ML20195D665

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Amend 120 to License DPR-3,enabling Piping Mods Needed to Allow for Installation of Water Cleanup Sys
ML20195D665
Person / Time
Site: Yankee Rowe
Issue date: 11/01/1988
From: Wessman R
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20195D623 List:
References
NUDOCS 8811070095
Download: ML20195D665 (5)


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NUCLEAR REGULATORY COMMISSION wAswinatos, o. c. nosss

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YANKEE ATOMIC ELECTRIC COMPANY YANKEE NUCLEAR POWER STATION DOCKET NO.50-029 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 120 License No. OPR-3 .

1. The Nuclear Regulatory Comission (the Comission) has found that: l A. The application for amendment by Yar.kee Atomic Electric Company L (thelicensee)datedJune 27, 1988, complies 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 application, the provisions of the Act, and the rules and regulations of the Comission;

. C. There is reasonable assurance (1) 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; 5 D. The issuance of this amendment will rot be inimical to the comon 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 i of the Comission's regulations and all applicable requirements have been satisfied. p

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

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8811070095 881101 PDR ADOCK 05000029 P PDC  ;

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

in the license. The licensee shall operate the facility i in accordance with the Technical Specifications.

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3. This license amendment is effective when the Water Clean-Up System is declared operable.  !

FOR THE NUCLEAR REGULATORY'COMMISSI'ON

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Richard H. Wessman, Director >

Project Directorate I-3  !

Division of Reactor Projects I/II ,

Attachment:

Changes to the Technical Specifications Date of Issuance: November 1, ils  !

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ATTACHMENT TO LICENSE MiENDMENT NO.120 FACILITY OPERATING LICENSE NO. DPR-3 DOCKET NO.50-029 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change,

, REMOVE INSERT 3/4 5-4 3/4 5-4 3/4 6-12 3/4 6-12 I

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anRutItilNet trnUf RFMElfTS 4.5.2 Each gCCS safety injection subsystem, the recircula: ion subsystem, and the long-term hot leg injection subsystem shall be demonstrated OPERABLE:

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a. At least once per 31 days on a STAGGERED TEST BASIS by:
1. Verifying that each high pressure safety injection pumpt (a) Starts (unless already operating) from the control room.

(b) Develops a discharge pressure of 1850 pais on recirculation flow to the safety injection tank.

(c) Operates for at least 15 minutes.

2. Verifying that each low pressure safety injection pumpt (a) Starts (unless alttady operating) from the control room.

(b) Develops a discharge pressure of 1250 pais on recirculation flow through CS-MOV-532.

I (c) Operates for at least 15 minutes.

b. At least once per .11 days by:
1. Verifying that the following valves are in'the indicated positions with power to the valve, operators removed by opening at least two breakers in series:

Valve Number Valve Function Valve Position

a. CH-MOV-522 a. Charging Header /LPSI a. Closed Isolation
b. CE-MOV-524 b. Charging Header / Loop b. Open 4 Bot Les Injection Long-Tern Recirculation
c. WC-MOV-603 c. WCS/LJSI Isolation c. Closed
d. WC-MOV-605 d. WCS/LPSI Isolation d. Closed 1 e. WC-MOV-615 e. WCS/LJSI Isolation e. Closed

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YANKEE-ROWE 3/45-4 Amendment No. 35, 31, 77, 120 D

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TASLE 5.6-1 (coatinued)

CONTAINMENT SAJtRIERS TESTABLE DURING ISOLATION PLANT OPERATION TIME FUNCTION (Yes or No) (Seconds)

VALVE NUMBER VD-V-754(4) Neutros Shield Tank Test NA NA NA NA HC-V-602 Air Purge Bypass NA NA C A-V-7 5'a ( 6 ) VCPH Pressure Relief NA Containment Sump to Charging NA FU-V-651 NA NA VD-V-917 LPST S.V. Discharge Header

-l NA NA VD-V-1170 Spare Penetration .NA

?JA VD-V-It71 Spare Penetration B.2 MANUAL VALVES (N_ot,t Subject to Type C Testing)

C.1 CRECK VALVES (Not Subject to Type C Testing)

NA Safety Injection (HP) NA NA Safety Injection (LP) NA

$  !-V-14 CS-V-621 (13(13))

MC Teed to Loop 84 NA NA CN-V-611 C.2 CHECK VALVES (Subject to Type C Testing)

!!A NA WC-V-6 22 WCS Return Check Valve D.1 REMOTE MANUAL VALVES (Subject to Type C Testing)

No NA CC-W-205(5) Component Cooling Return NA No CC-TV-20a( 5 ) Component Cooling Inlet NA Yee EV-SOV-39 Hydrogen Monitoring NA Nydrogen Monitoring Yee IV-50V-42 No NA WC-MOV-619 WCS Return Line WCS Return Line No NA WC-MOV-618 D.2 REMOTE MANUAL VALVES (Not subject to Type C Testing)

No NA l SC-MOV-551/ Shutdewn Cooling In -

553 (1,2) .

No NA SC-MOV-552/ Shutdown Cooling Out 554 (1,1)

No NA CH-MOV-522(7) MC Teod-to-Loop Till Header No NA

$1-MOV-516 ECCS Recirculation No NA SI-MOV-517 ECCS Recirculation .

AmondmentNo.If,M.,d,120 YANKEE R0WE 3/4 6-12 t.