ML20204G464

Amend 118 to License DPR-3,revising Tech Specs Re Specific Values of Boron Concentration

ML20204G464
Person / Time
Site:	Yankee Rowe
Issue date:	10/17/1988
From:	Wessman R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20204G458	List: ML20204G455 ML20204G464 ML20204G487
References
NUDOCS 8810240129
Download: ML20204G464 (6)

Text

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c e NUCLEAR REGULATORY COMMISSION .

WASHING TON, D. C. W6M l

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YANKEEATOMICELECTRICC0dPANY.

YANKEENUCLEARPOWERSTATipJt .

q DSCLET NO.50-029

, AMENDHENT TO FACILITY OPERATING LICENSE l 1

Amendment No.118 <i License No. DPH-3 i

1. The Nuclear Regulatory Comission (the Comiss'en) hus found that:

A. TheapplicationforamendmentbyYankeeA.odicElectricCompany s (the licensee) dated August 11, 1988 cor. plies with the standards l and requirements of the Atomic Energy Act of 1954, as a m nded I (the Act), and the Comission's rules and rcgulations set forth l in 10 CFR Chapter I; i c 7te facility will operate in conformity with the appl! cation,  !

the provisions of the Act, and the rules and regulations of the Comission; i l

C. There 1: 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 bri .

conducted in compliance with the Commission's regulations;  !

D. The issuance of this amendment will not be inimical to the connon  !

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 Comission's regulations and all applicable requiremnts have 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 Factitty Operating License No. OPR-3 is hereby amended to read as folicws: 3 1

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l SS10240129 881017 PDR ADUCK C5000029 P PDC

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. (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 113 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is offective as of the da+e of its issuance.

FOR THE NUCLEAR REGULATORY C0tullSS10N S

Richard H. essman, Director Project Directorate I-3 Division of Reactor Projects I/I!

Attachment:

Changes to the Technical Specifications Date of Issuance: October 17. 1988 l

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DATE : 10/ /88 : 10/LD /88 : 10/ /8R  : 10/n/88  :  :  :

OFFICIAL RECORC *0PY i

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(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 118 , are hereby incorporated in the license. The licensee shall operate the facility

., in accordance with the Technical Specifications. ,

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

FOR THE NUCLEAR REGULATORY COMMISSION f l

%4.w wr  !

Richard H. Wessman, Director

• r Project Directorate I-3 Division of Reactor Projects I/II '

Attachment:

Changes to the Technical I Specifications ,

i a Date of Issuance: October 17. 1988 L i

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, ATTACHMENT TO LICENSE AMENDHElli NO.118 FACILITY OPERATING LICENSE NO. DPR-3 DOCKET NO.50-029 Revise Apptndix A Technical Specifications by rer.oving the pages identified belew and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contains marginal lines indicating the area of change, REMOVE INSERT 3/4 9-1 3/4 9-1 3/4 9 2 3/4 9-2 i 4

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REFUELING OPERATIONS REACTIVITY LTMfTINC CONDITIOM FOR OPFRATION 3.9 1 With the reactor vessel head unbolted or removed, the boron ,

concentration of all filled portions of the Main Coolant System and the shield tank cavity shall be maintained uniform and suf ficient to ensure a k,gg of  ;

0.93 calculated or less. ,

i APPLICABILITY: MODE 6*

i ACTION:

a. With the boron concentration requirements of the above specification not satisfied, immediately suspend all operations involving CORE ,

1 ALTERATIONS or positive reactivity changes and initiate and continue t 1 boration at g 26 spm with a boron concentration sufficient to ensure (

It.gg is reduced to 1 0.93. ,

! b. With a significant unexpected increase in the count rate on any 2

channel, or an unexpected increase in the count rate by a factor of r' two after addition of a new fuel assembly or removal of a control

rod, suspend CORE ALTERATIONS until the situation is reviewed by l Plant technical supervisory personnel.

c. The provisions of Specification 3.0.3 are not applicable.

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• The reactor shall be maintained in MODE 6 when the reactor vessel head is j} unbolted or removed with fuel in the vessel. l 1 ,

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j YANKEE-ROW 7. 3/4 9-1 113 AmendmentNo./[

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l REFUELING OPERATIONS SURVETLLANCE RtoDIRFMENTS 4.9.1.1 The above required reactivity condition shall be determined:

a. Prior to removing or unbolting the reactor vessel head, and*

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b. Prior to withdrawal of any full-length control rod in excess of  !

3 feet from its fully inserted position.  !

l r 4.9.1.2 Equipment which would make possible inadvertent reactivity increases  ;

snail be made inoperable and tagged out of service.

i 4.9.1.3 The boron concentration of the Main Coolant System and the shield [

tank cavity shall be determined by chemical analysis at least 3 times per [

7 days with a maximum time interval between samples of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. i t

4.9.1.4 Before flooding the shield tank cavity with borated water, it shall  !

be determined that the boron concentration of the water in the safety i injection tank is not less than the required boron concentration of the Main  !

Coolant System as specified above. l t

4.9.1.5 A record will be made of the neutron count rate before and after any I change in core geometry. l l

• With all four main coolant loops isolated during reactor head removal, assure that all control rods are inserted. With a control rod withdrawn, borate to  !

compensate for the withdrawn rod. (

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l Amendment No.rj ( 113 YANKEE-ROWE 3/4 9-2 1 .

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