ML20198N495

Forwards Supplemental Info in Support of 10CFR70.24 Exemption Request,Dtd 971216.Addl Info Addresses Applicability of Seven Criteria to Vermont Yankee Nuclear Power Station

ML20198N495
Person / Time
Site:	Vermont Yankee
Issue date:	01/13/1998
From:	Reid D VERMONT YANKEE NUCLEAR POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BVY-98-04, BVY-98-4, NUDOCS 9801210093
Download: ML20198N495 (4)

Text

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VERMONT YANKEE M

• J NUCLEAR POWER CORPORATION 185 Old Fe'try Road, Brattleboro, VT 05301 7002 (802) 257 5271 January 13,1998 BVY 98-04 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Referenco: Letter, VYNPC in USNRC, BVY 97-168, dated December 16,1997

Subject:

Vermont Yankee Nuclear Power Station L! cense No. DPR-28 (Docket 50 271)

Supplementalinformation in Support of Part 70.24 Exemption Request The purpose of this lotter is to supplement our 10CFR Part 70.24 exemption request submittal (see Reference) addressing the applicability of seven criteria to the Vermont Yankee Nuclear Power Station. These criteria that usually are utilized in granting such exemptions and our corresponding responses are contained in the atiachment.

We trust this information is satisfactory; however, should you have any questions, please do not hesitate to contact this offico.

Sincoroly, VERMONT YANKEE NUCLEAR POWER CORPORAT ON s

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Donald A. Reid Senior Vice President, Oprations Attachment t

cc: USNRC Prclect Manager, VYNPS '

USNRC Region 1. Administrator USNRC Resident inspector, VYNPS '

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VT Department of Public Service 9001210093 980113 PDR ADOCK 05000271 P PDR

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l l VERMONT YANKEH NUCLEAR POWER CORI' ORATION I .

Docket No. 50 271 BVY 98-04 '

Pare 1 of 3 Attachment Response to NRC Criteria Regarding Part 70.24 Exemption Re'q uests Criterion 1. Plar , procedures do not permit more than [1 PWR or 3 BWR) fuel

[ assembly /au 'mblies) to be in transit between their associated shipping cask and dry storage rack at one time.

Response: This is met by Plant Procedures OP 1400 e'd 1401 which limit the maximum number of assemblies that can be in transit to two. After removal of the outer shipping container, the metal box containing two assemblies is moved to the air lock w;th additional boxes, following which they are temporarily stored on the refuel floor level by stacking them no more than three high (GE's recommended limit based on maintaining the applicable k n for a flooding condition is no more than four high). Individual boxes are then moved to the staging area where the metal cover is removed. The box is then brought to the upender where the fuel assemblies are individually removed and taken to the inspection or storage areas, s

Criterion 2. The k-effective qf the fresh fuel storage racks filled with fuel of the maximum permissible U 235 enrichment and flooded with pure water does not exceed 0.95, at a 95% probability,95% confidence level.

Response: This is met by Vermont Yankee. See Tech Spec 5.5A. It is to be noted that this calculation was performed by General Electric (the fuel vendor) and specific information as to the 95/65 requirement was not readily available. However, the reports GE uses for performing this type of calculation (e.g., SAFER /GESTP.) have been approved by the NRC and, as with similar Vermont Yankee reports (see below) would have been accepted for use if, among other things, they had met this requirement.

VERMONT Y ANKSE NUCLEAR POWER CORPOR ATION Docket No. 50 271 BVY 98 04 Page 2 of 3 Cri'erion 3. If optimum moderation of fuelin the fresh fuel storage racks occurs

• when the fresh fuel storage racks are not flooded, the k-offective corresponding to this optimum moderation does not exceed 0.93, at a 95% probability,95% confidence level.

Response: Vermont Yankee has no plans to store future new fuelin the New Fuel Storage Vault. Upon receipt, the Cycle 20 fuel will be channeled and stored in the Spent Fuel Storage Pool (SFSP) until it is loaded into the core. Plant Procedure OP 1401 defines the procedural steps to be used in tiansferring new fuel following its temporary storage on the refuel hoor (see Response to Criterion 1, above) to storage in the SFSP. (For et least the last three fuel cycles, the new fuel was stored in the SFSP.) A pre job briefing and/or written direction is provided, by the designated Fuel Inspection Supervisor, to management of, and key personnel involved in these fuel handling activities. Fuel is loaded into the SFSP by qualified personnel under the direction of the designated Fuel inspection Supervisor using maps whbh assign specific storage Iccations to each new fuel assembly (by assembly number).

Criterion 4 The k offective of spent fuel storage racks filled with fuel of maximum permissible U 235 enrichmem and filled with pure water does not exceed 0.95, at a 95% probability,95% confidence level.

Response: This is met by Vermont Yankee. See Tech Spec 5.5B. VY Calculation No. VYC-339, "VY Spent Fuel Rack Criticality Analysis", in Section 1.1, states that "the objective of this analysis is to assure that the.... Vermont Yankee spent fuel storage racks maintain a k.n s .95 under normal and abnormal storage conditions with a 95% probability at a 95% confidence level" (emphasis added).

Criterion 5 The quantity of forms of special nuclear material, other than nuclear fuel, that are stored cn site in any given area is less than the quantity necessary for a critical mass.

VIIRMONT Y ANKun NUCLEAR POwnn CORPOR ATION Docket No. 50-271 BVY 98 04 Page 3 of 3 Response: This is met by Vermont Yankee, as stated in the Attachment to our exemption request letter (BVY 97168, dated December 16,1997);

see paragraphs 2 and 3 of Section ll.B.1. M Critorion 6 Radiation monitors, as required by GDC 63, are provided in fuel storage and handling areas to detect excessive radiation levels and to initiate appropriate safety actions.

Response: This is met by Vermont Yankee. See FSAR Appendix F. page F2-16, which addresses GDC 63, and Table 7.13.2, which indicates that area radiation monitors are located at the West Refuel, Spent Fuel Pool and New Fuel Vault areas of the Reactor Building. Plant Or "ng Procedures OP 1100 and 1101 specify cctions to be j taker, o.e., evacuation) when a high radiation a! arm is sounded.

Criterion 7 The maximum nominal U-235 enrichment is 5 wt%.

Response: This is met by Vermont Yankee. A letter fiom General Electric (the fuel supplier for Cycle 20), " Vermont Yankee R19/C20 Final Fuel Bundle Ocsign Reports" (dated July 13,1997), transmitted two proprietary Fuel Bundle Design Reports, EDB Nos. 2278 and 2279.

Review of the fuel pellet maps and specifications in these reports clearly indicates that the maximura enrichment does not exceed 5 * 'o.

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