ML20079A937

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Proposed Tech Specs,Modifying Requirement to Perform Mtc Test Near End of Each Cycle
ML20079A937
Person / Time
Site: Waterford Entergy icon.png
Issue date: 12/09/1994
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20079A936 List:
References
NUDOCS 9501040196
Download: ML20079A937 (7)
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Text

NPF-38-161 ATTACHMENT A 95o1040196 941209 PDR ADOCK 05000382 P PDR

REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT 3 h,kh LIMITING CONDITION FOR OPERATION 3.1.1.3 The moderator temperature coefficient (MTC) shall be:

a. Less positive than 0.5 x 10 ~4 delta k/k/'F whenever THERMAL POWER  ;

is 5 70% RATED THERMAL POWER, and b.- Less positive than 0.0 x 10 ~4 delta k/k/ F whenever THERMAL POWER is > 70% RATED THERMAL POWER, and

c. Less negative than -3.3 x 10 ~4 delta k/k/*F at all levels of THERMAL POWER.

APPLICABILITY: MODES 1 (1) and 2*#

i ACTION:

With the moderator temperature coefficient outside any one of the above limits, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. ,

i SURVEILLANCE REQUIREMENTS 4.1.1.3.1 The MTC shall be determined to be within its limits by confirmatory measurements. MTC measured values shall be extrapolated and/or compensated to l permit direct comparison with the above limits.

i 4.1.1.3.2 The MTC shall be determined at the following frequencies and THERfc_  :

POWER conditions during each fuel cycle:

a. Prior to initial operation above 5% of RATED THERMAL POWER, after ,

each fuel loading.

b. At greater than 15% of RATED THERMAL POWER, prior to reaching 40 EFr l core burnup.
c. At any THERMAL POWER, within 7 EFPD of reaching two-thirds of 1 expected core burnup. )

i

  • With K,ff greater than or equal to 1.0.
  1. See Special Test Exception 3.10.2. I
  1. II)See Special Test Exception 3.10.2 applicable for Mode 1 during startup te- I of Cycle 2.

i WATERFORD - UNIT 3 3/4 1-4 AMENDMENT ' '5 l

l

3/4.1 REACTIVITY CONTROL SYSTEMS X' S7I l lG l

. BASES 3/4.~ 1.1 B0 RATION CONTROL i

3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN SHUTDOWN MARGIN is the amount by which the core is suberitical, or would l

i be subcritical immediately following a reactor trip, considering a single  ;

malfunction resulting in the highest worth CEA failing to insert. j i

The function of SHUTDOWN MARGIN is to ensure that the reactor remains subcritical following a design basis accident or anticipated operational l occurrence. During operation in MODES 1 and 2, with k,ff greater than or q

equal to 1.0, the transient insertion limits of Specification 3.1.3.6 ensure i that sufficient SHUTDOWN MARGIN is available, j-SHUTDOWN MARGIN requirements vary throughout the core life as a function of fuel depletion and reactor coolant system (RCS) cold leg temperature (Tcold)*

The ecrt restrictive condition occurs.at E0L, with (Tcold) at no-load operating i temperature, and is associated with a postulated steam line break accident and  !

the resulting uncontrolled RCS cooldown. In the analysis of this_ accident, the '

specified SHUTDOWN MARGIN is required to control the reactivity transient and -

ensure that the fuel performance and offsite dose criteria are satisfied. As '

(initial) Tcold decreases, the potential RCS cooldown and the resulting reactiv-ity transient are less. severe and, therefore, the required SHUTDOWN MARGIN also i decreases.

cold of about 200'F, the inadvertent deboration event becomes Below T j limiting with respect to the SHUTDOWN MARGIN requirements.. Below 200*F, the  !

specified SHUTDOWN MARGIN ensures that sufficient time for operator actions  ;

exists between the initial indication of the deboration and the total loss of 1 SHUTDOWN MARGIN. Accordingly, the SHUTDOWN MARGIN requirements are based upcn  :

these limiting conditions.

Additional events considered in establishing requirements on SHUTDOWN MAR-GIN are single CEA withdrawal and startup of an inactive reactor coolant pu ;.

Other technical specifications that reference the Specifications on SHUT-DOWN MARGIN are: 3/4.1.2, BORATION SYSTEMS, 3/4.1.3, MOVABLE CONTROL ASSEMELIE5, )

3/4.9.1, REFUELING OPERATIONS - BORON CONCENTRATION, and 3/4.10.1, SHUTDOWN I MARGIN.

3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT l 1

The limitations on moderator temperature coefficient (MTC) are provided to ensure that the assumptions used in the accident and transient analysis )

remain valid through each fuel cycle. The Surveillance Requirements for  ;

measurement of the MTC during each fuel cycle are adequate to confirm the MIC value since this coefficient changes slowly due principally to the reduction i in RCS boron concentration associated with fuel burnup. 'The confirmation tat i the measured MTC value is within its limit provides assurances that the cce*-

ficient will be maintained within acceptable values throughout each fuel c e.

WATERFORD - UNIT 3 B 3/4 1-1 AMENDMENT NO -

l l

d l

l 1

NPF-38-161 ATTACHMENT B 4

n, - . . . __ - - .

i' .

i REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATlJRE COEFFICIENT

)

LIMITING CONDITION FOR OPERATION 3.1.1.3 The moderator temnerature coefficient (MTC) shall be:

I

a. Less positive than 0.5 x 10-4 delta k/k/*F whenever THERMAL POWER is s70%  !

RATED THERMAL POWER. and ,

b. Less positive than 0.0 x 10-4 delta k/k/*F whenever THERMAL POWER is >70%

RATED THERMAL POWER, and  !

c. Less negative than -3.3 x 10-4 delta k/k/*F at all levels of THERMAL 5

POWER.

APPLICABILITY: MODES IM and 2*# l  ;

, ACTION:  ;

With the moderator temperature coefficient outside any one of the above limits, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

l SURVEILLANCE REQUIREMENTS ~~

i 4.1.1.3.1 The MTC shall be determined to be within its limits by confirmatory measurements.

MTC measured values shall be extrapolated and/or comffnsated.to permit direct comparison -[

with the above limits.  !

4.1.1.3.2 The MTC shall be determined at the following frequencies-and THERMAL POWER conditions during each fuel cycle:

l

a. Prior to initial operation above 5% of RATED THERMAL POWER. after each fuel  !

loading.

b. At greater than 15% of RATED THERMAL POWER. prior to reaching 40 EFPD core  !

burnup.

{

c. At any THERMAL POWER. within 7 EFPD of reaching two-thirds of expected core burnup.

The MTC determination of paragraph 4.1.1.3.P.c is not required if the i results of the tests required in surveillance 4.1.1.3.2.a and 4.1.1.3.2.b are ,

9 thin a tolerance of i0.36X10*.S delta k/k/*F from the corresponding design v419 e1 "With Keff greater than or equal to 1.0.

ee Special Test Exception 3.10.2. I gU S= Sp~:4al-tea 3;xqtf= 3.%2-app 14ctle for "~t 1 M ; starte-test-ef Cg4e-3r )

I WATERFORD - UNIT 3 3/4 1-4 l 1

[

. 3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 BORAT10N CONTROL 3  ;

3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN SHUTDOWN MARGIN is the amount by which the core is subtritical, or would be subcritical immediately following a reactor trip considering a single malfunction resulting in the highest worth CEA failing e.o insert.

The function of SHUTDOWN MARGIN is to ensure that the reactor remains subtritical following a design basis accident or anticipated operational occurrence. During operation in MODE 5 I and 2. with Keff greater than or equal to 1.0, the transient insertion limits of Specification 3.1.3.6 ensure that nif f1cient SHUTDOWN MARGIN is available.

SHUTDOWN MARGIN requirements vary throughout the core life as a function of fuel depletion and reactor coolant system (RCS) cold leg temperature (Tcold ). The most  ;

restrictive condition occurs at EOL, with (Tcold ) at no-load operating temperature, and is associated with a postulated steam line break accident and the resulting uncontrolled RCS cooldown. In the analysis of this accident, the specified SHUTDOWN MARGIN is required to control the reactivity transient and ensure that the fuel performance and i offsite dose criteria are satisfied. As (initial) Tcold decreases the potential RCS cooldown and the resulting reactivity transient are less severe and, therefore, the required SHUTDOWN MARGIN also decreases. Below Tcold of about 200*F, the inadvertent deboration event becomes limiting with respect to the SHUTDOWN MARGIN requirements. Below 200 F. the  :

specified SHUTDOWN MARGIN cnsures that sufficient time for operator actions exists between  ;

the initial indication of the deboration and the total loss of SHUTDOWN MARGIN. '

Accordingly, the SHUTDOWN MARGIN requirements are based upon these limiting conditions.

Additional events considered in establishing requirements on SHUTDOWN MARGIN are single CEA withdrawal and startup of an inactive reactor coolant pump.

Other technical specifications that reference the Specifications on SHUT- DOWN MARGIN ARE: 3/4.1.2. BORAT10N SYSTEMS. 3/4.1.3, MOVABLE CONTROL ASSEMBLIES, 3/4.9.1, REFUELING OPERATIONS - BORON CONCENTRATION, and 3/4.10.1, SHUTDOWN MARGIN.

WATERFORD - UNIT 3 B 3/4 1-1 l

i l

  • l 3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT

]

The limitations on moderator temperature coefficient (MTC) are provided to ensure i that the assumptions used in the accident and transient analysis remain valid through each fuel cycle. The Surveillance Requirements consisting of beginning of cycle measurements. I plant parameter monitoring, and explicit end-of cycle MTC predictions ensures that the MTC j remains within acceptable values for ===t Of tM MTC iri ; each feel-cg4e-are l

&~2 te t0 conf 4es-the-MTC ":!ue since this c0-ffict=t ch: ;^ 010ely i^ pri 04 pally-te the-reducti= *- PIS b0 0 00nce-tratic :::^ct:t-d with feel burnup. The confirmation that the measured beginning-of cycle MTC value is within a tolerance of 10.16X10d delta k/k/T ]

from its corresponding design values 4t4-44mit provides assurances that the coefficient will '

be maintained within acceptable values throughout each fuel cycle. CE NPSD-911 provides the analysis that established the design margin of 10.16X10d delta k/k/*F.

i

?30?CSD i

b I

i

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i WATERFORD - UNIT 3 B 3/4 1-la l

~

p NRC, Document Control Desk -

TO WHOM IT MAY CONCERN:

PLEASE ATTACH THE ENCLOSED INFORMATION WITH ENTERGY OPERATIONS, INC. (WATERFORD 3) LETTER, W3F1-94-0131 DATED DECEMBER 9, 1994. THIS ENCLOSURE WAS INADVERTENTLY OMITTED FROM THE ORIGINAL SUBMITTAL.

THANK YOU.

1 I

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