ML20204C456

Amend 162 to License DPR-36,revising App a TS of License DPR-36 to Change Limiting Condition for Operation for Fuel Storage Pool Water Level from 23 Feet to 21 Feet

ML20204C456
Person / Time
Site:	Maine Yankee
Issue date:	03/16/1999
From:	Weiss S NRC (Affiliation Not Assigned)
To:
Shared Package
ML20204C453	List: ML20204C450 ML20204C456 ML20204C463
References
NUDOCS 9903230104
Download: ML20204C456 (6)

Text

. .. - - . - . . - . - ~. . - _ - ._- - . .-- -. .-. - - - _ - .

l

e +

yaine Y,ankee Atomic Power Company '.Jocket No. 50-309 l

cc:

Mr. Charles B. Brinkman Friends of the Coast Manager - Washington Nuclear P.O. Box 98 Operations Edgecomb, ME 04556 ABB Combustion Engineering 12300 Twinbrook Parkway, Suite 330 Mr. William O' Dell l Rockville, MD 20852 Operations Director Maine Yankee Atomic Power Company )

Thomas G. Dignan, Jr., Esquire 321 Old Ferry Road Ropes & Gray Wiscasset, ME 04578-4922 l One International Place Boston, MA 02110-2624 Mr. George Zinke, Director Nuclear Safety and Regulatory Affairs Mr. Uldis Vanags Maine Yankee Atomic Power Company State Nuclear Safety Advisor 321 Old Ferry Road State Planning Office Wiscasset, ME 04578-4922 State House Station #38 Augusta, ME 04333 Mr. Jonathan M. Block Attorney at Law Mr. P. L. Anderson, Project Manager P.O. Box 566 Yankee Atomic Electric Company Putney, VT 05346-0566 580 Main Street Bolton, MA 01740-1398 Mr. Michael J. Meisner, President Main Yankee Atomic Power Company Regional Administrator, Region 1 321 Old Ferry Road U.S. Nuclear Regulatory Commission Wiscasset, ME 04578-4922 i 475 Allendale Road

'ing of Prussia, PA 19406 Mr. Robert Fraser, Director Engineering First Selectman of Wiscasset Maine Yankee Atornic Power Company Municipal Building 321 Old Ferry Road U.S. Route 1 Wiscasset, ME 04578-4922 Wiscasset, ME 04578 Mr. Patrick J. Dostie Mr. Mark Roberts State of Maine Nuclear Safety U.S. Nuclear Re3ulatory Commission Inspector 475 Allendale Road Maine Yankee Atomic Power Company King of Prussia, PA 19406 321 Old Ferry Road l Wiscasset, ME 04578-4922 Mary Ann Lynch, Esquire

)

Maine Yankee Atomic Pcwer Company Mr. Mark Ferri, Vice President 321 Old Ferry Road Decommissioning Director Wiscasset, ME 04578-409.2 Maine Yankee Atomic Power Company 321 Old Ferry Road Mr. Neil Sheehan Wiscasset, ME 04578-4922 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 WO3230104 990316 PDR ADOCK 05000309 P PDR

f RE%

[&

[" .. UNITED STATES . ,

j

.Z1. ). j NUCLEAR REGULATORY COMMISSION . .

"t WASHINGTON. D.C. 20555-0001

%...../

MAINE YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-309 MAINE YANKEE ATOMIC POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.162 License No. DPP. '26

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

A. The application for amendment filed by the Maine Yankee Atomic Power Company (the l'censee) dated April 13,1998, as supplemented Novernber 5, 1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the rules and regulations of the Commission as set forth in 10 CFR Chapter I; B. The facility will be maintained in conformity with the application, as amended, 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 regulations of the Commission:

D. The k?uance of this amendment will not be inimical to the common deferu 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 regulations of the Commission and all applicable requirements have been satisfied.

l l

i i

1

_ . ~ -____ - - - _ _ . . . . _. . _ _ _ ._ .-_m . _ _ _ . _

L- t t

. ~

l l 2 '

l i

2. Accordingly, the license is amended by changes to the Technical Specifications as -

indicated in the attachment to this license amendment, and paragraphs 2.B.(6)(b) of  ;

Facility Operating License No. DPR-36 is hereby amended to read as follows:

{

Technical Specifications l (b) The Technical Specifications containea in Appendix A, as revised through  :

Amendment No.162, are hereby incorporated in the license. The licensee will maintain the facility in accordance with the Technical Specifications.  ;

3. This license amendment is effective as of the date of its issuance and shall be i implemented no later than 30 days from the date of issuance. '

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

{

I

Attachment:

Changes to the Technical '

Specifications I

Date of issuance: March 16, 1999 '

i l

l l

l

ATTACHMENT TO LICENSE AMENDMENT NO.162 FACILITY OPERATING LICENSR_NO. DPR-36 DOCKET NO. 50-309 Replace the following pages of Appendix A Technical Specifications with the attached pages.

The revised pages are identified by amendment number and contain verticallines indicating the areas of change.

Remove insert 3-3 3-3 8 3.1-1 B 3.1-1 B 2.1-2 B 3.1-2 .

B 3.1-3 B 3.1-3 l

l l

i . .- .

Fuel Storage Pool Water Level 3.1.1 l

3.1 DEFUELED SYSTEMS l

3.1.1 Fuel Storage Pool Water Level LCO 3.1.1 The fuel storage pool water level shall be 2 21 ft. over the top l l of irradiated fuel assemblies seated in the storage racks.

APPLICABILITY: During movement of irradiated fuel assemblies in the fuel storage pool.

A_CTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Fuel Storage pool water A.1 Suspend movement of immediately level not within limit, irradiated fuel assemblies in the fuel storage pool.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify the fuel storage pool water level is 2 21 ft 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l above the top of irradiated fuel assemblies seated in the storage racks.

Maine Yankee 3-3 Amendment 46+. 162

.~. . .

Fuel Storage Pool Water Level B 3.1.1 B 3.1 DEFUELED SYSTEMS B 3.1.1 Fuel Storage Pool Water Level BASES BACKGROUND The minimum water level in the fuel storage pool meets the assumptions of iodine decontamination factors following a fuel handling i accident. The specified water level provides shielding during the

, movement of spent fuel and minimizes the general area dose.

A general description of the fuel storage pool design and the fuel storage pool cooling and purification system is given in the SAR. The assumptions of the fuel handling accident are given in the SAR.

APPLICABLE The Maine Yankee facility is permanently shutdown and the time SAFETY ANALYSES since the last operation of the reactor has allowed significant decay of fission products (especially the daughter products with short half-lives) contained in the spent fuel. The spent fuel pool water level is adequate to provide necessary shielding for the fuel handlers to minimize occupational dose during normal spent fuel handling activities.

The accident analysis for the fuel handling accident, as described in the l FSAR, assumes that the accident occurs one-year after shutdown from l operations and a decontamination factor for iodine of 75 (19 feet of I water.) No credit is taken for ventilation air filtration or isolation. For l the purpose of establishing an upper limit on the amount of fuel damage resulting from a fuel handling accident, it is assumed that the fuel assembly is dropped during handling. The number of ruptured fuel rods which would result depends on several variables including the kinetic energy at impact and fuel assembly orientation during impact.

The analyses indicate that if a fuel assembly were dropped to the bottom of the fuel storage pool and then rotated and struck a protruding structure, only the outer row of fuel rods would fail. However, to assure l that the limiting case is considered, it is assumed that all rods in the dropped assembly fail upon impact. The resulting doses calculated for j the fuel handling accident are below the NRC acceptance limit for this l accident, which is 10% of 10 CFR Part 100 limits. l (continued) i Maine Yankee B 3.1-1 Amendment 464,162 l J

.( -

t 1

T .

Fuel Storage Pool Water Level

! I l:

B 3.1.1 .

I BASES ,

APPLICABLE The normal operating water level of the fuei storage pool is  ;

SAFETY ANALYSES established at approximately 36.5 (44 foot elevation) feet above the '

l (continued) - floor of the pool. The Technical Specification value of 21 feet over the l top of irradiated fuel assemblies seated in the storage racks is equivalent to 34.7 feet of water above the fuel storage pool floor (42.2 I foot elevation).- The top of the fuel assembly is defined as the bottom l of the flow plate, which is the top of the fuel rods. In the case of a fuel  !

assembly dropped to the bottom of the fuel storage pool and standing i

, upright, the Technical Specification Water Level provides more than 19 l ,

feet of water for iodine decontamination. In the case of a fuel assembly l l dropped and lying horizontally on top of the spent fuel racks, the l J Technical Specification Water Level provides more than 19 feet of l !

- water above the top of the bundle. l t A red.uction in margin of safety for the fuel handling accident occurs l l when the acceptance limit (10% of 10 CFR Part 100 limits) is no longer i  !

met. The margin that exists between the technical specification limit for I ;

the fuel storage pool water level and the fuel handling accident l t acceptance limit represents operating margin. l Radiological shielding analysis has determined that five-and-one-half l feet of water above the top of a fuel assembly (bottom of the flow plate) l raised to its maximum height maintains the radiation dose rates less l than 80 mrem /hr at the surface of the water and less than 50 mrem /hr l at the fuel handling hoist platform or the walkway around tne pool. l Five-and-one-half feet of water above the top of a fuel assembly l (bottom of the flow plate) raised to its maximum height corresponds to l an elevation of 42.0 feet (34.5 feet above the floor of the fuel storage l pool.) l l

A reduction in margin of safety for the radiological shielding analysis j occurs when the acceptance limit is no longer met. The acceptance i ,

limit is defined as that combination of occupancy time and dose rate l )

such that no station personnel receive ir. excess of 5 rem per year (10 l  !

CFR 20.1201). l (Continued) 1 i Maine Yankee B 3.1-2 Amendment 464,162 l l

l

Fuel Storage Pool Water Level B 3.1.1 BASES LCO The fuel storage pool water level is required to be > 21 ft. over the top l of irradiated fuel assemblies seated in the storage racks. -The specified water level preserves the assumptions of the fuel handling accident analysis and provides shielding to minimize the general area dose when irradiated fuel is being moved. As such, it is the minimum level required for movement of irradiated fuel within the fuel storage pool.

APPLICABILITY This LCO applies whenever irradiated fuel assemblies are being moved in the spent fuel pool, since the potential for a release of fission products exists and increased water level shielding is needed.

ACTIONS A1.

When the initial conditions for an accident cannot be met, steps should be taken to preclude the accident from occurring. When the spent fuel pool water level is lower than the required level, the movement of irradiated fuel assemblies in the spent fuel pool is immediately suspended. This effectively precludes a spent fuel handling accident from occurring. Tnis does not preclude movement of a fuel assembly to a safe position.

SURVEILLANCE SR 3.1.1.1 REQUIREMENTS This SR verifies sufficient fuel storage pool water is available in the event of a fuel handling accident and to provide shielding to minimize the general area dose during the movement ofirradiated fuel. The water level in the spent fuel pool must be checked periodically when moving fuel. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency is appropriate because the volume in the pool is normally stable. Water level changes are controlled by facility procedures and are acceptable, based on operating experience l

l l

l Maine Yankee B 3.1-3 Amendment 464,162