ML20148H207

Amend 31 to License DPR-3,revising Rod Ejection Accident Analysis in Core 13 Performance Analysis

ML20148H207
Person / Time
Site:	Yankee Rowe
Issue date:	11/23/1976
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20148H200	List: ML20148H195 ML20148H207 ML20148H220 ML20148H225
References
NUDOCS 8011170401
Download: ML20148H207 (5)

Text

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,i- UNITED STATES s

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

[5 a ;f i k.....,/ j[$i YANKEE ATOMIC ELECTRIC COMPANY f .*

DOCKET NO. 50-29 g i

YANKEE NUCLEAR POWER STATION (YANKEE-ROWE)

AMEN 0 MENT TO FACILITY OPERATING LICENSE f

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' Anundment No. 31 l License No. DPR-3 h' The Nuclear Regulatory Comission (the Commission) has found that:

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A. The application for amendment by Yankee Atomic Electric Company (the licensee) dated August 17, 1976, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (e d (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; {

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B. The facility will operate in conformity with the application, rik the provisions of the Act, and the rules and regulations of g the Comission; y 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; W D. The issuance of this amendment will not be inimical to the comon i defense and security or to the health and safety of the public; #

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E. The issuance of this amendment is in accordance with 10 CFR Part i 51 of the Comission's regulations and all applicable requirements F, have been satisfied. 1

2. Accordingly, the license is amended by changes to the Technical ic; Specifications as . indicated in the attachment to this license amendment.

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1 l ATTACHMENT TO LICENSE AMENDMENT N0.31- s 6

FACILITY LICENSE NO. DPR-3 p g-j(

DOCKET NO.50-29_ G,

[ l, y 1r 74 A. Revise Appendix A of current Technical Specifications as follows: I 9#

Remove page 2 and insert revised page 2.

M Revise Appendix A of Standard Technical Specifications issued with B.

Amendment No. 27 (Effective January 1977) as follows: gl Replace pages 3/4 1-23 and 3/4 1-24 with revised pages 3/4 1-23 and 3/4 1-24 (no change has been made on page 3/4 1-24).  %!.

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214 , Nuclear Instrumnntation Systecs 215 Radiation Monitoring System  %

218 Fuel Handling System Ql 224 Compressed Air Systems 3j 231 Vapor Containment .j 232 Radiation Shiciding , 3

• 235 Architectural Features 1 Physical arrangements of structures and equipment will be as M described in Section 200 of the license application. Mechanical equipr.icnt and systems vill bc interconnected as shown in the L-Fundamental Flow Diagram included in that section. #

h Electrical equip =cnt and systems which provide station auxiliary f:

power supply vill be as described in Section 226 of the license Q ~

application and will be interconnected as shown in the 2400 volt h g

one-lino diagram and the 480 volt one-lino diagram, sheets 1, 2 and 3, included in that section.- 3 k

The ventilation vstem for the control room arca, radiochemical k laboratory, de amination cubic 1c, fuel transfer pit house, and g other potential, / contaminated portions of the Turbine Cencrator kg Service, Primary Auxiliary, and Waste disposal Buildings shall be in accordance with the description contained in Section 228 of k Part 3 of the license application.

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3. The Performanes nnalysis for the current reload core, " Yankee Nuclear f Power Station Core XII Perf ormance Analysis, July 9,1975" (as supple- 4 mented October 10, 1975, February 19, 1976, and August 17, 1976), and y the " Additional LOCA Analysis - Appendix B" dated February 20, 1976, '

W are insorporated as part of these technical specifications. The ,,

analysis presented in the FSAR for Core XI forms the basis for the , ,

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reference core performance analysis.

C. PERTORMAN'CE SPECIFICATIONS Calculated values of operating variables such as pressures, temperatures, flows, heat fluxet, reactivity coefficients and on-site radiation icvels under steady state and transient conditions which are stated in the sections '

of the license application listed in Paragraph B, above, are considered to be performance specifications of the reactor and are incorporat.1 by reference herein. Yankee shall not operate the f acility under circumstances- {f vhere there is a substantial variance between the foregoing performance  ;,

specifications and the corresponding values determined by operation of the  ;

facility.

• described in the following (g The performance and function of the syste:_2 p r,cetions of the license application shall be substantially as described; heuever, the details of individual components and their arrangement as 3 described in cach of these secticas may be altered by Yankee at its own discretion previded tha: such an alteration would not violate some other -)

provision of these Technical Specification's:

Amendment No. 3f>/31

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REACTIVITY CONTROL SYSTEMS 1.y 3/4.1.3 MOVACLE CONTROL RODS );

5 CONTROL RCD OPERAGILITY 1

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lit'.!TI.':G CC"D:T!OM FOR OPERATIO.'l ,,

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3.1.3.1 All control rods which are inserted in the core shall be OPERABLE 3 and positioned within + 8 inches (indicated position) of every other rod in

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their group.

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4,o APPLICASILITY: MDDES 1* and 2* ,y

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l "l a. With one or more control rods inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippabic, determine that the SHUTDOWN !%RGIN g@j requirement of Specification 3.1.1.1 is satisfied within 1 m hour and be in HOT STA :DBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.  !.

With more than one control rod inoperabie or misaligned from 9@E Lu b.

any other rod in its group by more than + 8 inches (indicated position), be in HOT STA';CSY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

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c. With one control rod inoperable or misaligned from any other 9 rod in its grcup by more than + 8 inches (indicated position), i W

POWER OPERATION may continue provided that within one hour cither: j h it

1. The rod is restored to OPERABLE status within the above "i alignment requirements, or a

2. The rod is declared inoperable and the SHUTDOWN MARGill );

requirement of Specification 3.1.1.1 is satisfied. PUWER $

OPEPJtTION may then continue provided that: Q 93 a) An analysis ocT the potential ejected rod worth  ??p is performed within 3 days and the rod worth is ph determined to be < 0.75'4 tik at zero power and 3

< 0.5% t.k at RATED Til R ML POWER for the F remainder of the fuel cycle, and

@o TScc Specia f ict,t Exceptions 3.10.2 and 3.10.4. p? '

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YAfiMEE-RO'.:C 3/4 1-23 Amendment flo. 31 1

. REACTIVITY CO: 1. SYSTEMS O

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's LI!!!TIf G C0!t01 TION FOR OPERATION (Continued) h

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F 's The SHlJTDOWN'MARGill requirement of Specification

. 3.111.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, T and ,

. yK c) A power distribution map is obtained from the ti

.rnovable incore detectors and F and F' are se verifiedtobewithintheirlibitswi$Ilin 9l 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

k j#;p d) The THEPJ1AL POWER level is reduced to < 75% of .

THERi%L POWER allowable for the Main Cliolant TF pump combination within one hour and within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the Power Range and Intermediate h(p Power Range lieutror. Flux high trip setpoint is reduced to < 103% of the 75% of allovable

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' THERMAL,POWfR,or ,

ny e) The remainder of the rods in the group with the j,is inoperabic rod are aligned to within + 8 inches of the inoperable rod within one hour'while rnaintaining the rod sequence and insertion f@

$y limits of Figures 3.1-1 and 3.1-2; the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.5 during subsequent operation. T@

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. N S'EVEILLANCE REOUIREMENTS j34g%

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4.1.3.1.1 The position of each control rod shall be determined to be &

within the limit by verifying the individual rod positions at least once y per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. ,

• Q 4 .1. 3.1. 2 Each control rod not fully inserted shall'be determined to be h; 0?ERABLE by movement of at least 4 inches in any one direction at least  ;%

or.ce per 31 days. ,

4 .1. 3.1. 3 The maximum reactivity insertion rate due to withdrawal of the highest worth control rod group shall be determined not to exceed I,y 1.5 x 10 ' ok/k per second at least once per 18 months.

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Y/,NKEE-ROWC 3/4 1-24 Amendment No. 31 a

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