ML20249A789

Amend 149 to License DPR-3,revising TS Sections Re Min Water Cover Over Spent Fuel,Crane Travel Over Spent Fuel & Related Bases

ML20249A789
Person / Time
Site:	Yankee Rowe
Issue date:	06/17/1998
From:	Weiss S NRC (Affiliation Not Assigned)
To:
Shared Package
ML20249A785	List: ML20249A784 ML20249A789 ML20249A790
References
NUDOCS 9806180240
Download: ML20249A789 (8)

Text

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ga nro 3 "- t UNITED STATES s# o NUCLEAR REGULATORY COMMISSION o WASHINGTON, D.C. 20555-0001

%, . . . . . ,5 YANKEE ATOMIC ELECTRIC COMPANY DOCKET NO. 50-29 YANKEE NUCLEAR POWER STATION 1

l AMENDMENT TO (POSSESSION ONLY) LICENSE License No. DPR-3 Amendment No.149

1. The U.S. Nuclear Regulatory Commission (the Commission or th- NRC) has found that:

A. The application for amendment filed by Yankee Atomic Electric Company (the licensee) dated September 5,1997, and as supplemented by letter dated March 30, 1998, 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 be maintained in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance: (l) 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 set forth in 10 CFR Chapter I; 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.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment. Paragraph 2.C.(2) of Facility Operating (Possession Only) License No. DPR-3 is hereby amended to read as follows:

(2) 1 ech$ cal Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.149, are hereby incorporated in the license. The licensee shall possess and maintain the facility in accordance with (ne Technical Specifications.

9806180240 980617 PDR ADOCK 05000029 P PDR

3. This license amendment is effective on implementation of crane modifications.

FOR THE NUCLEAR REGULATORY COMMISSION AA 4 Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: June 17, 1998

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ATTACHMENT TO AMENDMENT NO.149 FACILITY OPERATING (POSSESSION ONLY) LICENSE NO. DPR-3 DOCKET NO. 50-29 l

l Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by ar.ier.dment number and contain vertical lines indicating the areas of change, Remove Insert 3/4 3/4-2 3/4-3 3/4-3 3/4-4 3/4-4 B3/4-3 B3/4-3 B3/4-4 B3/4-4 1

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3/4.1 SPENT FUEL PIT WATER LEVEL LIMITING CONDITION FOR OPERATION 3.1.1 At least 14 feet of water shall be maintained over the top of irradiated fuel assemblies seated in the storage racks.

3.1.2 At least 5 feet of water shall be maintained over the top of irradiated seated fuelstorage in the assemblies racks.while the fuel assemblies ere not 3.1.3 Irradiated fuel assemblies may be transported in or out of the spent fuel pit, without the minimum 5 feet of water over the top of the irradiated fuel assemblies, when they are transported within a shipping and/or transfer cask.

APPLICABILITY:

Whenever irradiated fuel assemblies are in the spent fuel pit.

ACTION:

With the requirements of the specification not satisfied, place irradiated components in a safe condition and suspend fuel handling operations within the spent fuel pit and crane operations with loads over the spent fuel pit. Restore water level to within its limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.1.1 The water level in the spent fuel pit shall be determined to be j at least its minimum required depth at least once per 7 days I when irradiated fuel assemblies are in the spent fuel pit.

l YANKEE-ROWE 3/4-2 E__________________

3/4.2 CRANE TRAVEL SPENT FUEL PIT LIMITING CONDITION FOR OPERATION 3.2 Loads in excess of 900 pounds shall be prohibited from travel over the spent fuel pit except for the:

a. Spent Fuel Storage Building roof hatches.

b. Spent fuel inspection stand.

c. Fuel handling equipment.

d. Spent fuel racks.

e. Cask components and associated lifting devices,

f. Shipping and/or transfer casks: 80 tons maximum gross weight on Yard Area Crane.

g. Shipping cask liners. I

h. Volume reduction equipment.

'i. Cask set down pad and j.

Spent fuel assembly nondestructive test equipment. l APPLICABILITY: With fuel assemblies in the Spent Fuel Pit.

ACTION: t With the requirements of the above specifications not satisfied, place the crane load in a safe condition.

SURVEILLANCE REQUIREMENTS 4.2.1 Loads in excess of 900 pounds shall be prevented from traveling over the spent fuel pit by administrative control, except that the:

a. Spent Fuel Storage Building roof hatches. spent fuel inspection stand, fuel handling equipment, spent fuel racks. spent fuel assembly nondestructive test equipment.  ;

cask set-down pad shipping cask liners, volume reduction

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equipment, cask components and associated lifting devices.

and shipping and/or transfer casks may travel over the spent fuel pit in accordance with approved written procedures:

I YANKEE-ROWE 3/4-3 i

3/4.2 CRANE TRAVEL - SPENT FUEL PIT SURVEILLANCE RE0VIREMENTS (Continued) b.

The volume reduction equipment, the spent fuel inspection stand, and the spent fuel assembly nondestructive test equipment shall be prevented from traveling over fuel assemblies in the spent fuel pit by administrative control.

The volume reduction equipment (when transported by the Yard Area Crane), the shipping cask liners, the cask set-down pad, and the shipping and/or transfer casks shall be prevented from traveling over fuel assemblies in the spent fuel pit by administrative control and by the Yard Area Crane travel limit switch, which prevent movement of these loads beyond the southern end of the safe load path.

The cask hatch cover and the cask components and associated lifting devices shall be prevented from traveling over spent fuel assemblies stored in the spent fuel pit by administrative control and by the Yard Area Crane travel limit switch, except that the cask hatch cover and the cask components and associated lifting devices may be allowed over the spent fuel assemblies in the shipping and/or transfer cask when used in conjunction with cask operations; and

c. Fuel handling equipment, when moved for maintenance, shall be prevented from traveling over fuel assemblies in the spent fuel pit by administrative control.

YANKEE ,ROWE 3/4-4

3/4.1 SPENT FUEL PIT WATER LEVEL BASES The restriction of 14 feet of water cover for irradiated fuel assemblies seated in storage racks ensures that sufficient water depth is available to remove 90% of the approximately 30% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimem water depth is consistent with the assumptions of the accident analysis.

The restriction of 5 feet of water cover for irradiated fuel assemblies not seated in the storage racks ensures that the exposure to personnel in the spent fuel pit area during fuel movements will be maintained ALARA.

When spent fuel is transported in or out of the spent fuel pit within a shipping and/or transfer cask, shielding for personnel exposure is provided by the cask system. The cask system ensures that exposure to personnel will be maintained ALARA.

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YANKEE-ROWE B3/4-3

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3/4.2 CRANE TRAVEL - SPENT FUEL PIT l

BASES l

1 The restriction on movement of loads in excess of the nominal weight of a fuel assembly over fuel assemblies in the spent fuel pit ensures that in the event this load is dropped (1) the activity release wil'n be limited to that contained in a single fuel assembly, and (2) any possible a critical distortion array. of the fuel in the storage racks will not result in release assumed in the accident analysis.This assumption is consistent wit Handling of the present Spent Fuel Storage Building roof hatches under administrative control-will assure safe handling of the roof hatches.

The restriction of movement of the spent fuel inspection stand, the spent fuel assembly nondestructive test equipment, the cask hatch cover, l the volume reduction equipment, and the shipping cask liners over spent fuel ensures that these items cannot be dropped on spent fuel. Dropping l any one of these items from its maximum height will not result in loss of integrity of the spent fuel pit floor.

equipment for infrequent maintenance under administrative control willHandlin!

ensure the safe handling of any fuel handling components. l T

he use of a single-fatlure proof crane provides assurance that a credible single failure will not result in the shipping and/or transfer cask, the cask set-down pad, the cask hatch cover, and the cask

components and associated lifting devices having an adverse effect on the spent fuel pit or the irradiated fuel in the spent fuel pit. The restriction on movement of the shipping and/or transfer cask, the cask set-down pad, the cask hatch cover, and the cask components and lifting devices further ensures that these items cannot be dropped on spent fuel in the spent fuel pit storage racks. The use of a single failure proof crane ensures that the cask hatch cover and the cask components and associated lifting devices, which are permitted over the spent fuel in the~ cask, cannot be dropped on the~ spent fuel. The safe load path is established to support the defense-in-depth approach to safety concerning heavy loads over the spent fuel pit. Deviations from or changes to the safe load path shall be performed in accordance with approved written procedures which have been approved by PORC.

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YANKEE.ROWE B3/4-4