ML20148J319

Amend 39 to License DPR-3,modifying 761229 Amend 33 to Tech Specs Re Expansion of Storage Capacity for Spent Fuel Storage Pool

ML20148J319
Person / Time
Site:	Yankee Rowe
Issue date:	06/03/1977
From:	Schwencer A Office of Nuclear Reactor Regulation
To:
Shared Package
ML20148J306	List: ML20148J301 ML20148J319 ML20148J333 ML20148J344
References
NUDOCS 8011210683
Download: ML20148J319 (6)

Text

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• NUCLEAR REGULATORY COMMisslON g .".. . g-WASHINGTON, D. C. 20335

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YANKEE ATOMIC ELECTRIC COMPAljV_

DOCKET NO.50-29_

YANKEE NUCLEAR POWER STATION (YANKEE-ROWE) f

' AMENDMENT TO FACILITY OPERATING LIC'NSE Amendment No. 39 License No. DPR-3 1.- The Nuclear Regulatory Commission- (the Commission) has found that:

A. The applications for amendment by Yankee Atomic Electric. Company  ;

'(the licensee) dated March 2, and May 20, 1977, comply with the  !

standards and requirements of the Atomic Energy Act of 1954, as- amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the applications, the provisions of the Act, and the rules and regulations of l 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 Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health aid safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission'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 acendment, and paragraph 2.C.(2) of Facility Operating License No.

DPR-3 is hereby amended to read as ,follows:

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"(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 39 , are hereby incorporated -

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 issuance.

FOR THE NUCLEAR REGULATORY COMMISSION y77 n- e.+

/4 A. Schwencer, Chief 6 Operating Reactors Branch #1 Division of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance: June 3,1977 O

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• ATTACHMENT TO LICENSE AMENDMENT NO. 39 FACILITY LICENSE NO. DPR-3 DOCKET N0. 50-29 Revise Appendix A as follows:

Replace pages 5-4, 3/4 9-8 and B3/4 9-2 with revised identically '

numbered pages.

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I DESIGN FEATURES CONTP.0L ROD 5.3.2 The reactor core shall contain 24 control rods. At least twenty- ,

j two control rods shall contain a nominal 90 inches of absorber material.

The nominal values of this absorber material shall be 80 percent silver, '

15 percent indium and 5 percent cadmium. Up to two control rods may have four 90" blades of Hufnium as the absorber. All control rods shall be clad with stainless steel. .

5.4 MAlu COOLANT SYSTEM j DESIGN PRE.SSURE AND TEMPERATURE I

5.4.1 The Main Coolcnt System is designed and shall be maintained:

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a. In accordance with the code requircments specified in ASME Boiler and Pressure Vessel Code,Section VIII, including c11 addenda through 1955, ar.d the ANSI (formerly AST) Standards, i Power Piping Code, B3'.1, 1955 Edition, and E15.5, 1957 Edi Mon, with allowance fer normal degradation pursutnt to the applictble Surveillance Requirements,

b. For a pressure of 20C3 psig, and

c. For a temperature of 650*F, except for the pressurizer which is 668'F.

VOLUME 5.4.2 The total water ind.stetm volum2 of th: Main Cooltnt System is 2940 cubic feet. .

5.5 METEOROLOGICI.L TO'..'ER LOCATION 5.5.1 The meteorological tower shall be located as shown in Figure 5.1-1.

_5. 6 FUEL STORAGE 7

CDITI Cf.L ii't 5.6.1 The new and spent fuel storage r:cks are designed and shall be maintained with a cenier-to-center distance betweer. fuel assemblies piaced in tho storace racks to ensure a t ca equivalent to <0.95 with The j the new or spent fuel storage areas flood!d'withc.unborated Eater.

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1 I Y!',N::EE DG'..'E 5-4 Amendment No. 39

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REFUELIUS OPERATIONS BASES 3/4.9.6 SHIELD TAM;'. CAVITY 4tMIpULATOR CPANE OPERADILITY The OPERASILITV requirements for the manipulator cranes ensure that:

1) the manipulator crane and universal handling tool will be used for movement of control rods and fuel assenblias, 2) each crane and tool has sufficient load capacity to lift a control rod or fuel 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 reler e 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 spent fuel pit building roof hatches for infrequent transfers of spent fuel racks by. administrative control will assure safe handling of the roof hat:hes. The restriction of novement of the spent fuel storage racks and spent fuel inspection stand over spent fuel ensures' that a rack or stand cannot be dropped on socnt fuel. Dropping of a rack or stand from a

. maximum height will not result in loss of integrity of the fuel pit floor, l Handling of the fuel hanJ1ing equipment for infrequent naintenance by adninistrative control will ensure the safe handling of any fuel handling components. Handling of fuel casks over the spent fuel pit is not permitted until such time as MRC has reviewed and approved the spent fuel cask drop

- evaluation.

3/4.9.8 C00LAli CIRCULATION The requirsment that the Shutdown Cooling System be in operation is consistent with the assumptions in the analysis of the baron dilution accident and prevents local variations in boron concentrations, thus minimizing the effects of an inadvertent boron dilution. It also assures that sufficient cooling capacity is available to remove decgy heat and maintain the water in the reactor pressure vessel below 140 F as required during the REFUELIMG MODE.

3/4.9.9 COMTAIM"E]T PURGE FAN SHUTDOWN SYSTE.'1  ;

The OPERASILITY of this system ensures that the containment purge fan  :

can be shutdown uoon detection of high radiation levels within the contain- l

. ment. The OPERABILITY of this system is required to restrict the release 1 of radioactive caterial fron the containmant atnosphere to the environment. l l

YAMKEE-RONE B 3/4 9-2 Amendment No. 39 i

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REFUELING OPERATIONS s 1 CRANE TRAVEL: - SPENT FUEL P_I_T_

1 LIMITING CONDITION-FOR OPERATION  !

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

a. ' Spent fuel pit building roof hatches,

b. Spent 1 fuel inspection' stand, I

c. Fue1' handling equipment, and .l

d. Spent ' fuel racks. i APPLICABILITY: With fuel assemblies in the spent fuel pit.-

ACTION:

With the requirements of the above specification not satisfied, place the crane load in a safe condition. The provisions of Specification 3.0.3'are not .

applicable.

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SURVEILLANCE REQUIREMENTS 4.9.7 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 pit building roof hatches, the spent fuel inspection stand, the fuel handling equipment and the spent ' fuel racks, may travel over the spent fuel pit in accordance with approved written procedures, '

b. Spent fuel storage racks and the spent fuel inspection stand shall be prevented from traveling over fual assemblies in the si ant fuel pit by administrative control, and

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

YANKEE-ROWE 3/4 9-8 Amendment No. 39 l

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