ML20148G389

Forwards Revision of App a to License DPR-3.Util 640211 Proposed Revised Pages for Tech Specs Accurately Incorporates Changes Authorized by Changes 30,36 & 50

ML20148G389
Person / Time
Site:	Yankee Rowe
Issue date:	03/04/1964
From:	Lowenstein R US ATOMIC ENERGY COMMISSION (AEC)
To:	Coe R YANKEE ATOMIC ELECTRIC CO.
References
NUDOCS 8011110601
Download: ML20148G389 (1)

Text

l

-+ . ,

Distribution Doc. Room E. J. McAlduff

.% F,ormal E. G. Case j Suppl. H. Shapar DIAR Re ading - L. Eornblith -2 REPRSB Reading P. Travelstead Originator E. E. Enll D. C. Clark Lockot to. 50-29 E. Trennel MAR 4 1334  !!. Steele

' 3. Pai;c R. Euard Yankee Atonic Flectric Company "

hhl Stuart Street 9 Poston 16, Massachusetts , .;

Attention: Mr. Roger J. Coe Vice President Gentlement In your letter of February 11,196L, you submitted proposed q~

revised pages for the Technical Specifications of License .

Ke. DPR-3 which incorporated changes authorised by Changes

• No. 30, 36, and 50, dated January 2h, September 23, and ~

December 2h,1963. We have reviewed the revised pages and agree that they accurately represent tha aforesaid chances in the Technical Specifications for the Tankee reactor. Accordingly, we are issuing the enclosed revision of /.ppendix A to License Uo. TP1-3.

Sincercly yours, Or!ginal signed -

ty R. Lc.untyn, Lirector- '

I/ivision of Licensing and Regulation

Enclosure:

As stated above THIS DOCUMENT CONTAINS POOR QUAUTY PAGES f

emn> WR ...... 03C / .DN,,,,, [Ld5 DIld suaumt , M3 o c1r_ R,p an EC a g,, ,, ,,[g, 9, g,({rM om+ . ...,lhlih....

. 6. . . .+ .../.3 d. 4.. .. ....L.7 T[. q/d, rurm ac.m m.om> ........................a i.-wei e

/

-8011110 f6/, . . .

. . . AppemTr A ,

• t:

. C '

7 L

2 e 3/s/6h k '. 1 ,

, s .

l a, '

YANKEE ATOMIC ELECTRIC C'OMPANY 1, _ , _ , , , _ , . .

Technical Specifications .;;

A. SITE , ,

q a

. The reactor shall be located on the property owned by Yankee in 'Rowoj .

Mass. The site includes the property owned by Iankee and New England

. Power Company as shown on the map on page 300:2 of the license appli- , ,, .,

2 oation. ..

g.

No part of the site shall be sold or leased.without the prior approval' ,

n of the Comad.ssion. .No structure shall be located on the site without r '

the prior approval of the CommLssion except structures owned by Yankee S or New Ebgland Power Company and used in their utility operation and except railroad facilities. owned and used by the Hoosso Tunnel and '

-i Wilmington Rai3 road Company..

s ,  ?,

. H B. DESIGN SPECIFICATIONS 13 ~ Tho .following sections of the license application 'aro considered"" . . ,

, .to be design specifications of the reactor and.,are incorporated '

~y herein in their entiretys , ,

), ,

101 Core Mechanical Design .

e 201 Main Coolant System , ' ,

j 202 ' Pressure Control and Relief System t.~

.I 203 Charging and Volume Contsol System

• 20k Chemical Shutdown System .:

+

210 Shutdown Cooling System j 212 Safety Injection System .c 230 Reactor Vessel j l

2. The prosaures and temperatures used as a basis for decign, i materials of construction, general arrangements of the systems d R

and their components', weights, volumes, dimensions and tolerances, methods of-fabrication and applicable codes, tes procedures which appear in the followingssection,ts of the license and inspection

. application (excluding drawings) are considered to be designs speci.fications of the reactor and are incorporated

~

by reference herein ,

. 102 Core Thermal and Hydraulio Design

- - 103 Core Nuoloar Design .;

106 Reactor Coolant Chord.stry -

I, 107 Core Instrumentation j 20$ Purification System 1 207 ~ Corrosion Control Sys+.on -- Prinary Plant

- 209 Radios.ctive 4tasto Dicpooc.1 System

• 213 Roactor Control Syster. l 21h Huelsex Instnucento.ticn Syrteu  ;

215 Radiction Ibnitoring Cysten 218 -Fuel Hend31nC Bysten P

y. e ,  ;

~3/li/6h i l:  ;,

~ a ' .

-22h: Compressed Air Systems H 231; Vapor Containment- .a 232 Radiation Shielding 'y " d 235 Architectural Features y

4 c  ?

j

. Physical arrangements 'of structures and equipment will be as .

described in'Section 200 of the' licence application. Mechanical 21 equipment 'and systems will be interconnected as shown in the ./

. . Fundamental Flow Diagram included in that section. ,

h Electrical equipment and systems which provide station anv414mry power supply will be as described in Section 226 of the license application and will be interconnected as shown in the 2h00 volt

' one-line diagram and the hBO volt one-line diagram, sheets 1, 2 -

.g

.and 3, included in that section. , <

r The ventilation system for the control room area, radiochend. cal ,

laboratory,; decontamination cubicle, fuel transfer pit house, and -

other potentially contaminated portions of the Turbine Generator, ,

Service, Primary Anv414=v, and Waste Disposal Bn41 dings shall be ==:9

-in accordance with the description contained in Section 228 of ,

Part B of the license application. ,

g

, C. PERFORMANCE SPECIFICATIONS .u

..e Calculated values of operating variables such as pressures, temper-

.atures, flows, heat fluxes, reactivity coefficients and on-site , ,

radiation levels under steady state and transient coniitions 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 ihcorporated by reference herein. Yankee shall not operate the facility under circunstances where there i's a substantial variance between the forogoing perforr.cnce specifications and the corresponding values determined by operation of the facility.

The performance and function of the systems described in the following a sections of the license application shall be substantially as described; however, the details of indiv1 dual components and their arrangenent he deed. bed in bach of these sections may be alterod by Yankee at its own discretion provided that such an alteration would not violate some other provision of these Technical Specifications:

n '

206 Component Cooling System 208 Sampling System 211 Vent and Drain System, Primary Plant Fq 2 16 Vapor Container Attoophero Control Systems 219 Vain and Aux 111t.ry Stoc.m Systen 220 Condensato end Feed Watcr System .

.. 221 Circulating Water System 222 Untm' Supply Spter.

q

. .. q l

r

,m .

,, 3 . .

L 3/4/9h  : '.2 ':

D.. OPE!iATIN3 PROCEDURES AND RESTRICTIONS

1. Operatinz Procedures The reactor will at all times be operated in accordance with i generally accepted standards of safe operating proceduregt subject to the operating restrictions set forth below.- All operations will be conductei in accordance with written procedures and under the direct and personal supervision'of technically qualified and gc.

designated personnel. -

The Objective, Conditions and Precautions set forth in the individual instructions contained in the following sections of the license application will be observed:

50h Normal Plant Operation Instructions 505 Emergency Instructions 506 Plant Maintenance Instructions

2. Operating Limits ,

a. Reactivity m:-

5 (1) During core loading the fuel assemblies, control rods and .

shim rods will be loaded one by one in water sufficiently borated to render the fully loaded core sub-critical at room temperature, by a calculated margin of at leact 7% 6 K/K.

(2) During the refueling operation a record will be made of the neutren count rate before and af ter any change in core geometry. If a significant unexpected increase in the count rate occurs on any ene channel or if an unexpected increase in the count rate by a factor of two on two of the three channels occurs after addition of a new fuel assembly or removal of a control rod, the fuel loading operation will be suspended until the situation can be reviewed by plant technical supervisory personnel. '

In order to establish the shutdown margin of the core, a single control rod will be withdrawn periodically using the manipulator crane and regulated by a plot of control rod position vs. inverse count rate multiplication.

Using the inverse count rate data obtained in this manner, the shutdown margin will be calculated. If these calcu-lations indicate that there will be less than 5% l 6 K/K shutdnwn with all control rods inserted in the fully loaded core, the boren concentration will be -

.nereased to provide the required 5% 6 K/K shutdown mrgin.

(3) At all times when the reactor is at operating temperature sufficient beric acid shall be present in the main coolant system so that full insertion of all control rods 1

l

_q

=.. ,

, , w 4fb;h m ,.

I

~g~ mik/. . .y V

1 shall render the reactor not less than h% 6 K/K sub-critical or, if the max > .v.im worth rod were with-drawn, not less than 2.0% 6 4./K sub-critical.

(b) Sufficient boric acid will be added to the main coolant system prior to cold shutdown to maintain the cold core with all control rods inserted at least 5% 6 K/K sub-critical. This will be done before the temperature l-of the main coolant system has been reduced to a point where full insertion of all control rods would no longer -*

l~ render the reactor. 2% 6 K/K sub-critical without the presence of boric acid.

.(5) The raximum reactivity insertion rate due either to withdrawal of the highest worth control rod group or to reduction of boric acid concentration in the main coolant system through dilution will not exceed 1.5 x 10-4 6 K/K per second.

~

b (6) Whenever the reactor is shut down, before any operation -

which might result in a change of reactivity,. a control 55 rod group shall be withdrawn to a height sufficient to provide a reactivity worth of 1% for emergency shutdown capability. If for any reason this is not  ;,:.=,,

the main coolant system shall be borated to ^

practical, provide 5% 6 K/K cold shutdown margin with all contr:,1 g' rods inserted. ...-g (7) The reactor will be scrammed automatically below 15 W electric by a high startup rate signal set at a maximum of 5.2 decades / minute.

(8) The Commission shall be immediately notified should an unexplained reactivity change greater than 0.8% 6 K/K take place at any time subsequent to the first week of .

full power operation. This reporting requirement shall be in effect only when the boron concentration in the primary system exceeds 80 ppm and within one week after

• a reduction to a boron concentration of less than ,

80 ppm.

b. Power Ievel (1) The steady state power level of the reactor will not exceed rated power of 600 W thermal.

(2) The reactor will be scrammed automatically by a high

'i j

neutron fluxaslevel rated power signal,(set defined at not more tt '.108% of in 1) above.

(3) Daring operation with one loop of the four main coolant i loops isolated from the system, the steady state thermal  !

pcwcr level of the reactor will not exceed h50 W thermal.

i- t