5 45 5 1.05E-02 ZHEOS4 1 8 8 8 9 8 8 7.3333 341E5-2 -1.47E+00 ZI-50S4 5 5 10 5 5 10 5 45 5 Z11E-02 ZHESL4 2 8 8 9 9 5 8 6.8889 26SE-02 -1.58E+00 5 5 10 5 5 10 5 45 5 1.65E02 2-IEXT2 8 9 10 1 4 9 9 7.6567 4.12E-02 -1.39E+00 5 5 10 5 5 10 5 45 5 255E-02 ZFIEXT4 8 9 10 5 4 9 9 8.1111 5.29E2 .128E500 5 5 10 5 5 10 5 45 5 3.28E02 MN IER 0 0 0 0 0 0 0 0 5.44E44 -. 26E40 NCRMAUZE PS: 0.111 Q111 0222 0.1110.111Q2m Q111 VOGHT CAUBRATION TASKS PSF RANKINGS FU HER LOG(FIER)

MAX HER 10 10 10 10 10 10 10 10 5.OE-01 4.01E-01 DCZHEO51 2 2 1 5 5 3 4 28889 1.50E-03 -82E+00 EPRILI(1) 1 8 8 8 9 4 5 6.1111 ZOOE-03 -Z70E400 STP HEOR07 7 5 5 4 5 6 6 5.4444 Z08M-09 -1.685E00 MN HER 0 0 0 0 0 0 0 0 1.50E-03 -2.82E00 NOTE, RPessgeOuw Ca1 -3.264095629 (1) RANINGSARETHOSE FOR SMLAR Std En dY Est 0.69738723 ACTION INB92 (Z0 RSqaed 0 69i79788 No, d OfvAan 5 DeMrees d F&rn 3 X Coeffide(s) 0.245075073 SIdEnf Cef. 0093338437 Figure 42: BVPS-2 Post-EPU SLIM Worksheet Group 2

L-05-140 Enclosure 1, Attachment 4 Page 4 of 12 A\IRVAIlEYI'r2 - GtLP33HLNVPCN1N;EVLLUI~CN PEaWSHSRMFXGS PERM C P C P I P 0 R I P 0 R N R MO T N R MO T T E PC R T E P C R E CL E A S E CL E A S R E E D I T R E E D I T F D X U N T R F D X U N T R A I I RI I E S A I I R I I E S C N T E N M S U C N TEN M S E G Y S G E S M E G YS GE S M INIORNRR FbmrPSFVW s C111 Qa 01t11 111 Q167 Q22Z 0m2 1 HR-DCSTROLCN CPEA\TOvPCNS PSTR4N3S RI R L0MBF CPETCRM PSFV'SG-S MXSR tO 10 10 tO 10 10 10 10 216M -des MR2 4 1 8 5 10 8 8 7.167 6706M -1.17E+CO 2 5 0 5 5 10 10 10 45 5 41!4 ZH31 1 2 8 9 9 8 7 69444 812 -121E'00 2H 5 5 5 5 5 10 10 45 5 a7MM MN-R 0 0 0 0 0 0 0 0 a47E6 -243TD N 0il)PF 111 003 0Q1 Q1tt Q167 Q2m a 1 MlGM 0U1E1A0CNTAS9 PRFRiNS R L W9HR 10 10 10 10 10 10 10 10 1.0 00-4 STPH;Ot 6 4 6 3 10 10 3 64444 1.8Z -1.74E400 FEAIRE7 6 7 6 8 6 5 8 86 1.32 -1.88M MNFHR 0 0 0 0 0 0 0 0 8M3 -21iE

-24S9 WerdYEs Q745E5100 COMMt Nd dCmas 4 DqjdR+/-inm 2 XtlfidO4( atM5154 u4 BdP. S1G Figure 43: BVPS-2 Post-EPU SLIM Worksheet Group 3

L-05-140 Enclosure 1, Attachment 4 Page 5 of 12 BEAWERVAUIBE UNT 2 - AC1ON GROUP 4 HUVIAN ACn1ONS EVALUAllON FBSCFTINWPMFACTORS RWNZES14INGFACTa;S CiP C P I P HR I P 0 R N R MO T N R M O T T E P C R T E P C R E CL E A S E C L E A S R E E D I T R E E D I T F D X U N T R F D X U N T R A I I R I I E S A I I R I I E S C N T E N M S U C N T E N M S U E G Y S G E S M E G Y S G E S M 1W7TTOR19HNFCR NormPSFVMl Q125 0.125Q125 Q125 Q125 Q125 Q25 I KReMsTRaMCN CEATCRA CNS PSFRANGS RI FER L CWFER CPEATCRACnONS PSFM8G-S WM FACTOR MtAN MkXHER 10 10 10 10 10 10 10 10 1.76- -7.55C-Z-EUJI 2 4 8 4 6 2 8 525 S45'43 -22SE4 5 5 5 5 5 5 10 40 75 Z57E43 ZEM22 2 4 8 4 6 2 8 525 5SA 3 -22E40 5 5 5 5 5 5 10 40 7.5 Z57SE3 ZH 2 4 8 4 5 8 5.63 ZFEMJ3 6 7.17EC3 -214E#CO ZH3AJ2 5 5 5 5 5 5 10 40 7.5 :3IE aHBU 2 4 8 4 6 7 8 588 a6a;{ -207E400 2YEM 5 5 5 5 5 5 10 40 7.5 406E YEVM1 2 5 8 6 6 0 8 538 597E603 -22M4M 5 5 5 5 5 5 10 40 7.5 282E03 MNHER 0 0 0 0 0 0 0 0 1.17E04 4 EIM Q125 Q125 Q125 Q125 Q125 0.125 025 1 CAJERA=NTASS PSFR*HNGS RI HER LOcX6 MWXEIR 10 10 10 10 10 10 10 10 1.a01 -1.OE40o STPHFrC4 3 2 1 8 5 6 6 4.625 9.82EO4 -3.01E400 TMHTIB(1) 2 4 8 4 6 4 8 550 6202 -1E40 FERA HBM 4 6 3 3 3 3 3 3.50 1.1503 -294E+OD MNIHE 0 0 0 0 0 0 0 0 1.(0ED4 4.OOE+M NOlM Rweaf OJPLL Oft 4 9305 (1)RA NFSAREASEFR SMLAR SWBrdYEs 022 ACTICN INMBV2 tM RS~mied Q7970 NhdCb5v& 5 Deg d A rrb, 3 XOltxdal(s) Q31748772 SdFud44V. aPosEPSMih Figure 44: BVPS-2 Post-EPU SLIM Worksheet Group 4

L-05-140 Enclosure 1, Attachment 4 Page 6 of 12 BEAVER VALLEY UNIT 2 - ACTION GROUP 5 HUMAN ACTIONS EVALUATION FERFORMAFE SHAPING FACTORS PERFORMANCE SHAPING FACTORS C P C P I P 0 R I P 0 R N R M 0 T N R M 0 T T E P C R T E P C R E C L E A S E C L E A S R E E D I T R E E D T N

F D X U N T R F D X U T R A I I R I I E . S A I I R N I E S C N T E N M S

U C N T E I M S U E G Y S G E S M E 0 Y S E S NI INPUT TO RISKNI4 FOR Norm PSFSdqIts

- 0.1450145 0.14 0.145 014 0.140145 SI HER 3STIfAlON OPERATOR ACTIONS PSF RAN0NGS FI HER F LOGE OPERATOR ACTIONS PSFWEIGHTS RANGE FACTOR MECtAN MAXHER 10 10 10 10 10 10 10 10 9.75E-01 *1.12E4-2 DHEAF2 2 3 3 2 2 0 2 2.01 3365E-4 4347E+03 ZHEAF2 5 5 5 5 5 5 5 35 10 126-E04 D EAF3 (ZHEMAI) 2 3 3 2 2 0 2 2.01 336E*-4 -3.47E.00 ZHEAF3 gZFEMA1l) 5 5 5 5 5 5 5 35 10 1.265-4 ZHECC1 2 6 6 7 2 2 5 4.30 33tE43 -2.48E500 ZHECC1 5 5 5 5 5 5 5 35 7.5 1.56E-03 2 6 7 7 2 4 6 487 SE82E-3 -224E+00 ZHECC2 5 5 5 5 5 5 5 35 7.5 Z75E-03 2 4 3 3 2 1 4 273 6.88E-04 4.16E+50 ZFEc 5 5 5 5 5 5 5 35 10 2.58E-C4 ZHECIt ZHE= 2 5 8 5 6 1 4 4.42 3.73E-03 -243E+.0 5 5 5 5 5 5 5 35 7.5 1.76E-03 1 2 4 1 3 3 3 242 5.05E-04 4.30E+00 ZHE02 5 5 5 5 5 5 5 35 10 1.99E44 3 7 7 7 7 7 e 6.28 237E-2 .1.62E+00 ZHES1 5 5 5 5 5 5 5 35 5 1.47E-02 2 7 6 4 7 1 3 428 325E43 -249E+00 ZHIEFLI 5 5 5 5 0 0 5 25 7.5 1.53E-03 ZHEC02 1 7 5 5 2 2 6 4.02 249E-3 -2.60E+00 1EHH1 5 5 5 5 5 5 5 35 7.5 1.18E-03 2 2 3 1 3 1 4 229 4.44E-04 -3.35E500 ZHEHHt2 5 5 5 5 5 5 5 35 10 1.67E-04 ZHEMA2 2 6 5 3 8 5 6 4.99 656-E03 -Z18E+.0 ZHEMA2 5 5 5 5 5 5 5 35 7.5 3.10E-03 DFIEOR2 afCB1 5 3 5 3 3 7 6 4.57 4.31E43 -2.37E+40 ZFIEOB1 5 5 5 5 5 5 5 35 7.5 2.04E-03 2 3 5 2 5 0 5 3.14 1.04E-3 .298E+C0 DHEOD1 5 5 5 5 5 5 5 35 7.5 4 92E44 2 4 5 2 3 4 5 3.57 1.59E-03 -2.8eE+0 ZHEOF1 5 5 5 5 5 5 5 35 7.5 7.51E-04 DFIERED 2 1 1 2 2 3 5 2.29 4 46E-04 4.335E+00 5 5 5 5 5 5 5 35 10 1.67E-04 ZHERR1 Di~EOR1 2 3 5 3 4 0 5 315 1.05E43 -298E500 ZHEORI 5 5 5 5 5 5 5 35 7.5 . . 4.94E-04 ZHEHH2 2 3 5 3 4 5 5 385 Z1IO-03 -2.68E.00 ZHEOR2 5 5 5 5 5 5 5 35 7.5 9.93E04 ZHEOSS 1 4 2 2 4 2 5 2.86 7.88E-04 -. 10E+00 ZHEOS5 5 5 0 5 5 5 5 30 10 Z56E04 0 0 1 5 3 2 5 Z29 4.46E-04 -. 35E+00 5 5 5 5 5 5 5 35 10 1.67E504 D-1ERE5 ZHEOD1 1 2 8 9 9 3 5 5.27 867E-03 -Z2SE.00 ZIERE5 5 5 5 5 5 5 5 35 7.5 4.Q9403 1 2 2 8 2 3 2 2.58 5.93E-04 .323E+00 DHERED 5 5 5 5 5 5 5 35 10 223E04 2 2 5 5 4 2 2 114 1.04E-3 .209E+00 ZHIERRI 5 5 5 5 5 5 5 35 7.5 4.89E-04 2 2 5 5 4 2 2 114 1.04E-3 -2.9E+00 ZHERR2 5 5 5 5 5 5 5 35 7.5 4 89E-04 ZHESE2 2 7 1 2 5 1 2 2.87 7.92E-04 4.10E500 ZFESE2 5 5 5 5 5 5 5 35 10 2.97E-04 ZHESES 5 4 5 2 7 1 5 4.14 282E-03 -2.55E+00 ZHESE5 5 5 5 5 5 5 5 35 7.5 1.33E-03 ZKS12 3 2 8 5 4 0 8 4.29 328E43 -2.48E+00 ZHESL2 5 5 5 5 5 5 5 35 7.5 1.55E-03 7 10 9 9 10 0 10 7.88 1.18E-01 -929E-0 ZHESL3 5 5 5 5 5 5 5 35 3 9.41E402 D,391 gFEC1) 2 7 1 2 5 1 2 2.87 7.92-04 -. 10E+00 ZHETB1(ZHEICI) 5 5 5 5 5 5 5 35 7.5 3.74E-04 IFER 0 0 0 0 0 0 0 0 4AE4-05 4.34E500 NRMLAZED PSF 0.145 0.145 014 0.145 014 0.14 0145 WeGHTS Figure 45: BVPS-2 Post-EPU SLIM Worksheet Group 5

L-05-140 Enclosure 1,Attachment 4 Page 7 of 12 FTRM Ri 6RR 1T-M 10 10 10 10 10 10. 10 10 9REM1 -459<

USWTNPS 2 3 5 3 4 5 5 38 47C-M 4ZEKD 1MMO 2 3 5 3 4 2 5 343 iZ7E-6 6 6 5 6 8 9 657 4aM -39EW 4-IEC SIP13P 1:B9CO 2 4 3 3 2 3 4 301 1zE-m tgE CO SPFEM 5 3 4 3 3 3 6 387 210 6 3 2 3 4 4 4 372 231E03 -26C-MNHER 00 0 0 00 0 0 1.CIEB -ORDO Nam RknQi+/-t OGrxt 43CD aJErdYt 072473 RStani 07471M PCrCNINBRO-EQ NMdCQbBTr 8 RNIFNM4E C rkdhmtrn 6 Xlxmd"4 0433OM 3iJrdQd. 06eui Figure 45: BVPS-2 Post-EPU SLIM Worksheet Group 5 (continued)

I

L-05-140 Enclosure 1, Attachment 4 Page 8 of 12 R39CPRNNSFACIFP= PCFJhTUS-fliNjFACUS CP C P I P 0 R I P 0 R N R MO T N R M O T T E PC R T E P C R E CL E A S E C L E A S R E ED I T R E E D I T F D X U N T R F D X U N T R A I I RI I E S A I I RI I E S C N T E N M S U C N T E N M S U E G Y S G E S M E G Y S G E S M IN1=lDRS/9 XR PF\WiS Q143 Q143 Q14 143 Q143 0 Q236 1 IfRDSTRICN CPUmicnCN PSFRPNNS Rl KR ACAsCS PSFV\BGfSS RPAEFA=CTU MON 10 10 10 10 10 10 10 10 37401 -42E01 2 0 2 0 3 2 7 3C0 38C-M alm 5 5 5 5 5 0 10 7.5 1.81E03

2'1G3 MNHR 0 0 0 0 0 0 0 0 53-4M NODP8F Q013 0143 014 143 014 OCS02E5 1 VOG-M C4VCNTA9S RJ H-R LQGBj 10 10 10 10 10 10 10 10 5C01 -301501 MNR(1)

MFXERA2 2 0 2 0 3 2 7 300 t71E. -277E.M 3 4 3 3 5 5 8 483 18602 -1.93ME MNI-6R 0 0 0 o o o o 0 1.S3 -300R (1)R4N*XKMASlFUM 9SMLAR SdEirdYE1 3274'01 ACKININDROEN R~tnled 95601 Nb dooans 4 DRiden 20 XQxffidfs) 024B745 SdErd~d. 0049 Figure 46: BVPS-2 Post-EPU SLIM Worksheet Group 6

L-05-140 Enclosure 1, Attachment 4 Page 9 of 12 BEAVER VALLEY UNIT 2-ACTION GROUP 7 HUMAN ACTIONS EVALUAllON PERFORMANCE SH-APING FACTORS PERFORMAhCE SiAPING FACTORS C P C P I P 0 R I P 0 R N R M 0 T N R M O T T E P C R T E P C R E C L E A S E C L E A S R E E5 D I T R E E o I T F D X U N T R F D X U N T R A I I R I I E S A I I R I I E S C N T E N M S U C N T E N M S U E G Y S G E S M E G Y S G E S M INPUTTO RISKaAAN FOR NormPSF %W" 012 0.24 0.14 0.12 0.12 0.12 0.14 1 HER DISTRIBLmON OPERATOR ACTIONS PSF RANKINGS FU FIER LOG(HS) OPERATOR ACTIONS PSFGHTS RANGE FACTOR MEDAN MAXHER 10 10 10 10 10 10 10 10 529E01 -Z76E-01 ZHECD5 1 5 8 5 8 5 8 5.45 Z36E02 -1 63E+00 ZH1ECDS 5 10 5 5 5 5 10 45 5 146E-02 ZHEaEt 1 5 7 3 2 5 2 3.77 7.52E-03 -Z12E+00 ZHEO1 5 10 10 5 5 5 5 45 7.5 3.55E-03 ZHELA2 3 7 2 2 2 5 6 4.24 1.04E02 -1.96E54 ZHEtA2 5 10 5 5 5 5 .5 40 5 5.43E-03 ZHEIA3 3 8 7 9 9 9 6 735 867E-02 .1.06E+00 5 10 5 5 5 5 5 40 5 5.37E-02 ZHEO02 5 9 5 3 3 7 8 614 378E-02 .1.42E+00 ZI-EMS ZHIEO32 5 10 5 5 5 5 5 40 5 Z34E42 ZHESE3 2 9 1 2 5 1 6 4.35 1.12E4-2 .1.95E+.0 ZHESE3 5 10 5 5 5 5 5 40 5 6 2E-03 ZHESS4 2 9 2 2 7 1 6 4.73 145E-02 .1.S4E400 ZHESE4 5 10 5 5 5 5 5 40 5 897E-03 ZiETE (ZEIC2) 2 9 1 2 5 1 6 4.35 1.12E-02 *1.05E4C MrMM gHE C2) 5 10 5 5 5 5 5 40 5 e.2E-03 ZHET33 2 9 2 2 7 1 6 4.73 145E-02 -1.84E+00 ZHETB3 5 10 5 5 5 5 5 40 5 897E-03 MIN HER 0 0 0 0 0 0 0 0 5.73E-04 -3 24E+00 NORMAZeD PSF 0.122 0.243 0135 0.122 0122 0.122 0135 VGHTS CALIsRATION TASKS PSF RANKINGS FU HER LOGQER)

MAXHER 10 10 10 10 10 10 10 10 1.02E+00 000E+00 STPHEOY2 6 4 2 3 4 7 8 4.75 58CE-03 -203E+50 OPRA8(1) 5 9 5 3 3 7 6 5ss 1.00E-2 -2.0E+00 DC ZHEO81 7 5 4 7 e 8 6.00 5.49E-02 -126E+00 M!NHER0 0 0 0 0 0 0 0 1.0DE43 -3 00E+00 NOTE Regreson OutpxL Const -3.242184575 (1)RANKINGS ARE THOSE FOR SIMILAR SWdEforYEsI 0.3%6s9-945 ACTION INe02 WrEOM R Sqared 0.90051090 No. f ObCseons 5 Degrees of Freedom 3 X Coeffdere(s) 0.2%s"=o ad E ofCoef. 0.05441031 Figure 47: BVPS-2 Post-EPU SLIM Worksheet Group 7

L-05-140 Enclosure 1, Attachment 4 Page 10 of 12 BEAVER V ALLEY UNIT 2 -ACTION GROUP 8 HUMAN ACTIONS EVALUATION PERFORMANCE SHAPINGFACTORS PERFORMANCE SHAPING FACTORS C P C P I P 0 R I P 0 R N R M 0 T N R M 0 T T E P C R T E P C R E C L E A S E C L E A S R E E D I T R E E D I T F D X U N T R F D X U N T R A I I R I I E S A I I R I I E S C N T E N M S U C N T E N M S U E 0 Y S o E S M E C Y s 0 E s M INPUTTO RISKIJAAN FOR Nm PSF Wei" 0.128 0.128 0.128 0.116 0.116 0.256 0.128 1 HEROSTRIBUTON OPERATOR ACTIONS PSFRANF3NGS FU HER LOG0 ER) OPERATOR ACTIONS PSFWEIGHTS RANGEFACTOR MEDIAN MAXHER 10 10 10 10 10 10 10 10 3.53E401 4.53E401 ZHBCD3 2 3 3 2 2 0 5 2.13 121E-03 -2.92E+00 ZHECO3 5 5 5 5 5 10 5 40 7.5 5.72E-04 ZHECC4 2 5 a 5 6 0 7 4 09 4 s90-3 *2.30E+00 ZHECD4 5 5 5 5 5 10 5 40 7.5 2.38E603 ZHEIAI 1 3 2 5 2 7 3 3.76 3.91E.03 *2.41E.00 ZHEIA1 5 5 5 5 5 10 5 40 7.5 1.8sE-03 ZHEOTI I 0 1 0 0 5 6 2.30 1.37E-03 22.8E.E0 ZHEOTI 5 5 5 0 5 10 5 35 7.5 6.48E-04 ZHEREE 1 2 2 6 2 5 5 3.49 3 23E-03 -2.49E+00 ZHEREE 5 5 5 5 5 10 5 40 7.5 1.52E-03 ZHERII I 0 1 0 0 5 7 2.43 1.516-03 -282E0.00 ZHER01 5 5 5 5 5 10 5 40 7.5 7.11E-04 2HE#51(gHEOC1,ZI4EOC2) 2 4 2 1 4 7 5 4 03 4.7sE-03 -. 32E+00 ZHESEI(HEOCI.ZEOZ2) 5 5 5 5 5 10 5 40 7.5 226E-03 2HESL1 2 1 5 2 3 5 6 3.65 360E-03 -2.44E+00 ZHESL1 5 5 5 5 5 10 5 40 7.5 1.716-03 ZHESLs 2 4 5 2 4 6 a 4.ee 7.sE-03 .2.12E00 ZHESLS S 5 5 5 5 10 s 40 7.5 3.556-03 ZHEWA2 2 3 7 4 2 5 5 4.15 520E-03 -228Eo00 ZHEWA2 5 5 5 5 0 10 5 35 7.5 2.46E-03 ZHEWA4 2 6 7 7 10 5 6 5.94 1J.sE2 .1.72E+00 ZHEWA4 5 5 5 5 5 10 5 40 5 1.17E-02 MINHER 0 0 0 0 0 0 0 0 2.61E-04 43.586E0 NORALIZED PSF 0.128 0.128 0.128 0.116 0.116 0.255 0.128 WEIGHTS CAuBRATION TASKS PSFRANKINGS FU HER LOG(HER)

MAXHER 1o 10 10 10 10 10 10 10 1.OE00 0000E+00 STPHEOSL1 5 3 4 3 3 3 6 3.77 2.13E403 .267Eo00 FERM HERSI 2 7 2 3 2 4 6 3.78 1.7sE-03 .2.70E+00 STPHEOSOI 6 4 6 3 10 10 3 6 50 1.50E-02 .1.74E+00 DC ZEOXI(1I) 2 1 5 2 3 7 6 4.16 3200-03 -249E+00 MINHER 0 0 0 0 0 0 0 0 1.00-03 .3.00E+00 NOTE Regrssion Output Constt 4.5s30s92 (1)RANKINGS ARETHOSEFORSMTAR StdErrfdY Est 0.4551634 ACTIONIN N2 (gHESLI) RSquared 0 8675913 No.dObservans 6 Dee., d FreedOm 4 x Coeff~de4(a) 0.31302434 StdErrd Cooe. o 001141234 Figure 48: BVPS-2 Post-EPU SLIM Worksheet Group 8

L-05-140 Enclosure 1,Attachment 4 Page 11 of 12 EA\EVAllEY UNT2 - CCN P 9HN RNllCNS EVALllCN F9TwN EsX9VRGFX'M RFsflRXNMSf IWNI c P c P I P 0 R I P 0 R N R Mo T N R Mo T T E P C R T E PC R E C L E A S E C L E A S R E E D I T R E ED I T F D X U N T R F D X U N T R A I I RI I E S A I I RI I E S C N T E N M S U C N T E N M S U E G Y S G E S M E G Y S G E S M INWnDORSINFCR Nm PSWi" 0 0178 1175 Q178 Q178 0a1180178 1 sasRamCN CPFTCRcnCNS WFR*N3; Rl KR LW l63 Atcnars PsFVamrS WMFP= MMN WHXR 10 10 10 10 10 10 10 10 628E0 2ZE01O Z 2 9 3 3 7 3 9 58 7. -1.12E#CO ZH3M 0 5 5 5 5 5 5 5 474EG2 2 7 2 9 8 5 8 4 9 7.35 1.65O -7.8X1 23M7 0 5 5 5 5 5 5 3 1.3X;O1 a-EMW 2 4 5 4 5 2 1 35 248M -1.61E'O 0 5 5 5 5 0 5 5 , 1.536M MNH-R 0 0 0 0 0 0 0 a0o 4064 -23E M DPr=SF o Q178a178 a178 a1780118 a178 I OCTS CATUEPAT1CNTA9T PSFRTnNMS ru FER LOl6~

MWXi-R 10 1010 10 10 10 10 10 1m Iac0 SIPH3 6 6 6 5 6 8 9 Ek= 4386{ AOSE00 ERMs (1) 2 9 3 3 7 3 9 5M5 1. 0R1 .1.CE#0 MNFER 0 0 0 0 0 0 0 0 o 50 -23OE0 NOTE Qr1at -23 13371 (1)R*qNNSAFETFEFRRSSMLAR S15rdYEt a 5 PCnCPNINQEv-M* RSRn~i 19151131 NadOnawkm 4 EisdFRe+/-d" 2 X xffide(s) 012117541 S rdi. 00Q71718 Figure 49: BVPS-2 Post-EPU SLIM Worksheet Group 9

L-05-140 Enclosure 1, Attachment 4 Page 12 of 12

\EEVAYlEYLNT2-- G.UP 10 HNMMCMMS WAIAICN F5'CEV-9i1ARRFACT F RRCE94 G;S c P C P I P 0 R I P O R N R MO T N R M O T T E P C R T E P C R E CL E A S E C L E A S R E ED I T R E E D I T F D X U N T R F D X U NT R A I I RI I E S A I I R I I E S C N T E N M S U C N T E N MS U E G.Y S G E S M E G Y S GE S M IVfJMORS"NI;R N7MFPVt 014 01402 a) U041414 1 HfRDSTRBmfl SPCFM MO'S FSRAN26 RI RR LDMU5 aR*TRcnas PF5GF MXKR 10 10 10 10 10 10 10 10 9aSn u7S ZHDl 8 9 10 1 4 5 8 7.71 a5a(2 *l4SO ZHD(f 5 5 10 0 5 5 5 5 221E2 MNFR 0 0 0 0 0 0 0 GOD 46SW 63Xm4M MISn N3?MMSl Q14 Q14 Q29 GO 14 014 Q14 1 CMUi1nCNTA9S PSFR*I* RJ FER LCT MXR 10 10 10 10 10 10 10 10 1.0mo QGM S;<CN 0 0 1 0 2 0 0 QMN4 1as- -am MNFER 0 0 0 0 0 0 0 0 . 5sow -3010 SiErdY~t RSnv G' M115 INb d>mxdxm 3 EmdR~rn XOXlide1( 0a F idgu r 5 0. QBPPMhr Figure 50: BVPS-2 Post-EPU SLIM Worksheet Group 10

L-05-140 Enclosure 2 Proprietary Response to RAI Question Number 4

L-05-140 Enclosure 3 Non-Proprietary Response to RAI Question Number 4

Westinghouse Proprietary Class 3 "Probability Risk Assessment (PRA) RAI Response #4 for the RSG/EPU Program" BVPS EPU Submittal August 29, 2005 Westinghouse Electric Company LLC P.O. Box 355 Pittsburgh, PA 15230-0355 C)2005 Westinghouse Electric Company LLC All Rights Reserved

Question

4. Section 10.16.1.5 states that the RSGs will result in a lower frequency for steam generator tube rupture (SGTR) because of the use of Alloy 690. Please provide the basis for the new SGTR frequency including the supporting reference(s) (or excerpts).

Response

Beaver Valley Power Station Unit No. 1will be installing Westinghouse Model 54F steam generators, designed and constructed with Alloy 690 tubes. It was recognized that current, industry generic steam generator tube rupture (SGTR) initiating event frequencies are based on years of operating experience of Alloy 600 steam generator tubes and that operating experience may not be applicable to new steam generator tube designs, such as designs utilizing Alloy 690. A methodology was prepared, by Westinghouse, for calculation of a generic SGTR initiating event frequency for steam generators constructed with Alloy 690 tube material. This methodology does not ignore the many years of data currently available for Alloy 600 steam generator design, but incorporates that information with current understanding of the SGTR failure modes and improvements to steam generator tube designs and improvements to plant operating practices.

STEAM GENERATOR TUBE RUPTURES EVENTS Most of the PWR steam generator tubes which have failed over the years have been mill-annealed Alloy 600 tubes. However, some failures of thermally treated Alloy 600 tubing have been reported, primarily due to fretting (degradation mechanisms due to the design of the support plates and anti-vibration bars (AVBs), and the presence of loose parts, rather than the tubing material). But there have also been a few failures of thermally treated Alloy 600 tubing due to primary and secondary-side stress corrosion cracking (SCC).

Degradation mechanisms include primary water stress corrosion cracking (PWSCC),

outside diameter stress corrosion cracking (ODSCC), transgranular stress corrosion cracking, intergranular stress corrosion cracking (IGSCC) (fretting, wear and thinning),

pitting, denting, high-cycle fatigue, and wastage (erosion-corrosion and corrosion-fatigue).

A search of the INPO database for SGTR License Event Reports was performed. The search confirmed the following SGTR events, which are provided in Table 4-1.

[Table 4-1: SGTR Industry Events 1 Plant Year Failure Mechanism Point Beach 1 1975 Wastage/SCC Surry 2 1976 PWSCC Doel 2 1979 PWSCC Prairie Island 1 1979 Loose Parts Wear Ginna 1 1982 Loose Parts Wear North Anna 1 1987 High-Cycle Fatigue McGuire 1 1989 IGSCC

Table 4-1: SGTR Industry Events Plant Year Failure Mechanism Mihama 2 1991 High-Cycle Fatigue Indian Point 2 2000 PWSCC STEAM GENERATOR TUBE RUPTURE FREQUENCY METHODOLOGY A methodology was created by Westinghouse for a generic SGTR initiating event frequency for use with Westinghouse Alloy 690 steam generator designs. The methodology considers the history of steam generator operating experience (total tube years and plant availability) and calculates a steam generator tube non-plugging factor to determine a "tube years adjusted" value. The Alloy 690 SGTR initiating event frequency is the postulated number of SGTR events (based on expert elicitation) divided by the "tube years adjusted" value.

I Ia~c

[

]ac Expert Elicitation A Westinghouse expert opinion discussion was held to discuss the likelihood of SGTR due to various failure mechanisms.

The expert opinion discussion focused on the known, potential failure mechanisms for current steam generator tubes. Based on current knowledge of Alloy 690 steam generator tubes, the likelihood of a SGTR event due to a given failure mechanism was debated and the results were documented.

The results of the expert opinion discussion can be used to calculate a postulated number of steam generator tube rupture events.

I I 01)

0) I I 0D

Page 6 ac Steam Generator Tube Rupture Frequency Calculations For mill annealed steam generators, a frequency per tube-year has been calculated to be 1.25 E-06 (see Table 4-3); and, for thermally treated or Alloy 690 steam generators, the frequency per tube-year has been calculated to be 1.94 E-07 (see Table 4-4).

An extensive search of data was performed for all domestic, foreign and foreign licensee Westinghouse type steam generators.

The data points for the overall database consist of the following:

Plant name

Steam generator model

Number of plant loops

Number of tubes per steam generator

Total number of tubes in all steam generators at that plant

Date plant was commissioned or date the plant replaced the original steam generator

Effective date of analysis or the date the plant ceased operation

Total number of years between commission or replacement date and the date of analysis or ceased operation

Tube-years (a multiplication between total number of years and the total number of tubes)

3 year availability

3 year capability

Shutdown date if the plant ceased operation

Steam generator replacement date if the steam generator was replaced

Replacement model

Date the plant is considering future steam generator replacement

Total number of tubes plugged at each plant I

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Page 8 ac I

ac Page 10 BVPS-1 Steam Generator Tube Rupture Frequency Calculation BVPS-1 has three SGTR initiating events (one for each steam generator); thus, the calculation here will be on a per steam generator basis. Based on the frequency (tube-year) value of 1.94E-07 for Model 54F (Alloy 690) steam generators, the calculation for BVPS-1 results in the following:

Frequency = 6.96E-04 SGTR per year per steam generator

L-05-140 Enclosure 4 Affidavit

eWestinghouse Westinghouse Electric Company Nuclear Services P.O. Box 355 Pittsburgh, Pennsylvania 15230-0355 USA U.S. Nuclear Regulatory Commission Directtel: (412) 3744419 Document Control Desk Directfax: (412) 374-4011 Washington, DC 20555-0001 e-mail: maurerbf@westinghouse.com Our ref: CAW-05-2046 August 26, 2005 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE

Subject:

"Probability Risk Assessment (PRA) RAI Response #4 for the RSG/EPU Program" (Proprietary)

The proprietary information for which withholding is being requested in the above-referenced report is further identified in Affidavit CAW-05-2046 signed by the owner of the proprietary information, Westinghouse Electric Company LLC. The affidavit, which accompanies this letter, sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CFR Section 2.390 of the Commission's regulations.

Accordingly, this letter authorizes the utilization of the accompanying affidavit by FirstEnergy Nuclear Operating Company.

Correspondence with respect to the proprietary aspects of the application for withholding or the Westinghouse affidavit should reference this letter, CAW-05-2046, and should be addressed to B. F. Maurer, Acting Manager, Regulatory Compliance and Plant Licensing, Westinghouse Electric Company LLC, P.O. Box 355, Pittsburgh, Pennsylvania 15230-0355.

Very truly yours, B. F. Maurer, Acting Manager Regulatory Compliance and Plant Licensing Enclosures cc: B. Benney L. Feizollahi A BNFL Group company

CAW-05-2046 bcc: B. F. Maurer (ECE 4-7A) I L R. Bastien, IL (Nivelles, Belgium)

C. Brinkman, IL (Westinghouse Electric Co., 12300 Twinbrook Parkway, Suite 330, Rockville, MD 20852)

RCPL Administrative Aide (ECE 4-7A) I L, I A (letter and affidavit only)

A BNFL Group company

CAW-05-2046 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:

ss COUNTY OF ALLEGHENY:

Before me, the undersigned authority, personally appeared J. A. Gresham, who, being by me duly sworn according to law, deposes and says that he is authorized to execute this Affidavit on behalf of Westinghouse Electric Company LLC (Westinghouse), and that the averments of fact set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief:

A. resham, Manager Regulatory Compliance and Plant Licensing Sworn to and subscribed before me thisc i( day of A, 2005 Notary Public I Notaf SealI Shawn L Foi, Notary Pubic W=f Boro, Allehwy Cout MY AdrExDires January 29,2007 Mamber. Pennsytvania Assndition of Noari"

2 CAW-05-2046 (1) 1 am Manager, Regulatory Compliance and Plant Licensing, in Nuclear Services, Westinghouse Electric Company LLC (Westinghouse), and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear power plant licensing and rule making proceedings, and am authorized to apply for its withholding on behalf of Westinghouse.

(2) 1 am making this Affidavit in conformance with the provisions of 10 CFR Section 2.390 of the Commission's regulations and in conjunction with the Westinghouse "Application for Withholding" accompanying this Affidavit.

(3) I have personal knowledge of the criteria and procedures utilized by Westinghouse in designating information as a trade secret, privileged or as confidential commercial or financial information.

(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.390 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld.

(i) The information sought to be withheld from public disclosure is owned and has been held in confidence by Westinghouse.

(ii) The information is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the public. Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence.

The application of that system and the substance of that system constitutes Westinghouse policy and provides the rational basis required.

Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows:

(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.

3 CAW-05-2046 (b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability.

(c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.

(d) It reveals cost or price information, production capacities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers.

(e) It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse.

(f) It contains patentable ideas, for which patent protection may be desirable.

There are sound policy reasons behind the Westinghouse system which include the following:

(a) The use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors. It is, therefore, withheld from disclosure to protect the Westinghouse competitive position.

(b) It is information that is marketable in many ways. The extent to which such information is available to competitors diminishes the Westinghouse ability to sell products and services involving the use of the information.

(c) Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.

(d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage. If competitors acquire components of proprietary information, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.

4 CAW-05-2046 (e) Unrestricted disclosure would jeopardize the position of prominence of Westinghouse in the world market, and thereby give a market-advantage to the competition of those countries.

(f) The Westinghouse capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a competitive advantage.

(iii) The information is being transmitted to the Commission in confidence and, under the provisions of 10 CFR Section 2.390, it is to be received in confidence by the Commission.

(iv) The information sought to be protected is not available in public sources or available information has not been previously employed in the same original manner or method to the best of our knowledge and belief.

(v) The proprietary information sought to be withheld in this submittal is that which is appropriately marked in "Probability Risk Assessment (PRA) RAI Response #4 for the RSG/EPU Program," (Proprietary) dated August 26, 2005, for support of the RSG/EPU project, being transmitted by the FirstEnergy Nuclear Operating Company letter and Application for Withholding Proprietary Information from Public Disclosure, to the Document Control Desk. The proprietary information as submitted by Westinghouse for Beaver Valley Units I & 2 is expected to be applicable for other licensee submittals in response to certain NRC requirements for justification of Alloy 600 SG Tube Rupture Frequency methodology.

This information is part of that which will enable Westinghouse to have a:

(a) competitive position for RSG.

(b) competitive position for PRA Data Analysis.

Further this information has substantial commercial value as follows:

(a) Westinghouse plans to sell the use of similar information to its customers for purposes of future PRA and RSG analysis contracts.

5 CAW-05-2046 (b) Westinghouse can sell support and defense of SGTR Initiating Event Frequency Methodology.

(c) The information requested to be withheld reveals the distinguishing aspects of a methodology which was developed by Westinghouse.

Public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to provide similar calculations for SGTR Initiating Event Frequency and licensing defense services for commercial power reactors without commensurate expenses. Also, public disclosure of the information would enable others to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the information.

The development of the technology described in part by the information is the result of applying the results of many years of experience in an intensive Westinghouse effort and the expenditure of a considerable sum of money.

In order for competitors of Westinghouse to duplicate this information, similar technical programs would have to be performed and a significant manpower effort, having the requisite talent and experience, would have to be expended.

Further the deponent sayeth not.

PROPRIETARY INFORMATION NOTICE Transmitted herewith are proprietary and/or non-proprietary versions of documents furnished to the NRC in connection with requests for generic and/or plant-specific review and approval.

In order to conform to the requirements of 10 CFR 2.390 of the Commission's regulations concerning the protection of proprietary information so submitted to the NRC, the information which is proprietary in the proprietary versions is contained within brackets, and where the proprietary information has been deleted in the non-proprietary versions, only the brackets remain (the information that was contained within the brackets in the proprietary versions having been deleted). Thejustification for claiming the information so designated as proprietary is indicated in both versions by means of lower case letters (a) through (f) located as a superscript immediately following the brackets enclosing each item of information being identified as proprietary or in the margin opposite such information. These lower case letters refer to the types of information Westinghouse customarily holds in confidence identified in Sections (4)(ii)(a) through (4)(ii)(f) of the affidavit accompanying this transmittal pursuant to 10 CFR 2.390(b)(1).

COPYRIGIT NOTICE The reports transmitted herewith each bear a Westinghouse copyright notice. The NRC is permitted to make the number of copies of the information contained in these reports which are necessary for its internal use in connection with generic and plant-specific reviews and approvals as well as the issuance, denial, amendment, transfer, renewal, modification, suspension, revocation, or violation of a license, permit, order, or regulation subject to the requirements of 10 CFR 2.390 regarding restrictions on public disclosure to the extent such information has been identified as proprietary by Westinghouse, copyright protection notwithstanding. With respect to the non-proprietary versions of these reports, the NRC is permitted to make the number of copies beyond those necessary for its internal use which are necessary in order to have one copy available for public viewing in the appropriate docket files in the public document room in Washington, DC and in local public document rooms as may be required by NRC regulations if the number of copies submitted is insufficient for this purpose. Copies made by the NRC must include the copyright notice in all instances and the proprietary notice if the original was identified as proprietary.

v t e Letter Sequence Response to RAI
TAC:MC4645, (Approved, Closed)
Initiation Request, Request, Request, Request, Request Acceptance, Acceptance, Acceptance Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement Administration Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance Meeting, Meeting, Meeting, Meeting Questions 11 March 2005 5 May 2005 2 August 2005 30 September 2005 1 November 2005 Answers 6 September 2005 Results Approval, Approval, Approval Other: ML060330262, ML061770605
MONTHYEAR2005-07-28 [Table View]

L-05-140, Response to a Request for Additional Information (RAI Dtd August 2, 2005) in Support of License Amendment Request Nos. 302 and 173, Extended Power Uprate

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L-05-140, Response to a Request for Additional Information (RAI Dtd August 2, 2005) in Support of License Amendment Request Nos. 302 and 173, Extended Power Uprate

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