ML20151G087

Amend 102 to License DPR-61,revising Tech Spec Figures 3.17-1A & B & Section 3.17,2 to Reduce LHGR by Approx 1KW/ft W/Corresponding Reduction in Axial Offset Limits for Four Loop Operation

ML20151G087
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	04/08/1988
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20151G070	List: ML20151G068 ML20151G087 ML20151G094
References
NUDOCS 8804190214
Download: ML20151G087 (6)

Text

-

t

'c

• oq'o UNITED STATES

, '!#[.oS g n NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

. ( .

%,...../

CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213 HADDAM NECK PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.102 License No. OPR-61

1. The Nuclear Regulatory Comission (the Comission) has found that:

A. The application for amendment by Connecticut Yankee Atomic Power (the licensee), dated April 5, 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 (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; D. The issuance of this amendment will not 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 of the Comission's regulations and all applicable requirements have been satisfied, t

8804190214 880408 PDR ADOCK 05000213 p PDR

i a ~  :

,. l 2

i l

2. Accordingly, the license is amended by changes to the Technical ,

l Specifications as indicated in the attachment to this license amendment.

and paragraph 2.C.(2) of Facility Operating License No OPR-61 is hereby i arended to read as follows:

1

(?) Tect.,nical Spe,cifications  ;

The Technical Specifications contained in Appendix A, as revised through Amendment No.102, are hereby incorporated in the license.

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

I

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

FOR THE NUCLEAR REGUL TORY COPPISSION

(,M '

JohnjF. Stolf, Director Mect Directorate I-Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Attachrent:

Changes to the Technical Specifications Date of Issuance: April 8, 1988 I

4 l

ATTACHMENT TO LICENSE AMENDMENT NO.102 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-213 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendnent nur,ber and contain vertical lines indicating the areas of change.

Renove Insert-3-31A 3-31A

• Figure 3.17-1A Figure 3.17-1A ~

Figure 3.17-1B Figure 3.17-1B I

a 4

1 J

. ,- . POWER DISTRIBUTION LIMITS 3.17.2 LINEAR HEAT GENERATION RATE FOUR LOOPS OPERATING LIMITING CONDITION FOR OPERATION 3 .1,7 . 2 .1 All LINEAR HEAT GENERATION RATES (LHGRs) shall not exceed the following kilowatt per foot limits for cycle residency time:

a. Less than 125 EFPD 13.3 kW/ft

b. 125 To 250 EFPD ,13.3 kW/ft

c. Greater Than 250 EFPD But Less Than END OF CORE LIFE 14.6 kW/ft .

APPLICABILITY: MODE 1, above 40% of RATED THERMAL POWER.

ACTION: With the LHGR of any fuel rod exceeding the limits specified above.

initiate corrective action within 15 minutes and continue corrective action so that the LHGR is within the limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 40% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE REQUIREMENTS

1. LHGR's shall be determined to be within the above limits by a core power distribution measurement using the Moveable Intere Detector System and in consideration of the factors listed in 2 below:

a. At least once per 31 EFPD, d

b. Prior to THERMAL POWER exceeding 80% of RATED THERMAL POWER after each fuel loading, and

c. After reaching 100% of RATED THERHAL POWER and achieving  ;

equilibrium xenon conditions after each refueling.

3 31a Amendment No, 23, 7p, AB, 102

FIGURE 3.17-1A POWER LEVEL VS, AxlRL OFFSET LIMITS.

0-250 EFPD, FOUR LOOP OPERATION 120 t .

(-13,100) (8,100) -

100 I .

I 60 _'__ ,

m ,

(.30,70) (20,70)

N

' I d 60  !  !

t  !

a  !

E l I 40 =

(. 3 0 ,. 0 ) - (20,40) 20 - _

O I '

-40 -20 0 20 40 RXlRL OFFSET 1 */ i Amendment No. 97,102

L FIGURE 3.17.1B POWER LEVEL VS. RXIAL OFFSET Limits, 250 EFPD-EOL, FOUR LOOP OPERATION 120

(-15,100) .

(10,100) 3,g 8

i 80 l

z e i . i g

(-30,70) (20,70) x_

I d so _

a I

e I y  !

~

E l .

40 (-30,40) (20,40) 20 0 l

-40 -20 0 20 40 RXIAL OFFSET (%)

Amendment No. 97,]02

.-, . _ _ _ - _