ML12146A017

Issuance of Amendment on Beacon Core Monitoring and Operations Support System

ML12146A017
Person / Time
Site:	Summer
Issue date:	05/30/2012
From:	Martin R Plant Licensing Branch II
To:	Gatlin T South Carolina Electric & Gas Co
Martin R
References
TAC ME6878
Download: ML12146A017 (12)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 May 30, 2012 Mr. Thomas D. Gatlin Vice President. Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88 Jenkinsville, SC 29065 SUB..IECT:

VIRGIL C. SUMMER NUCLEAR STATION, UNIT 1 -ISSUANCE OF AMENDMENT ON BEACON CORE MONITORING AND OPERATIONS SUPPORT SYSTEM (TAC NO. ME6878)

Dear Mr. Gatlin:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 190 to Renewed Facility Operating License No. NPF-12 for the Virgil C. Summer Nuclear Station (VCSNS). Unit 1 in response to your application dated August 11, 2011. This amendment allows an updating of the applicable topical report in TS 6.9.1 11, "Core Operating Limits Report" to use the three-dimensional Advanced Nodal Code neutronic model.

A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's Biweekly Federal Register notice.

Sincerely,

~

Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-395

Enclosures:

1. Amendment No. 190 to NPF-12

2. Safety Evaluation cc w/encls: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUMMER NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No.

190 Renewed License No. NPF-12

1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by South Carolina Electric & Gas Company (the licensee), dated August 11, 2011, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act). and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act.

and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public. and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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2.

Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-12 is hereby amended to read as follows:

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 190,and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. South Carolina Electric & Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This amendment is effective as of its date of issuance and shall be implemented within 90 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

~'1l4-Y :/~

Nancy L. 'Salgado, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. NPF-12 and the Technical Specifications Date of Issuance:

May 30, 2012

ATTACHMENT TO LICENSE AMENDMENT NO. 190 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 Replace the following pages of the License and Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Insert Pages License License License No. NPF-12, page 3 License No. NPF-12, page 3 TS TS 6-16a 6-16a

(3)

SCE&G, pununt 10 the Ad and 10 CFR Pan 70, 10 receive, possess and ule a1 any time IPIdaI nuclear material as reactor fuel, i1 aocordltlC8 with Ihellmllltionl for storage and IIJIOUnbs required for reactor operaton, as d8lCribed In Ihe Rnal Safety Anatt!is Report. al amended thn:H.Igh Amandmem No. 33; (4). SCE&G. p.nuant 10 the Ad and 10 CFR Parts 30, 40 and 70 CO receMt.

possess and use at fIny time any byproducr. aource and spedall"lIClear material. seaIed,..mn 8OW08S for t8actDr 8t8r1up. _led neutron SOUtCeS for reactor InItrul1'l8l1Talicn and RlClation moniIoring equfprna'lt caflbratlon. IU'Id.. tllSIcn detactof'lln amounts as requi'ed; (5)

SCE&G. ~ 10 the Act and 10 CFR Parts 30, 40. and 10. to receive, possess and Ull81n arnounlllS required any byproduct, IQW'Ce or apecia/ nuclear material without resb1c11on 10 chemical 01' physlcalfonn*.

for sample analysis or Instrument caRbratlon or associated wiIh radioactive apparatus of camponenta; and (6)

SCEIG. pursuant to the Am and 10 CFR Parts 30. 40, and 10, to poRe"', but Jd separate, IUCh byproduct and special nuclear materials as mt be ptOdaJd by the operation of the facility.

C.

this renewed license 01 be deemed to contain. and is subject to, the ccndtionl specified In Ihe Commission" regulations set fOrth" 10 CFR Chapter I and Is ~ 10 alt appUc:able provtsions of !he Act and to tle rules, regtJatlona, and order, 01 the C<<nmiHion now or hereafter In effec1; and Is sLbJect to the addIlIonaI conditions lIpadfled or Incorporated below:

(1)

Maxlmym Power LMl SCE&~ it authorized to operate the facility at reactor core power level~

not In exwss of 2900 ~ 1hermaI1n ~ with the conditiOns epedfted tWrwln and In Attachment 1 to this reneWed ic&nse.

The preoccUpallon teets, lltartup t81\\8 n other itema IdBnIII&d In to this renewed lICanse shall be completed as specified.

Anactlment, is ~Teby IncorpOrated Ir10 ttlle ",newed license.

(2)

Tectmis:e' SpecHlcatlon, and ~lronm.nt" pro!8£!IOn Plan The technical SpN:ifica1ion8 contained In Appendix A. !!S ~ througl\\

Amen~ent No 1~ and the Erwitorrnental Protection plan contained in Appendix B, aI'8 hereoy incorporated In the renewed Ucense. South Carolina Electric & Gas eon,.ny.11 operate the facility In accordance with ther Technical Spedflca1ions and the Envirormental Pl'OI8c1ion Plan.

Renewed Facillty (')pera1ing License No. NPF*12 Amendment No. 190

ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued)

c.

WCAP~12945-P-A, Volume 1 (Revision 2) through Volumes 2 through 5 (Revision 1) "Code Qualification Document for Best Estimate lOCA Analysis,"

March 1998 (Westinghouse Proprietary).

Liparulo, N. ('t:!J to NRC Document Control Desk, NSD-NRC-96-4746, "Re Analysis Work Plans Using Final Best Estimate Methodology" dated 6/13/1996.

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)

d.

WCAP-12472-P-A, "BEACON CORE MONITORING AND OPERATIONS SUPPORT SYSTEM," August 1994, (W Proprietary).

WCAP-12472-P-A, Addendum 1~A, "BEACON CORE MONITORING AND OPERATIONS SUPPORT SYSTEM," January 2000, (W Proprietary)

(Methodology for Specifications 3.2.2 - Heat Flux Hot Channel Factor, 3.2.3 RCS Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor, and 3.2.4*

Quadrant Power Tilt Ratio.)

e.

WCAP-13749-P-A, "Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOl Moderator Temperature Coefficient Measurement,"

March 1997, (Westinghouse Proprietary).

(Methodology for SpeCification 3.1.1.3 - Moderator Temperature Coefficient.)

f.

WCAP-12610-P-A, "VANTAGE + Fuel Assembly Reference Core Report," April 1995 (W Proprieta~). WCAP-12610-P-A & CENPD-404-P-A, Addendum 1-A, "Optimized ZIRlOT," July 2006 (W Proprietary).

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)

The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal mechanical limits, core thermal-hydraulic limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements there to shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

SUMMER - UNIT 1 6-16a Amendment No. 88, 121, 1aa, 142, 169,176,182, 190

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 190 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-12 SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY VIRGIL C. SUMMER NUCLEAR STATION, UNIT 1 DOCKET NO. 50-395

1.0 INTRODUCTION

By letter dated August 11,2011, (Reference 1) South Carolina Electric & Gas Company (SCE&G, the licensee), submitted a license amendment request (LAR) for changes to the Virgil C. Summer Nuclear Station (VCSNS), Unit 1, Technical Specification (TS) 6.9.1.11, "Core Operating Limits Report (COLR)" to reference and use Westinghouse topical report, WCAP-12472-P-A, Addendum 1-A (Reference 3). This is an update to the existing reference to WCAP-12472-P-A, "BEACON Core Monitoring and Operations Support System," August 1994, (Reference 2) which was approved for use at VCSNS by License Amendment No. 142. Reference 3 reflects NRC approval of Addendum 1-A to WCAP-124 72-P-A, which allows the use of the three-dimensional Advanced Nodal Code (ANC) neutronic model (Reference 4) in BEACON in place of the previously approved SPNOVA model.

The purpose of the reactor core monitoring system is discussed in the NRC staff's safety evaluation for the issuance of License Amendment No. 142 (Reference 6) as follows:

[The changes to the VCSNS TS] incorporate a new reactor core power distribution monitoring system (PDMS). The new system uses an NRC-approved Westinghouse proprietary computer system, the best estimate analyzer for core operation-nuclear (BEACON), to augment the flux mapping system when performing a core power distribution surveillance. The proposed TS changes allow the use of the PDMS at power ranges greater than 25% rated thermal power (RTP). At ranges less than or equal to 25% RTP, the licensee must declare the PDMS inoperable.

The existing TS will continue to require the licensee to perform a surveillance using the present movable incore detector system when the PDMS is declared inoperable.

The NRC-approved BEACON Topical Report WCAP-12472-P-A... is acceptable for use at VCSNS, and it describes a greatly improved on-line power distribution monitoring system. This system provides direct, continuous core power distribution determination and directly relates power distribution to fuel safety limits for Westinghouse plants. At VCSNS, the licensee will use the BEACON system for measuring power distribution instead of using the moveable in-core flux mapping

- 2 system when power is greater than 25% RTP. All existing power distribution limits remain unchanged. SCE&G will continue to perform power distribution surveillances at the current frequency (every 31 effective full power days). The NRC staff has confirmed that the licensee has referenced and adhered to any restrictions and/or conditions the NRC imposed on WCAP-12472-P-A approval. SCE&G will use the BEACON system only with moveable in-core detectors, as the Westinghouse Topical Report does not apply to fixed in-core detectors.

The proposed TS 6.9.1.11 revision to add WCAP-12472-P-A,"BEACON Core Monitoring and Operations Support System," August 1994, will ensure the values for cycle-specific parameters are maintained within the applicable limits of the plant safety analysis, thus ensuring conformance to 10 CFR 50.36.]

2.0 REGULATORY EVALUATION

The BEACON core monitoring system methodology was approved for use at VCSNS in license amendment number 142 for monitoring and determining the three-dimensional core power distribution (Reference 6). This calculation was performed with the NRC approved Westinghouse SPNOVA nodal method (Reference 5). SPNOVA employs a single effective neutron fast group calculation to determine the global neutron flux solution, and then uses a local correlation to determine thermal11ux and power distribution (Reference 2). SPNOVA is a simplified neutron diffusion equation code which was used due to limited computational power of early vintage work stations. The licensee, as a result of enhanced capability workstations and improvements in numerical solution technique of the nodal expansion method, proposes to upgrade the BEACON core monitoring system to use the three-dimensional ANC neutronic model (Reference 4), as referenced in WCAP-12472-P-A, Addendum 1-A.

Title 10 of the Code of Federal Regulations, Section 50.36(b) states, in part, that the TS will be derived from the analyses and evaluations included in the safety analysis report, and amendments thereto, submitted pursuant to Section 50.34. Section 50.36(c)(5) states that TS shall contain Administrative Controls "relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner."

VCSNS TS 6.9.1.11 requires that the core operating limits be established and documented in the COLR prior to each reload cycle using NRC approved analytical methods. WCAP-12472-P-A, Addendum 1-A for the BEACON core monitoring system (Reference 3) was reviewed and approved by the NRC staff. The license amendment is proposed by the licensee under 10 CFR 50.90 to incorporate the Addendum 1-A into the VCSNS TS.

The NRC staff reviewed the LAR to evaluate compliance of the proposed methodology with the requirements of Title 10 of the Code of Federal Regulations (10 CFR), Part 50, General Design Criterion 13:

GDC-13, "Instrumentation and Contro/" Instrumentation shall be provided to monitor variables and systems over their anticipated ranges for normal operation, for anticipated operational occurrences, and for accident conditions as appropriate to assure adequate safety, including those variables and systems that can affect the fission process, the integrity of the reactor core, the reactor coolant pressure boundary, and the containment

- 3 and its associated systems. Appropriate controls shall be provided to maintain these variables and systems within prescribed operating ranges.

3.0 TECHNICAL EVALUATION

3.1 Background and Methodology The BEACON system was originally developed by Westinghouse to monitor core power distribution in Westinghouse reactors. The monitoring operation was based largely on, and tied together by, the use of the NRC staff-approved three-dimensional neutronics analysis code SPNOVA (Reference 5). SPNOVA's primary role in BEACON was to generate detailed power distributions and compare them to core limits (e.g., departure from nucleate boiling (DNB) ratio limits, on a nearly continuous basis and supply that information to the operator. SPNOVA was calibrated periodically using the incore neutron flux measurement system to provide details of the power distribution, and calibrated frequently using the exit thermocouples for the updating of radial power distributions and the excore neutron detectors for updating axial power distributions.

The BEACON monitoring system that used the SPNOVA neutronic methodology employed one-node-per-assembly (radial) representation to achieve the rapid running times required by hardware platforms available in the late 1980s. The limited computational capabilities at the time of the initial approval with SPNOVA precluded extension of the BEACON monitoring capability to use the NRC-approved PHONIX/ANC methodology. However, recent workstation advancements, coupled with improvements in numerical solution techniques of the nodal expansion method, have permitted the optional use of the ANC neutronic code in the BEACON system while maintaining BEACON functionality. The NRC staff reviewed the Addendum 1-A to WCAP-12472-P-A and approved the use of PHOENIX-P/ANC code for the prediction of the incore detector currents and power distribution calculated from these currents.

Addendum 1-A to WCAP-12472-P-A incorporates additional features into the BEACON system, such as, (1) the use of self-powered detectors (SPD) and (2) the use of the three-dimensional advanced nodal (ANC) neutronic model code. The PHOENIX/ANC code is a licensed methodology that is supported by many critical experiments and plant data. The method is based on neutron physics and avoids the use of empirical correlations and data. Another advantage is that this method can be applied to a wider range of design and operating conditions.

The proposed BEACON-ANC methodology determines the measured power distribution by monitoring the predicted power distribution and multiplying it by the ratio of measured-to-predicted currents. The current ratio is indicative of the flux distribution. The best estimate measured power distribution is obtained by adjusting the predicted power distribution by the current ratio. The ratio of the measured-to-predicted power in each node is defined as the incore calibration constant for that node. This constant is then multiplied by the node fluxes and the node peak powers to generate the adjusted values of these parameters.

Since the BEACON monitoring system is statistical in nature, the determination of the measured peaking factor is affected by such things as the detector measurement variability, the number and layout of detectors, interpolation techniques, and any differences between predicted and true power distribution. Westinghouse implemented the BEACON system uncertainty using a statistical method in which the detector behavior is simulated on the basis of measurement variability statistics (Reference 2). Details of the calculations for the bounding 95/95 upper

-4 tolerance limit in the fuel assembly power and peak node power, the total uncertainty in the assembly power, the total uncertainty in the peak node power, the total hot channel F t.H measurement uncertainty, and the total hot channel FQ measurement uncertainty are detailed in References 2 and 3.

Implementation of the upgrade of BEACON requires that the plant-cycle-specific components shall be determined on a plant-specific basis and confirmed each cycle. The staff has determined that in order to ensure that the assumptions made in BEACON uncertainty analyses remain valid; the generic uncertainty components will require reevaluation when BEACON is applied to plant or core designs each cycle of operation.

3.2 Summary The NRC staff has reviewed the LAR (Reference 1) to evaluate the upgrade of the BEACON core monitoring and operations support system to use the three-dimensional Advanced Nodal Code (ANC) in place of SPNOVA code. The staff finds that the licensee will comply with the processes and procedures set forth in the BEACON topical reports (References 2 and 3) in implementing the update of BEACON at VCSNS, Unit 1. Accordingly, the NRC staff concludes that based on the review as discussed above, the licensee provided sufficient information to support the proposed TS changes and those changes are acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the South Carolina State official was notified of the proposed issuance of the amendments. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

S The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (October 11, 2011, 76 FR 62864). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c){9).

Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

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7.0 REFERENCES

1. License amendment request from T. D. Gatlin (SCE&G) to US NRC, proposing change to TS Administrative Controls section to allow use of Westinghouse WCAP-12472-P-A, Addendum 1-A, August 11,2011, (Agencywide Documents Access and Manqgement System (ADAMS) Accession No. ML11228A009).

2. WCAP-12472-P-A, "BEACON Core Monitoring and Operations Support System, "Westinghouse Electric Company, August 1994.

3. WCAP-12472-P-A, Addendum 1-A, BEACON Core Monitoring and Operations Support System," Westinghouse Electric Company, January 2000, ADAMS AcceSSion No.ML003678346.

4. WCAP-11596-P-A, "Qualification of the PHOENIX-P/ANC Nuclear Design System for Pressurized Water Reactor Cores," Westinghouse Electric Corporation, June 1998.

5. WCAP-12394 (Proprietary), "SPNOVA-A Multidimensional Static and Transient Computer Program for PWR Analysis," Westinghouse Electric, September 1989.

6. License amendment no. 142 for VCSNS, Unit 1, April 9, 1999, ADAMS Accession No. ML012260068.

Principal Contributor: M. Panicker, NRR Date:

May 30, 2012

May 30,2012 Mr. Thomas D. Gatlin Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88 Jenkinsville, SC 29065

SUBJECT:

VIRGIL C. SUMMER NUCLEAR STATION, UNIT 1 -ISSUANCE OF AMENDMENT ON BEACON CORE MONITORING AND OPERATIONS SUPPORT SYSTEM (TAC NO. ME6878)

Dear Mr. Gatlin:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 190 to Renewed Facility Operating License No. NPF-12 for the Virgil C. Summer Nuclear Station (VCSNS), Unit 1 in response to your application dated August 11, 2011. This amendment allows an updating of the applicable topical report in TS 6.9.1.11, "Core Operating Limits Report" to use the three-dimensional Advanced Nodal Code neutronic model.

A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's Biweekly Federal Register notice.

Sincerely, IRA!

Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-395

Enclosures:

1. Amendment No. 190 to NPF-12

2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:

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