ML20234D747
| ML20234D747 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 06/24/1987 |
| From: | Murphy W VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | Murley T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20234D749 | List: |
| References | |
| FVY-87-67, NUDOCS 8707070327 | |
| Download: ML20234D747 (6) | |
Text
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' VERMONT YANKEE Proposed Change No. 139 NUCLEAR POWER CORPORATION l
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FVY 87-67 l
RD 5, Box 169, Ferry Road, Brattieboro, VT 05301 l
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ENGINEERING OFFICE y'
L 1671 WORCESTER ROAD FR AMINGHAM, M MASSACHUSETTS 01701 4
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TELEPHONE 617-872-6100 June 24, 1987 United States Nuclear Regulatory Commission Washington, DC 20555 Attention:
Office of Nuclear Reactor Regulation Mr. T. E. Murley, Director
References:
(a) License No. DPR-28 (Docket No. 50-271)
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(b) General Electric Standard Application for Reactor Fuel
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(GESTARII), NEDE-24011-P-A-8, May 1986, ns Amended (c) Letter, USNRC to VYNPC, SER, dated November 27, 1981 i
(d) Letter, USNRC to VYNPC, SER, dated September 15, 1982 (e) Letter, USNRC to VYNPC, SER, dated September 27, 1985 (f) General Electric Company, "LOCA Analysis Report for Vermont Yankee Nuclear Power Station," NEDO-21697, I
August 1977 i
(g) Letter, USNRC to VYNPC, SER, dated November 30, 1977
Subject:
Proposed Technical Specification Change for Cycle 13 operating i
Limits I
Dear Sir:
Pursuant to Section 50.59 of the Commission's Rules and Regulations, Vermont Yankee Nuclear Power Corporation hereby proposes the following changes to Appendix A of the Operating License.
Proposed Change Vermont Yankee proposes the following changes to the Technical Specifications which are directly related to the fuel cycle design and safety analyses for Cycle 13:
- 1) incorporation of additional Maximum Average Planar Linear Heat Generation R.te (MAPLHGR) limits for the new fuel type; 2) revision of Minimum Critical Power Ratio (MCPR) limits by eliminating the fuel type dependence; and 3) updating bases section references associated with certain cycle dependent limits.
The specific changes and reasons for the changes are shown in Attachment A.
The Cycle 13 Core Performance Analysis Report (YAEC-1600) which supports Cycle 13 operation and provides the basis for the Technical Specification changes requested, is provided in Attachment B.
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United States Nuclear Regulatory Commission June 24, 1987 Attention:
Mr. T. E. Murley Page 2 Reason for Changes The Technical Specification changes for Cycle 13 operation at Vermont Yankee are proposed to allow the use of the GE fuel type BP8DRB299. This fuel type is slightly higher in enrichment than the present fuel type, P8DPB289, to allow for longer cycle lengths. This fuel type is described in Reference (b) which has been reviewed and approved by the NRC for use in operating BWRs.
The Cycle 13 core will contain 136 bundles of BP8DRB299 and 232 bundles of P8DPB289. The fuel design for Cycle 13 results in several changes to the Technical Specifications. Change 1 to the Technical Specifications adds the MAPLEGR limits for the BP8DRB299 fuel type. Change 2 removes the fuel type l
dependence of the MCPR operating limits.
Both fuel types are limited by the values in Table 3.11.2.
Finally, Change 3 is administrative and will ensure i
that the current-version of Reference (b), associated with certain cycle dependent limits is accurately incorporated by the reference in the Technical Specifications.
Basis for Changes The basis for the VY Cycle 13 licensing analysis is provided by the Vermont Yankee Cycle 13 Core Performance Analysis Report, YAEC-1600 (Attachment B).
This report presents the mechanical, thermal-hydraulic, physics, and safety analysis for Cycle 13, using approved methods described in References (c), (d), and (e).
Change 1 - the basis for this change is described in Section 8.0 of Attachment B.
The same approved ECCS evaluation methods, which are described in Reference (f) and were reviewed and approved by the NRC [ Reference (g)],
were used to calculate both the proposed MAPLEGR limits and the current limits. The limits are established to ensure conformance with 10CFR50.46.
The addition of Table 3.11-1H, "MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE" for fuel type, BP8DRB299, allows use of this fuel type during Cycle 13 and beyond. The limits, peak cladding temperature, and oxidation fraction versus exposure were transmitted in the errata and addenda notice for the approved licensing topical report { Reference (f)].
Change 2 - the basis for this change is described in Section 7.0 of Attachment B.
The same approved methods were used to calculate both the proposed MCPR limits and the current limits. The change of Table 3.11.2, "MCPR OPERATING LIMITS" will provide the bounding limits for both fuel types which are the present P8x8R limits.
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United States Nuclear Regulatory Commission June 24, 1987 Attention:
Mr. T. E. Murley Page 3 Change 3 - the Bases of the VY Technical Specifications are outdated with references to previous versions of GESTARII and overly descriptive with explicit sections in GESTARII being referenced. Accordingly, the Technical Specification Bases Section is proposed to be revised to provide for reference to the applicable GESTARII Report.
Safety Considerations These proposed changes do not present any unreviewed safety questions as defined in 10CFR50.59. As discussed in the attached Core Performance Analysis Report, the Cycle 13 core will contain the 136 new fuel type assemblies, manufactured by GE, with 232 fuel type assemblies, previously approved for use at Vermont Yankee. The acceptance criteria for the Technical Specifications associated with the Cycle 13 core design are the same as the acceptance criteria for the current Technical Specifications. The methods used to calculate the MCPR and MAPLHGR limits are proven accepted methods as described in References (c), (d), (e), and (g).
The LOCA accident snalysis calculations are described in Section 8.0 in the Core Performance Analysis Report. The accident analysis calculations are described in Section 7.0 in the Core Performance Analysis Report.
This analysis was done for the limiting fuel type and does not include analysis of the 7x7, 8x8, or 8x8R fuel types which were previously approved.
If it becomes necessary to reinsert any of these fuel types, they will be evaluated in accordance with 10CFR50.59. The bases will continue to reference the applicable GESTARII Report.
This change has been reviewed by the Vermont Yankee Nuclear Safety Audit and Review Committee (NSARC).
Significant Hazards Consideration The standards used to arrive at a determination that a request for amendment requires no significant hazards consideration are included in the Commission's regulations, 10CFR50.92, which state that the operation of the facility in accordance with the proposed amendment would not:
- 1) involve a significant increase in the probability or consequences of an accident previously evaluated; 2) create the possibility of a new or different kind of accident previously evaluated; or 3) involve a significant reduction in a safety margin.
The discussion below addresses these standards and demonstrates that the proposed amendment involves no significant hazards considerations:
(1) The first and second proposed changes to the Technical Specifications have been analyzed with respect to previously analyzed accidents. The resultant proposed changes do not increase the probability of an accident previously evaluated in the Vermont Yankee F/AR. The effect of Cycle 13 operation and the consequences of accidents, as shown in Attachment B, have not increased and continue to be well within the acceptance criteria. The third proposed change is administrative and does not affect the manner in i
l which the plant is operated. Therefore, the amendment will not involve any significant increase in the probability or consequences of an accident.
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e United States Nuclear Regulatory Commission June 24, 1987 Attention:
Mr. T. E. Murley Page 4 (2) The first and second proposed changes do not physically change the facility.
The BP8DRB299 fuel type has been used in other operating plants and does not create any new or different accident type from those already analyzed.
In addition, this fuel type is similar to those evaluated in previous calculations. The third proposed change is meant to update the reference to GESTARII. Therefore, the amendment will not create the possibility of a new or different kind of accident from any previously evaluated.
(3) The first proposed change expands the existing limiting condition for operation. The LOCA limits-were defined with approved methods such that the design basis LOCA would not violate the criteria of 10CFR50.46.
The second proposed change does not change the existing limiting condition for operation. The MCPR limits are the same as q
presently defined in the Technical Specifications for the P8x8R fuel j
type. Therefore, the acceptance criteria was met by the events analyzed. The third proposed change is administrative and thus does j
not involve any physical change to the facility nor does it change any existing limiting condition of operation or surveillance requirement.
Therefore, the amendment will not involve any reduction in a safety margin.
Therefore, we conclude that these proposed changes associated with the Cycle 13 core design do not constitute a significant hazards condition as defined by 10CFR50.92.
Fee Determination In accordance with the provisions of 10CFR170.12, the application fee of
$150.00 is enclosed.
Schedule of Change These changes will be incorporated into the Vermont Yankee Technical Specifications as soon as practicable following receipt of your approval. A timely review and approval of this submittal consistant with the Cycle 13 startup schedule is requested. Accordingly, since Cycle 13 startup is
i United States Nuclear Regulatory Commission June 24, 1987 Attention:
Mr. T. E. Murley Page 5 scheduled for September 28, 1987, we request approval of this submittal by September 14, 1987.
We trust that the information above adequately supports our request; however, should you have any questions on this matter, please contact us.
Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION M ^h w
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Warren P.
i Vice President and Mana r of Operations WPM /dhm
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l Enclosure j
i Attachment cc: Vermont Department of Public Services 120 State Street Montpelier, VT 05602 Attention:
Mr. G. Tarrant, Chairman i
STATE OF VERMONT
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OF WINDHAM COUNTY
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Then personally appeared before me, Warren P. Murphy, who, being duly sworn, did state that he is a Vice President and Manager of Operations of Vermont Yankee Nuclear Power Corporation, that he is duly authorized to execute and file the foregoing document in the name and on behalf of Vermont Yankee Nuclear Power Corporation, and that the statements therein are true to the best of his knowledge and belief.
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l M.Mcp Diane McCue j
Notary Public
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My Commission Expires NOTARY
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ATTACHMENT A Description of Proposed Changes to Technical Specifications i
Section/ Location Change Reason for Change l
1.
Section 3.11A:
Add MAPLHGR limits for Tc incorporate page 180-a, the fuel type, adaitional limits Table 1, page 180-f BP8DRB299-7G4.0.
consictent with Table 3.11-1H, page 180-n6 anticipated fuel type operation.
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2.
Section 3.110:
Elimin:.ce the fuel type To define bounding Table 3.11-2, dt.4etidence in the limits based on the page 180-01 MCPn limits.
present P8x8R
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Technical Specification limits.
3.
Section 3.11A Bases.
Change reference to To update the page 180-d the most recent reference for the Section 3.11B Bases, revision of GESTARII.
Bases which page 180-g describes the MAPLHGR and LHGR calculation.
Summary of Technical Specification Changes Delete the Following Pages Insert the Following Pages 180a 180a 180d 180d 180f 180f 180g 180g 180-n6 180-01 180-01 J
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