ML20151K369

Amend 113 to License DPR-3,revising Tech Specs to Permit Loads Greater than 900 Lbs to Travel Over Plant Fuel Pit to Enable Removal of Control Rods from Spent Fuel Pit

ML20151K369
Person / Time
Site:	Yankee Rowe
Issue date:	07/25/1988
From:	Wessman R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20151K367	List: ML20151K360 ML20151K369 ML20151K380
References
NUDOCS 8808030171
Download: ML20151K369 (6)

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YANKEE ATOMIC ELECTRIC COMPANY vANKEE NUCLEAR POWER STATION 00CKET !!0.50-029 AMEN 0 MENT TO FACILITY CPERATING LICENSE Amendment No.113 License No. OPR-3

1. The Nuclear Regulatory Comission (the Commission) has found that:

A. The application for amendment by Yankee Atomic Electric Company (the licensee) dated January 15, 1988, March 31, 1988'and Pay 19, 1988 complies with the standards and requirements of the

. Atomic Energy Act of 1954, as amended (the Act), and the Cemission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety o# the public; and E. The issuance of this emendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements beve been satisfied.

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

m 8808030171 000725 9 DR ADOCK 0500

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-2 (2) Techr;ical Specifications The Technical Speci'ications contained in Appendix A as

. revised through Amendment No. 113, are hereby incorpnrated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuarce.

F0P THE NUCLEAR PEGIILATORY C0f! MISSION Ri' chard P. Wessman, Director Project Directorate I-0 Division of Reactor Projects I/II

Attachment:

Changes to the Technical Specifications Date of Issuance: July 25, 1988 e

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ATTACl!!/FNT TO LICENSE AMENDMENT NO.113 FACILITY OPEPATING LICENSE NO. DPR-3 DOCKET NO.50-029 Revise Appendix A Technical Specifications by removing the page identified below and inserting the enclosed page. The revised page is identified by the captioned amendment number and contains marginal lines irdicating the area of change.

REMOVE INSERT 3/4 9-8 3/4 9-8 3/4 9-Ca 3/4 9-8a B3/4 9-2 B3/4 9-2 O

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• REFUELENG' OPERATIONS bRANETRAVEL-SPENTFUELPIT LIMITING CONDITION FOR OPERATION 4

3.9.7 Loads in excess of 900 pounds shall be prohibit'ed from travel over the spent fuel pit except for the:

a. Spent Fuel Pit Building roof hatches,

b. Spent fuel inspection stand,

, c.. Fuel handling equipment,

d. Spent fuel racks,

e. Temporary gate,

f. Shielding panels,

g. Shipping cask liners,

h. . Volume reduction equipment,

1. - Shipping casks: 35 tons maximum gross weight - not for spent fuel, and J. Spent fuel assembly nondestructive test equipment.

APPLICABILITY: With fuel assemblies in the spent fuel pit.

I ACTION With the requirements of the above specifications not satisfied, place the crane load in a safe condition. The provisions of Specification 3.0.3 are not applicable.

SURVEILLARCE REQUIREMENTS 4.9.7.1 Loads in e,: cess of 900 pounds shall be prevented f rom traveling over the spent fuel pit by administrative control, except that the:

a. Spent Fuel Pit Building hatches, the spent fuel inspection stand, the fuel

' handling equipment, spent fuel racks, the temporary gate, the shielding .

panels, the spent fuel assembly r.c9 destructive test equipment, the volume reduction equipment, the shipping' cask liners, and the shipping casks (35 tons maximum gross weight - not for spent fuel) may travel over the spent fuel pit in accordance with approved written procedures,

b. The spent fuel inspection stand, the temporary gate, the shielding panels, the spent fuel assembly nondestructive test equipment, and the cask hatch cover shall be prevented from traveling over fuel assemblies in the spent fuel pit by administrative control. The volume reduction equipment, the shipping cask liners, and the shipping casks shall be prevent,ed from traveling over fuel assemblies in the spent fuel pit by administrative control and by the steel' framing at the southern edge of the SFP superstructure roof opening which is also at the southern end of the safe load path; 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 9-8 Amendment 39, 31, 37, 73, 93, 113 f

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.itEFUELING OPdRATIONS SPENT FUEL PIT ,

SURVEILLANCE REQUIREMENTS 4.9.7.2 Spent fuel pit building hatches (excluding the cask hatch cover), the temporary gate, the shielding panels, the shipping cask liners, the volume .

reduction equipment, the shipping casks, and the spent fuel assembly nondestructive. test equipment shall not be permitted to be moved over the spent, fuel pit unlecs:

(a) With newly discharged spent fuel stored in the lower racks, all spent fuel in the spent fuel pit has decayed for at least 45 days for 76 Newly Discharged Spent Fuel Assemblies (NDSFA), 37 days for 40 NDSFA, and 36 for 36 NDSFA, or (b) With newly discharged spent fuel stored in the upper racks, all spent fuel in the spent fuel pit has decayed for at least 60 days for 76 Newly Discharged Spent Fuel Assemblies (NDSFA), 45 days for 40 NDSFA, and 43 days for 36 NDSFA. ~

YANKEE R0WE 3/4 9-8a Amendment No. 93,113

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REFUELING OPERATIONS BASES 3/4.9.6 SHIELD TANK CAVITY MANIPULATOR CRANE OPERABILITY The OPERABILITY requirements for the manipulator cranes ensure .that: 1) the manipulator crane and universal handling tool will be used for movement of control 4 rods and fuel assemblies, 2) each crane and tool has sufficient load capacity to

.lif t a control rod or f uel assembly, and 3) the core internals and pressure vessel are protected from excessive lifting. force in the event.they are inadvertently engaged ~during lifting operations.

3/4.9.7' CRANE TRAVEL - SPENT FUEL PIT 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 will be limited to that contained in a single fuel assembly, and (2) any possible distortion of the fuel-in the storage tanks will not result in a critical array. This assumption is consistent with the activity release assumed in the accident analysis.

Handling of the present fuel pit building roof hatches for inf requent transfers of spent fuel racks by administrative control will assure safe handling of the roof hatches. The restriction of movement of the spent fuel inspection stand, the temporary gate,.the shielding panels, the spent fuel assembly nondestructive test equipment, the cask hatch cover, the volume reduction equipment,-the shipping cask liners, and the shipping casks over spent fuel ensures that these items cannot be dropped on spent fuel. Dropping any one of these items from its maximum height will not result in loss of integrity of the fuel pool floor. Handling of the fuel handling equipment for infrequent maintenance by edministrative control will ensure the safe handling of any fuel handling components.

3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirement that at least one residual heat removal (RHR) loop be in operation ensures that (1) suf ficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 1400F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effect of a boron dilution incident and prevent boron stratification.

The requirement to have two RHR loops OPERABLE when there is less than 32 feet of water above the core ensures tha.t a single failure of the operating RHR loop will not result in a complete loss of' residual heat removal capability. With the reactor vessel head removed and 32 feet of water above the core a large heat sink is available for core cooling. Thus, in the event of a failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the _

core.

i YANKEE-ROWE B 3/4 9-2 Amendment No. 39, 64 113 m'- .