ML082600573
| ML082600573 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 09/02/2008 |
| From: | Safin F Public Service Enterprise Group |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| WCAP-15942-P-A NFS-0255, Rev 0 | |
| Download: ML082600573 (18) | |
Text
Attachment 2 LR-N08-0204 Hope Creek Generating Station Facility Operating License NPF-57 Docket No. 50-354 Initial Implementation of WCAP-1 5942-P-A (Formerly CENP-287), -Fuel Assembly Mechanical Design Methodology for Boiling Water Reactors Supplement I to CENP-287 Evaluation of Control Blade Interference (Non-Proprietary)
NFS.0255, Revision 0
Non-Proprietary NFS-0255 Revision 0 NFS-0255 Revision 0 September 2, 2008 Hope Creek Generating Station Initial Implementation of WCAP-15942-P-A (Formerly CENP-287), Fuel Assembly Mechanical Design Methodology for.Boiling Water Reactors Supplement 1 to CENP-287.
Evaluation of Control Blade Interference (Non-Proprietary)
Prepared by:
ErahGcis J Safin Senior Fuel Project Engineer Reviewed by:
7:::
JamesP Collins Core Design & Methods.Engineer Approved by:.
(Iý1 V'
Donald V Notigan Manager - BWR Design.& Analysis Date: qM10 a Date:
9*Z./o Date: __-___
Page-1 of'11
Non-Proprietary NFS-0255 Revision 0 Table of Contents Section Title Page
- 1.
INTRODUCTION 3
- 2.
WCAP-15942-P-A NRC SER INFORMATION REQUIREMENTS 3
- 3.
HCGS -RESPONSE TO WCAP-15942-P-A NRC SER INFORMATION 4
- 4.
REFERENCES 11 Page,2 of 11
Non-Proprietary NFS-0255 Revision 0
- 1.
INTRODUCTION-Hope Creek Generating Station (HCGS) is operating in Cycle 15. The Cycle 15 reload core is comprised of 548 GE14-fuel assemblies and 216 SVEA-96+-fuel
-assemblies. Cycle-15-began on 11/15/2007 and is-scheduled to shutdown for a refueling outage -on 04/10/2009. Cycle 15 is the last cycle of planned operation for the SVEA-96+ fuel assembly design.
Prior to the end of Cycle 15, the burnup limit for the mechanical design of the SVEA-96+ fuel assembly that is currently established in the Updated Final Safety Analysis Report (UFSAR) will be exceeded. The current limit of 50 Gwd/Mtu rod average burnup for the mechanical design of the SVEA-96+ fuel is justified for Hope Creek through the application of the Westinghouse (formerly ABB/CENP)
NRC approved topical, ABB Combustion Engineering Nuclear Power, "Fuel Assembly Mechanical'Design Methodology for Boiling Water Reactors", CENPD-287-P-A, July 1996, UFSAR reference 4.2-6.
In February of 2006, Westinghouse obtained NRC approval of a supplement-to the Mechanical.Design Methodology topical which supports extending-the burnup limit for the mechanical design of SVEA-96+ to 62 Gwd/Mtu; Reference 4.1:
WCAP-15942-P-A (Formerly CENP-287), Fuel Assembly Mechanical Design Methodology for-Boiling Water Reactors Supplement 1 to CENP-287. HCGS will incorporate this supplemental reference into the UFSAR prior to the end of Cycle
- 15. The approved topical will be incorporated into the design and licensing basis in accordance with 10 CFR-50.59 requirements (implementing a generically approved methodology within the-terms and conditions of the NRC SER on the methodology). One requirement-of the terms and conditions of the NRC SER on WCAP-15942-P-A is that the first time-that a licensee references the approved topical, certain specific information must be supplied to the NRC. This report provides the HCGS responses to the SER information requirements.
Cycle specific reload evaluations performed by Global Nuclear Fuels (HCGS's current fuel supplier) in accordance with General Electric Standard Application for Reactor Fuel, NEDE-24011-P-A-15 and the U. S. Supplement, NEDE-24011-P-A-1 5-US, will utilizethe updated burnup limit as an input to determine-any impact on the cycle specific reload licensing bases for the remainder of Cycle 15.
Any changes to the cycle specific reload licensing -bases for the remainder of Cycle 15 will be implemented in accordance with existing HCGS reload control procedures.
- 2. WCAP-15942-P-A NRC SER INFORMATION REQUIREMENTS The following in italics is from the Safety Evaluation -by the Office of Nuclear Reactor Regulation, Topical Report WCAP-1 5942, -"Fuel Assembly Mechanical Design Methodology for Boiling Water Reactors -. Supplement 1 to CENP-287,"
Page 3 of 11
Non-Proprietary NFS-0255 Revision 0 Revision 0, Westinghouse Electric Company, Project 700. The required information request is shown.
4-.0 LIMITATIONS AND CONDITIONS Licensee's referencing WCAP-15942-P must comply with the following limitations and conditions:
- 4. During initial implementation, licensees must submit to the NRC an evaluation of control blade interference taking into account manufacturing tolerance, channel bulge, and channel bow over the life of the fuel assemblies (similar to RAI No. 15 response). As part of this evaluation, the licensee must demonstrate the following:
- a. The calculated maximum channel-to-control rod interference (blade and roller/pad) must be less than that determined for-the reference plant defined in the response to RAI No. 15.
- b. Westinghouse's channel.bow database remains valid. This demonstration must.consider the materials and manufacturing process employed in the fabrication of the SVEA channels.
- c. The control rod force-time [ ((Paccumulator X Aannulus) tcR-73%) / MCR] for the target plant must be calculated using the methodology outlined in the response to RAI No. 15 and the value of the control rod force-time must be greater than or equal to the force-time parameter for the reference plant.
- d. The SVEA channel experience is applicable for the specific application and continues to be bounded by the database presented in the response to RAI No. 15. This condition is satisfied by assuring the trend in control rod insertion.time (e.g., the number of "slow" control rods) in U. S. plants which have implemented SVEA fuel channels since.the time of issuance of this -safety evaluation. This demonstration should identify the number of "slow" control rods as well as the historical significance of these indications. Updates to the database reflecting new channel bow data measurements may be used to address increasing trends in the numbers of slow rods. The updated database will be used as the bases to evaluate control blade interference.
.3. HCGS.RESPONSE-to WCAP-15942-P-A NRC SER INFORMATION REQUIREMENTS Information -Request 4.a The -calculated maximum channel-to-control rod interference (blade and
-roller/pad) must-be less thanthat determined for the reference plant defined in the response-to RAI No. 15.
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Non-Proprietary NFS-0255
'Revision 0
Response
The channel-to-control rod interference is calculated following the methodology in,RAI # 15 of WCAP-1 5942-P-A.
[
.Ia,c Page 5 of 11
Non-Proprietary NFS-0255 Revision 0
[
ac The calculated maximum channel / control rod roller/pad interference and maximum channel / control blade interference are bounded by the numbers from the reference plant case in RAI #15 of WCAP-1 5942-P-A.
Information Request.4.b Westinghouse's channel bow database remains valid. This demonstration must consider the materials and manufacturing process -employed in the fabrication of the SVEA channels.
Response
The.current reference.database.used for the evaluation of control blade interference contains data from -the 10xl 0SVEA designs-including the SVEA-96, SVEA-96+, SVEA-96 Optima and SVEA-96 Optima2 designs. The mechanical design of the channels for these designs -has not been modified in a -manner which would.affect channel bow or bulge. The channel material has evolved from Zircaly-4 in earlier designs to-the current Zircaloy'2 channels. Furthermore, the annealing process has been improved to provide greater uniformity. Both ofthese changes tend -to reduce channel bow.
Therefore, the entire database provides a conservative description of the current SVEA-96+ channels which are in-the HCGS plant with respect to channel bow.
Information Request-4.c The control rod force-time[ ((Paccumulator X Aannulus) -tCR-73%)- / McR ]-for the target plant must be calculated using-the methodology outlined in the response-to RAI No. 15 and the value of the control rod force-time must be greaterthan or equal to the force-time -parameter for-the reference plant.
Response
The insertion force-time parameter for the -reference plant in RAI # 15 of WCAP-15942-P-A is calculated as:
[]'ac Page 6 of 11
Non-Proprietary NFS-0255 Revision 0 a,c Information Request 4.d The SVEA channel -experience is applicable for-the specific application and continues to be bounded by the database presented in the response to RAI No. 15. This condition is satisfied.by assuring the trend in control rod
.insertion time (e.g., -the number of "slow" control rods) in U. S. plants which have implemented SVEA fuel channels.since the time of issuance of this safety evaluation. This demonstration should identify the number of "slow" control rods as well as the historical.significance of these indications.
Updates to-the database reflecting new channel bow data measurements may be used to address increasing trends in the numbers of slow rods. The updated database will -be used as the bases to evaluate control blade interference.
Response
HCGS first loaded the SVEA-96+fuel design in Cycle 10. The Cycle 10 core was comprised of SVEA-96+ fuel and GE9-fuel. SVEA-96+ fuel was loaded
.in Cycles 11 and 12, with Cycle 12 being predominantly SVEA-96+ fuel. For Cycle 13, HCGS transitioned to-the GE14 fuel design and has loaded that
-design for reloads up to the current operating Cycle 15. Over this time period with the core comprised of the SVEA-96+ fuel design and GE fuel designs, no adverse trends in control rod insertion time have been observed that would indicate the onset of "slow" control rods. The following figures (4.d.1 to 4.d.4) illustrate the control rod insertion time performance trend. The figures include Technical Specification scram time data collected from-beginning of Cycle 9 to-current operating Cycle 15.
Table 4.d.1 provides cyclespecific scram insertion time information for each cycle. 'The information in the table illustrates no adverse trend in control rod insertion performance indicating the onset of slow-control rods and shows-that all measured times are-within Technical Specification -requirements.
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Non-Proprietary N FS-0255 Revision 0
.Page 8 of 1-1
Non-Proprietary NFS-0255 Revision 0 Page 9 of 11
Non-Proprietary NFS-0255 Revision 0 Table 4.d.1 Cycle Specific Control Rod SCRAM Insertion Time Data to 90%
Inserted Cycle 9
10 11 12 13 14 15 Slowest 3.20 3.16 2.78
,2.64 2.71 2.69 2.69 Recorded Mean 2.34 2.37 2.38 2.37 2.40 2.38 2.36 Standard Dvation 0.11 0.11 0.09 0.09 0.10 0.10 0.10 DeviationIIIII Technical Specification Requirements (insertion time is from the fully withdrawn position to the indicated % inserted):
Average-scram insertion time to 90% = 3:49 seconds Four control rod group insertion timeto 90% = 3.70 seconds Maximum scram insertion time of each control rod to 90% = 7.0 seconds Page 10 of 11
Non-Proprietary NFS-0255 Revision 0
- 4. References 4.1 HCG.5-0080, WCAP-1 5942-P-A (Formerly CENP-287), Fuel Assembly Mechanical Design Methodology for Boiling Water Reactors Supplement 1to CENP-287.
Page 11 of 11 Westinghouse Proprietary Information LR-N08-0204 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). The justification 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).
Westinghouse Westinghouse Electric Company Nuclear Services P.O. Box 355 Pittsburgh, Pennsylvania 1 5230-0355 USA Directtel: (412) 374-4643 Directfax: (412) 374-4011 e-mail: greshaja@westinghouse.com U:S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Our ref: CAW-08-2469 August.27, 2008 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE
Subject:
NFS-0255, "Hope Creek Generating Station, Initial Implementation of WCAP-15942-P-A (Formerly CENP-287), Fuel AssemblyMechanical Design Methodology for Boiling Water
.Reactors Supplement 1 to CENP-287, Evaluation of Control Blade Interference" (Proprietary)
The proprietary informationwfor which withholding is being requested in the above-referenced report is further identified.in Affidavit CAW-08-2469 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 PSEG Nuclear LLC.
Correspondence with respect to the proprietary aspects of the application for withholding or the Westinghouse affidavit should reference this letter, CAW-08-2469 and should be addressed to J. A. Gresham, Manager, Regulatory Compliance and Plant Licensing, Westinghouse Electric Company LLC, P.O. Box 355, Pittsburgh, Pennsylvania 15230-0355.
Very truly yours, J. A. Gresham, Manager Regulatory Compliance and Plant Licensing Enclosures cc:
G. Bacuta/NRR
CAW-08-2469 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:
& J. A. Gresham, Manager Regulatory Compliance and Plant Licensing
- Sworn to and subscribed before me this y of
,2008 Notary Public COMMONWEALTH OF PENNSYLVANIA I
NotafSew Shamn L Marlde, Notaty Pubic aonrol Boo, AIheny County MYeCmb, en a AresoJano29,t2011 Member, PennsylaIs Association of Notaries-
,2 CAW-08-2469 (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) 1 have personal knowledge of the criteria and procedures utilized by Westinghouse in designating information as a trade secret, privileged oras 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.
(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.
3 CAW-08-2469 (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.
(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.
4 CAW-08-2469 (v)
The proprietary information sought to be withheld in this submittal is that which is appropriately marked in NFS-0255, "Hope Creek Generating Station, Initial Implementation of WCAP-1 5942-P-A (Formerly CENP-287), Fuel Assembly Mechanical Design Methodology for Boiling Water Reactors Supplement 1 to CENP-287, Evaluation of Control Blade Interference" (Proprietary) being transmitted by PSEG Nuclear LLC letter and Application for Withholding Proprietary Information from Public Disclosure, to the Document Control Desk. The proprietary information as submitted by Westinghouse for use by Hope Creek is in response to conditions and limitations of an NRC safety evaluation.
This information is part of that which will enable Westinghouse to:
(a)
Support PSEG's use of WCAP-15942-P-A at Hope Creek.
Further this information has substantial commercial value as follows:
(a)
Westinghouse can use this information to further enhance their licensing position with their competitors.
(b)
Assist customers to obtain license changes.
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 analyses 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.