ML12193A141

6/28/2012 Summary of Meeting with Pacific Gas and Electric to Discuss Digital Replacement of Process Protection System at Diablo Canyon, Units 1 and 2 and Presubmittal of TSTF-493 Option B License Amendment Request (TAC ME7522-ME7523, ME851

ML12193A141
Person / Time
Site:	Diablo Canyon
Issue date:	07/25/2012
From:	Joseph Sebrosky Plant Licensing Branch IV
To:
Sebrosky J M
References
TAC ME7522, TAC ME7523, TAC ME8517, TAC ME8518
Download: ML12193A141 (41)

Text

UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 July 25, 2012 LICENSEE:

Pacific Gas and Electric Company FACILITY:

Diablo Canyon Power Plant, Unit Nos. 1 and 2

SUMMARY

OF JUNE 28, 2012, MEETING WITH PACIFIC GAS AND ELECTRIC COMPANY TO DISCUSS TECHNICAL SPECIFICATION INSTRUMENTATION AND CONTROL SETPOINT CHANGES AT DIABLO CANYON POWER PLANT (TAC NOS. ME7522, ME7523, ME8517, AND ME8518) On June 28,2012, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Pacific Gas and Electric Company (PG&E, the licensee) at NRC Headquarters, One White Flint North, 11555 Rockville, Maryland.

The purpose of the meeting was to discuss Technical Specification (TS) instrumentation and control setpoint changes. A list of attendees is provided in Enclosure

1. PG&E's handouts from the meeting are provided in Enclosure

2. The meeting was broken into two parts with the first part of the meeting discussing the setpoint methodology used to support a license amendment request (LAR) submitted by PG&E on October 26, 2011, for the Digital Replacement of the Process Protection System (PPS) Portion of the Reactor Trip System and Engineered Safety Features Actuation System at Diablo Canyon Power Plant, Unit Nos. 1 and 2 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 113070457).

The second part of the meeting included PG&E's plans for submitting a future LAR to implement a TS setpoint control program to allow relocation of the setpoints from the TSs to licensee control in accordance with TS Task Force (TSTF) Change Traveler TSTF-493, "Clarify Application of Setpoint Methodology for LSSS [Limiting Safety System Settings]

Functions," Option 8. Highlights and Action Items from the Meeting PG&E indicated that the setpoint methodology that it intended to use to support the October 26, 2011, digital replacement LAR was imbedded in WCAP-17504-P, "Westinghouse Generic Setpoint Methodology," February 2012 that was submitted to the NRC by a letter dated February 20, 2012 (ADAMS Accession No. ML 12058A448).

PG&E requested NRC confirmation that WCAP-17504-P would be reviewed by the staff as part of the October 26,2011, digital replacement LAR. The NRC staff indicated that trying to perform the LAR review in parallel with the WCAP review was extremely problematic.

For example, the staff indicated that at the completion of the WCAP review there would most likely be specific action items that would have to be addressed by anyone that wanted to reference the WCAP safety evaluation.

Therefore, the application-specific action

-items could not be addressed until the WCAP review was completed several months into the future. The staff indicated that typically review and approval of topical reports take approximately 18 to 24 months to conclude.

Therefore, it is highly likely that including the WCAP within the scope of the LAR approval will delay issuance of the DCPP PPS LAR. Furthermore, accepting license amendment requests referencing unapproved topical reports is not consistent with the agency's licensing process. The staff indicated that as an alternative, PG&E could submit the setpoint methodology applicable to the DCPP PPS LAR on a plant-specific basis, which would allow the staff to better manage the review. PG&E took the following actions as a result of the discussion: Consider the staff's feedback on whether a plant-specific submittal for the setpoint methodology better supported PG&E's needs, as opposed to relying on the staff's review of a topical report. Consider whether or not to provide a letter to the NRC stating that it intended to use the WCAP-17504-P methodology so that the staff could consider this information as part of its prioritization of topical report reviews. In addition, PG&E indicated that it would submit on the docket the setpoint calculation summary report and that the setpoint calculations themselves would be made available for NRC review in the form of Westinghouse Calculation Notes at Westinghouse's Rockville, MD offices. The NRC staff indicated that in the past, representative setpoint calculations were placed on the docket to support the staff's safety evaluation.

This is required by the NRC's licensing process (LlC-101) if the information within a setpoint calculation is used to make the safety finding and documented within the safety evaluation.

The process that was used in the past is the staff asked for a listing of all the setpoint calculations, and then based on the list requested the licensee to formally submit one or two of the calculations as representative samples. The staff explained that the NRC has regulations, procedures, and a records management system designed to protect proprietary information submitted on the docket. PG&E took an action to determine if the staff's suggested approach was problematiC and, if it is, to provide this feedback, including the reason for it being problematic, to the staff. In the second portion of the meeting, PG&E indicated that it was targeting summer 2013, for the LAR to implement TSTF-493 option B. In response to a PG&E question, the NRC staff stated that it was the staff's expectation that the plant-specific setpoint control program should be submitted with the TSTF-493 Option B LAR. NRC took the following actions as a result of this discussion: Issue the draft guidance that the staff is developing that will provide additional guidance to those utilities that intend to pursue TSTF-493 Option B.

-3 The NRC's Instrumentation and Controls Branch will work with the Division of Policy and Rulemaking to determine if a pilot program for the use of TSTF-493 Option B is appropriate.

PG&E indicated that it would be interested in being the pilot for the use of TSTF-493 Option B and would be further interested in pursuing a fee waiver, if possible, associated with the review. The NRC staff indicated that it would consider the request by PG&E to be considered as a pilot for TSTF-493 Option B. Docket Nos. 50-275 and 50-323

Enclosures:

1. list of attendees

2. PG&E handouts cc w/encls: Distribution via listserv LIST OF JUNE 28, 2012, MEETING PACIFIC GAS AND ELECTRIC COMPANY TECHNICAL SPECIFICATION SETPOINT CHANGES DIABLO CANYON POWER DOCKET NOS. 50-273 AND NAME ORGANIZATION Ken Schrader Pacific Gas and Electric Russ Prentice Pacific Gas and Electric Robert Washington Pacific Gas and Electric Terry Williams Westinghouse Rick Tuley Westinghouse Ryan Rossman Westinghouse Zackary King Westinghouse Jim Andrachek Westinghouse Dewey Olinski Westinghouse John Hefler Altran Ted Quinn Altran Brian Haynes Invensys John Thorp U.S. Nuclear Regulatory Commission David Rahn U.S. Nuclear Regulatory Commission William Kemper U.S. Nuclear Regulatory Commission Kristy Bucholtz U.S. Nuclear Regulatory Commission Thomas Burton U.S. Nuclear Regulatory Commission Pong Chung U.S. Nuclear Regulatory Commission Louis Dumont U.S. Nuclear Regulatory Commission Joe Sebrosky U.S. Nuclear Regulatory Commission Shiattin Makor U.S. Nuclear Regulatory Commission Gordon Clefton Nuclear Energy Institute Jerry Voss Excel Services Bob Hunter Hurst Technologies Bill Sotos Hurst Technologies Steve Widem Wolf Creek Nuclear Ken Korcz Babcock and Wilcox MPower Enclosure 1

DIABLO CANYON POWER PLANT SETPOINTS, DIGITAL REPLACEMENT OF PROCESS PROTECTION SYSTEM AND Option B June 28, Ken Schrader Robert Washington Russ Prentice Pacific Gas & Electric Co. Avila Beach, CA c. Rick Tuley Terry Williams Jim Andrachek Ryan Rossman Westinghouse John Hefler Altran San Francisco, CA 1 Enclosure 2

.... ...-................... PPS Replacement LAR Setpoints License Amendment Request (LAR) for Process Protection System (PPS) Replacement submitted October 26, 2011 ADAMS Accession No. ML 11307 A331

• Setpoints for PPS replacement being addressed in two phases Phase One -Setpoint evaluation Phase Two -Setpoint calculations Setpoint evaluation and calculations performed by 2

I PPS Replacement LAR

--* Setpoint evaluation information for Replacement submitted June 6, Interim Staff Guidance (ISG) 6 Phase 2 documents Enclosure Attachment 15 (proprietary) Enclosure Attachment 16 (nonproprietary) Inputs, equations, and results are consistent with information contained in current Diablo Canyon Setpoints Report, WCAP-11 082 Revision 6

• Initially referenced in 2004 Amendments 178/180

• Last referenced in 2009 Amendment 208 3 PPS Replacement Setpoint Evaluation Calculate as-found tolerances (AFT) and as-left tolerances (AL T) for applicable process racks, transmitters, and sensors Review current plant accident analyses, installed sensors, manufacturer specifications, plant procedures and calculations Evaluate as-found minus as-left drift data from recent surveillance results for sample of transmitters 4

I PPS Replacement Setpoint Evaluation Scope Reactor Trip System (RTS) and Engineered Safety Feature Actuation System (ESFAS) functions processed by PPS D WCAP-17504-P, Westinghouse Generic Methodology, submitted February Total uncertainty determined at two-sided 950/0 probability and 95% confidence (95/95) level Uncertainty algorithm consistent with 2006 ISA-RP67.04.02-2010 considered 5

PPS Replacement Setpoint

• Setpoint evaluation uses current Diablo Canyon drift allowances that are expected to be bounding WCAP-14646, Revision 1, Diablo Canyon evaluation for 24 month fuel cycle (approved in 1998 Amendments Confirmed that the RCS Flow and Pressurizer Pressure drift was within the defined sensor calibration accuracy (SCA) and sensor drift (SO) Bounding PPS rack uncertainties from existing design (reference accuracy, temperature affects, drift) PPS replacement design specified to be less than or equal to the current PPS rack uncertainties 6

• ...--.-.......-.. .... -........ --_.__.........

__.... PPS Replacement Setpoint Evaluation

• Evaluation submitted June 6, 2012, concludes current PPS related RTS/ESFAS Technical Specification (TS) nominal trip setpoints remain acceptable for PPS replacement

• Uncertainty calculations are being Confirm at a 95/95 level, consistent Regulatory Guide 1.105 Revision 7 PPS Replacement Setpoint

• Westinghouse Setpoint Methodology as described in WCAP-17504-P Basic algorithm and term identification Definitions and Summary Tables of Inputs and Calculations for:

• RTS/ESFAS Protection functions

• ITDP/RTDP Control functions

• Indication Calibration and drift evaluation Application of Setpoint Methodology 8

PPS Replacement Setpoint Calculations

• Basic Algorithm for Protection Functions PMA 2 +PEA 2 +SRA 2 +(SMTE +SD)2 +(SMTE +seA)2 +} . eSA PROT = +EA +Blas{ SPE 2 +STE 2 +(RMTE + RD )2 + (RMfE + RCA)2 + RTE 2

• Statistical Basis is 95/95 Two-sided

• PG&E and Westinghouse are working the vendors to determine 95/95 9 PPS Replacement Setpoint Safety Limit II Setpoint Parameter Relationship

-.,..----r"1

-SAL Diagram (Increasing Function)

IA II SAL =Safety Analysis Limit III TA =Total Allowance II CSA = Channel Statistical

('SA Allowance III NTS =Nominal Trip Setpoint II RCA =Rack Calibration Allowance

-+ALT"" + .\FT II AL T =As-left Tolerance

\Iaq!in I -r NTS (LSSS) -R( A -AtT" -.\FT AFT =As-found Tolerance II 10

!pPS Replacement Setpoint Calculations As-found Tolerance (J Transmitters

+/-AFT =* As-found within +/-AL T =Operable

• As-found within +/-AFT =Operable, needs recalibration

• As-found +/-AFT = Inoperable, needs recalibration

& evaluation o Process Racks +/-AFT =+/-AL T =+/-RCA As-left Tolerance (J Transmitters

+/-AL T =(J Process Racks +/-AL T =

11 PPS Replacement Setpoint Calculations consider: Plant accident analyses Plant installed sensors and transmitters o PPS replacement D Measurement and Test D Plant surveillance Initial conditions uncertainties in WCAP-11594, Revision 2 (amendments 123 and 121 for 24 month surveillance frequencies) Vendor instrument data 12 I PPS Replacement Setpoint

• Sensor and rack calibration and D Process as described in WCAP-17504-P D Determination of calibration and drift data at a 95/95 level 13 I pPs Replacement Setpoint Calculation summary report will be submitted to NRC with: Listing of instrument uncertainties CSA calculation SAL, NTS (Protection) T A calculation Margin Transmitter AL T, AFT limits Process Rack AL T, AFT limits 14 PPS Replacement Setpoint Setpoint calculations will be available for NRC review at-Westinghouse White Flint office, as requested 15 PPS Replacement Setpoint Calculations Application of Westinghouse Setpoint Methodology Basic Assumptions

• Instrument techs drive as left value towards 0 error

• Process rack calibration and drift data are evaluated

• Transmitter calibration and drift data are evaluated Operability First confirmation of operability is: Ability to calibrate Second confirmation of operability is: Drift magnitude 16 PPS Replacement Setpoint Calculations PG&E currently controls the as-found and as-left tolerances through existing procedures The current surveillance test procedures for the RTS and ESFAS PPS functions require: If the as-found setting is not within range, enter into corrective action The as-left setting shall be within the desired range 17 I PPS Replacement Setpoint Calculations PG&E committed to actions to be performed if AFT or AL T are exceeded for PPS related setpoints in PG&E Letter dated June 6, 2012 18 PPS Replacement Setpoint D PG&E is expecting the NRC staff to review Westinghouse WCAP-17504-P as part of the PPS Replacement LAR. D Please confirm the review will be included as part of the PPS Replacement LAR. 19 I PG&E LAR for TSTF-493 Option B PG&E submitted an LAR for SG replacement that included a revision to the TS 3.3.2 ESFAS Feedwater isolation on SG water level-high high (P-14) function Letter dated January 11 , 2007 As-found and as-left tolerance notes added to P-14 function In the LAR, PG&E committed to submit an LAR for TSTF-493 to address the remaining RTS/ESFAS functions Amendments 198/199 include commitment 20 II IPG&E LAR for TSTF-493 Option B PG&E plans to submit LAR to implement TSTF-493, Revision 4, Option B with a Setpoint Control Program (SCP), based on Westinghouse WCAP-17503-P TSTF-493 Option B Model Application Allowable values and nominal trip setpoints will be removed, consistent with TSTF Currently planned for summer 2013 submittal SCP will address each of the blocks of Westinghouse SCP Process Flow Diablo Canyon specific SCP will provide linkage with Westinghouse setpoint methodology assumptions 21 I PG&E LAR for TSTF-493 Option B Instrumentation items to be included in SCP: TS 3.3.1, RTS TS 3.3.2, ESFAS TS 3.3.5, Loss of power DG start TS 3.3.6, Containment ventilation isolation TS 3.3.7, Control room ventilation actuation TS 3.3.8, Fuel Building ventilation actuation 22 PG&E LAR for TSTF-493 Option B SCP provides comprehens*ive controls of critical instrumentation design input parameters so plant remains within design and safety analysis assumptions 23

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I PG&E LAR for TSTF-493 Option NRC documents to be D RG 1.105 Rev. D RIS 2006 D BTP 7-12 Rev. D GL 25 PG&E LAR for TSTF-493 Option

• Industry documents to be evaluated o ISA Documents o IEEE Standards o TSTF-493 Rev. 4 26 PG&E LAR for TSTF-493 Option B Examples of Vendor documents to be evaluated:

CJ Cameron/Barton 763A GP Transmitter User Manual C 10861, Rev. 03, 7/10) CJ Ultra/Weed RTO Installation/Instruction/Operation Manual (OWG 3017-307485-003, Rev. 3, 9/89) CJ Rosemount 11530/1154 Transmitter Reference Manual (00809-0100-4388/4514, Rev. BA, 1/08) CJ Rosemount 1154 H Transmitter Reference Manual 0100-4631, Rev. BA, 4/07) Fluke 8842A Multimeter User Manual (879309, Rev. 3, 7/96) 27 IPG&E LAR for TSTF-493 Option B Examples of Diablo Canyon documents to be Setpoint Control Program Setpoint Control, CF6 Setpoint Control Program, CF6.ID1

• Instrument Channel Uncertainty and Setpoint Methodology, CF6.NE1

• Assessment of Industry Operating Experience, OM4.I03 28 PG&E LAR for TSTF-493 Option B Examples of Diablo Canyon specific documents ( continued): Scaling Procedures/Calculations

• I&C Scaling Calculation Standard Practices, CF3.DC6

• Bases Documents for Maintenance Organization Procedures, CF3.DC5 Calibration Procedures

• Test Control, AD13

• Conduct of Plant and Equipment Tests, AD13.ID1

• Calibration of Measuring and Test Equipment, MA2.DC1 29 I PG&E LAR for TSTF-493 Option B Examples of Diablo Canyon documents Surveillance Procedures Test Control, AD13

• Conduct of Plant and Equipment Tests, AD13.ID1

• Drift Monitoring Program for 24-Month Fuel Cycle, CF6.ID3

• Instrument Channel Uncertainty and Setpoint Methodology, CF6.NE1 30

!PG&E LAR for TSTF-493 Option B

• Examples of Diablo Canyon specific documents D Corrective Action

• Setpoint Control Program, CF6.ID1

• Conduct of Plant and Equipment Tests, AD13.ID1

• Performance Monitoring Equipment Calibration and Usage Control, MA2.ID2

• 10 CFR 21 Reportability Review Process, OM7.ID11

• Operability Determination, OM7.ID12 31 PG&E LAR for TSTF-493 Option B

• Examples of Diablo Canyon specific documents (continued):

o Maintenance Procedures

• Maintenance Organization Procedure Use, AD7.DC9

• Conduct of Plant and Equipment Tests, AD13.ID1

• Bases Documents for Maintenance Organization Procedures, CF3.DC5

• Conduct of Maintenance, MA 1.DC54 32 IPG&E LAR for TSTF-493 Option B Examples of Diablo Canyon documents D Change Control Modification Control, CF4 Modification Request and Authorization, CF4.ID1

• Modification Implementation, CF4.ID3 Design Control, CF3

• Design Change Development, CF3.ID9

• Replacement Part Evaluation, CF3.ID13 33 PG&E LAR for TSTF-493 Option Examples of Diablo Canyon specific documents (continued): Administrative Controls

• Development of Performance Monitoring Equipment Channel Uncertainty Calculations, AWP E-001

• Engineering Services Post Earthquake Inspection Guidelines, AWP E-019 Earthquake, CP M-4 o Diablo Canyon Safety Analyses ___a Design Calculations, CF3.ID4 34 PG&E LAR for TSTF-493 Option B PG&E is expecting the NRC staff to review WCAP-17503-P (SCP) because it is linked to WCAP-17504-P (Methodology). Please confirm the WCAP-17503-P review will be included as part of the PPS replacement LAR. 35 PG&E LAR for TSTF-493 Option B Does the plant specific SCP need to be submitted with the TSTF-493 Option B LAR? 36

-The NRC's Instrumentation and Controls Branch will work with the Division of Policy and Rulemaking to determine if a pilot program for the use of TSTF-493 Option B is appropriate.

PG&E indicated that it would be interested in being the pilot for the use of TSTF-493 Option B and would be further interested in pursuing a fee waiver, if possible, associated with the review. The NRC staff indicated that it would consider the request by PG&E to be considered as a pilot for TSTF-493 Option B. Please direct any inquiries to me at 301-415-1132 or at Joseph.Sebrosky@nrc.gov.

IRA! Docket Nos. 50-275 and 50-323

Enclosures:

1. List of attendees

2. PG&E handouts cc w/encls: Distribution via Listserv DISTRIBUTION:

PUBLIC lPLIV Reading RidsAcrsAcnw

_MaiICTR Resource RidsNrrDeEicb Resource RidsNrrDorl Resource RidsNrrDorllpl4 Resource RidsNrrLAJ Burkhardt Resource RidsNrrPMDiabloCanyon Resource RidsOgcRp Resource RidsRgn4MailCenter Resource WMaier, RIV Joseph M. Sebrosky, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation TWertz, WKemper,

RStattel, RAlvarado,

SMakor, SAchen, SKennedy, EDO DRahn,

JThorp, KBucholtz, L ADAMS Accession Nos. MeetingNotice M 121350037; Meeting s ummarv ML12193A141 OFFICE DORULPL4/PM DORULPL4/LA NRRIDE/EICB DORULPL4/BC DORULPL4/PM NAME JSebrosky JBurkhardt DRahn MMarkley JSebrosky DATE 7/24/12 7/23/12 7/24/12 7/25/12 7/25/12 OFFICIAL RECORD COpy