Text

Amend 46 to License NPF-12,revising Tech Specs Re Required Shutdown Margin from at Least 2% for Modes 3,4 & 5 to Mode & RCS Boron Concentration Dependent Shutdown Margin Variable from at Least 1% to at Least 3.98%
	ML20136B216
Person / Time
Site:	Summer
Issue date:	11/07/1985
From:	Adensam E; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20136B181	List: ML20136B178; ML20136B216; ML20136B229;
References
	NUDOCS 8511200157
	Download: ML20136B216 (8)
	v • d • e

. . _ _ . _ _ _ . __

UNITED STATES 8 % NUCLEAR REGULATORY COMMISSION j WASHWGTON, D. C. 20555

. e,

.....* SOUTH CAROLINA ELECTRIC & GAS COMPANY l l

SOUTH CAROLINA PUBLIC SERVICE AUTHORITY --

DOCKET NO. 50-395 ,

I VIRGIL C. SUPMER NUCLEAR STATION, UNIT NO.1 ,

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.46 License No. NPF-12

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

A. The application for amendment to the Virgil C. Sumer Nuclear Station, Unit No. 1 (the facility) Facility Operating License No. NPF-12. filed by the South Carolina Electric & Gas Company acting for itself and South Carolina Public Service Authority (the licensees), dated March 6, 1985, and amended October 18, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; .

B. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the 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 set forth in 10 CFR Chapter I; D. The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public;

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

2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment and paragraph 2.C(2) of Facility Operating License No. NPF-12 is hereby amended to read as follows:

(2) Technical Specifications

The Technical Specifications contained in Appendix A, as revised through Amendment No. 46 are hereby incorporated into this license.

South Carolina Electric & Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

8511200157 e51107

, PDR ADOCM 05000395 P PDR

l

3. This amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION f)J n I_ ',

cras/ +Y inor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing

Enclosure:

Technical Specification Changes Date of Issuance: November 7, 1985 J

D ATTACHMENT TO LICENSE AMENDMENT NO. 46 ..

FACILITY OPERATING LICENSE NO. NPF-12

DOCKET NO. 50-395 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.

Amended Overleaf Page Page 3/4 1-3 3/4 1-4 3/4 1-3a (new page)

B3/4 1-1 B3/4 1-2

REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN - MODES 3, 4 AND 5 LIMITING CONDITION FOR OPERATION 3.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to the limits shown in Figure 3.1-3.

APPLICABILITY: MODES 3, 4 and 5.

ACTION:

With the SHUTDOWN MARGIN less than the required value, immediately initiate and l continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7000 ppm baron or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.2 The SHUTDOWN MARGIN shall be determined to be greater than or equal to the required value: l

a. Within one hour after detection of an inoperable control rod (s) and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the rod (s) is inoperable.

If the inoperable control rod is immovable or untrippable, the SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable control rod (s).

b. Atleastonceper24hoursbyconsiderationofthefollowingfactors$

1. Reactor coolant system boron concentration,

2. Control rod position,

3. Reactor coolant system average temperature,

4. Fuel burnup based on gross thermal energy generation,

5. Xenon concentration, and

6. Samarium concentration.

SUMMER - UNIT 1 3/4 1-3 Amendment No. 46 l 1

FIGURE 3.1-3 ._ - ,_

.l bl .ljj b I!I REQUIRED SHUTDOWN MARCIN 0

!.. " I[

Iy. n[i, (MODES 3, 4 & 5) d ll' its l ;

l Jp li, ,[

4.0 'j i ; i ,,

n .i: . : :: @!

l '

, e d..j -

T: .- ; i 1 T.

g j l i'. .

!q!:; :,!'

ll , 4_ .I J

d i I

.g l ..

1 l[.

i i

..r_ ' . . .

l I; 1

'l

, - ,/ .,...

i _,!

l . !

ji I !!I' ACCEPTABLE / S/I g hY i llj MODES 3, 4 & 5 ,-

S,

~;

l l

,,P[j

] '{ ' g- >{' [ /

3.0

((

i .

1 .,

T[~

in g.

p -

1: _

,- 7

,,4

.:q g

l W >4 j.. .

,b h I

b -

f y.g.

'l

<3 l

.. f, ,

' h/. [- .

t. .

i.p,/

] ,

. 'I- E :

.t; 8

y .y ,

1 l~

.1 '.! g tri'

~g:l~;1' [f

,i_.j dh, '

~~- -

f...i

.t-

$ l

{. i I

p d

f'f 'y i f o t i -f -

, -i r M,4 2.0 I i i x l' ! !

S, h>

.i ,

I- ..'.p... ,I.' . . .

H I I I l 1.l.l' l MODES 3 & 4 .:q

,1.- ,1'. '

f g ,

m . . .

.2s. t. .

.I Q ..

4.,_ ,4 g

pr 8 .j ' ; ip fl ':ll";1tilrllitijlill[1111tljg; ij ,

$ . F:. Ii j ACCEPTABLE p '

$ 1 y! l -

t MODE 5 ;, -

i;l' 11it p~'/

p 41 i 3

t -

ll II' g jj, 3 i . .!!! .

6 i' 11: .

) ,

5 ki.: N Mj

~

MODE 5 d o :

.. I. . , , . , _ ;, ,'

N 1.0 .... 3 i

t. m -i T'j iU 7 ~ ' '

UNACCEPTABLE 6

~'

- I

! .j ..

s Lt.

H

+

, r ,

.. g g.L L j g 7 500 1000 1500 2000 7l fl 4 ,. m 1, , .

mmm, .

RCS BORON CONCENTRATION Cppii) ,

t ,

t

. v *% ,- - O

FIGURE 3.1-3

'2r" flli I !l !

dlIjj o

~'l' '

'E l l REQUIRED SHUTDOWN MARCIN (MODES 3, 4 & 5) d il!

t "l .

t % Uh i z 4.0 ' K." y , i ! ,

j i n. i 7 .o 7.j s j .j!! ; !.

lio g

H. ,.il

l p

q yll i l

i /

i g

o E'

~

r. , ,

=

I

~

~i~ -

i

UU

/ ',

I I [I,! !Ih :s *

~,, .1 4

[

I f! ! I; illl /, ! !

Il '", i O i .

ill' Iji ACCEPTABLE ~-

S '

I f !' !]l MODES 3, 4 & 5 ,

b .- S.- ,, M 3.0 h "h

~

7 lTl

p7 d "

{]

[ lg , j; g,f. .

je;)

Ell j t :l. !:; q

.l i ,W

' :j w

N .

U 1 .

, 1 j, i - -

y ,,,

... . p _..

.;... .: / j ly x

,,F ,,, p tl .i ,i _. !

g. 4 l. h. ' .! .!!!-

p 1

r .

3._

y, , 3.. ..

jp

..j.

4 4, .

g a c i i qI! q' 1 g/ , y

.d,N '

l 2.0 , - I i . !- + l' '

fI I' !

. - S 0

~

$.g! I g

8 L..

.t l i !,i l l'

.pi it l

. r_

t ll

___,i_ } MODES 3 & 4

llr;illivilitillilillintliti

,1. _.2 _L ji lf G/

+,_ .; j. . _[

A J" ' 3

$ ! l'i 'I ! ACCEPTABLE p '

y 4 y! LI t . 1 MODE 5 ,

- '+

o j il .

3 4 t" iI l[ fi- i1 p' y I gj,

T i .iii. + i- i! it: t /

l 5 17 : kth M

~ '

MODE 5 n O :: l .,, , ~,

,d d 1.0 ,

y a i

.L.4._ .: .j. j ,

t

~

L E

. UNACCEPTABLE j . = .

x 4 ,

a

1 t-g

s 5

m ,

500 ~ 1000 1500 i . 2000 il 1:. e i ! -

r-mm .. ,,,,,,,,,, m es m ,, ..... ..

RCS BORON CONCENTRATION (ppid) t Y d

-# J- #

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

a. Less positive than 0 delta k/k/*F for the all rods withdrawn, beginning of cycle life (80L), hot zero THERMAL POWER condition.

b. Less negative than -4.2 x 10 -4 delta k/k/*F for the all rods withdrawn, end of cycle life (EOL), RATED THERMAL POWER condition.

APPLICABILITY: Specification 3.1.1.3.a - MODES 1 and 2* only#

Specification 3.1.1.3.b - MODES 1, 2 and 3 only#

ACTION:

a, With the MTC more positive than the limit of 3.1.1.3.a above.

operation in MODES 1 and 2 may proceed provided:

1. Control rod withdrawal limits are established and maintained sufficient to restore the MTC to less positive than 0 delta k/k/*F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in HOT STANDBY within the next (

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . These withdrawal limits shall be in addition to the insertion limits of Specification 3.1.3.6.

2. The control rods are maintained within the withdrawal limits established above until a subsequent calculation verifies that the MTC has been restored to within its limit for the all rods withdrawn condition. -

3. In lieu of any other report required by Specification 6.9.1, a Special Report is prepared and submitted to the Commission pursuant to Specification 6.9.2 within 10 days, describing the .

value of the measured MTC, the interim control rod withdrawal limits and the predicted average core burnup necessary for restoring the positive MTC to within its limit for the all rods withdrawn condition.

b. With the MTC more negative than the limit of 3.1.1.3.b above, be in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

With K,ff greater than or equal to 1.0

See Special Test Exception 3.10.3 k

SUMMER - UNIT 1 3/4 1-4

3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 BORATION CONTROL

.3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that 1) the reactor can be made subcritical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and 3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.

SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS T,yg. In MODES 1 and 2 the most restrictive condition cecurs at EOL, with T,yg at no load operating temperature, and'is associaw d with a postulated steam line break accident and resulting uncontrolled RCS cooldown. In the analysis of this accident, a ~

! minimum SHUTDOWN MARGIN of 1.77 percent delta k/k is required to control the reactivity transient. Accordingly, the SHUTDOWN MARGIN requirement is based upon this limiting" condition and is consistent with FSAR safety analysis assumptions. In MODES 3, 4 and 5 the most limiting accident is a boron dilu-tion accident. The SHUTDOWN MATL%IN is varied as a function of average RCS boron concentration in order to provide adequate protection in these MODES. ,

3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT The limitations on moderator temperature coefficient (MTC) are provided to ensure that the value of this coefficient rsmains within the limiting condition assumed in the FSAR accident and transient analyses.

The MTC values of this specification Are applicable to a specific set of plant conditions; accordingly, verification of MTC values at conditions other than those explicitly stated will require extrapolation to those conditions in order to permit an accurate comparison.

The most negative MTC value equivalent to the most positive moderator density coefficient (MDC), was obtained by incrementally correcting the 10C used in the FSAR analyses to nominal operating ceditions. These corrections

. SUPMER - UNIT 1 B 3/4 1-1 Amendment No. 46

REACTIVITY CONTROL SYSTEMS BASES 1

MODERATOR TEMPERATURE COEFFICIENT (Continued) ,

involved subtracting the incremental change in the MDC associated With a core condition of all rods inserted (most positive MDC) to an all rods withdrawn condition and, a conversion for the rate of change of moderator density with temperature at RATED THERMAL POWER conditions'. This value of the MDC was then transformed into the limiting MTC value -4.2 x 10~4 delta k/k/*F. The MTC value of 3.3 x 10 -4 delta k/k/ F represents a conservative value (with correc-tions for burnup and soluble boron) at a core condition of 300 ppm equilibrium boron concentration and is obtained by making these corrections to the limiting MTC value of -4.2 x 10 -4 k/k/ F.

~ The surveillance requirements for measurement of the MTC at the beginning and near the end of the fuel cycle are adequate to confirm that the MTC remains within its limits since this coefficient changes slowly due principally to the ~

reduction in RCS boron concentration associated with fuel burnup.

[

3/4.1.1.4 MINIMUM TEMPERATURE FOR CRITICALITY This specification ensures that the reactor will not be made critical with the Reactor Coolant System average temperature less than 551 F. This limitation is required to ensure 1) the moderator temperature coefficient is within its analyzed temperature range, 2) the protective instrumentation is within its normal operating range, 3) the pressurizer is capable of being in .'

an OPERABLE status with a steam bubble, and 4) the reactor pressure vessel is above its minimum RT temperature.

NDT 3/4.1.2 BORATION SYSTEMS The boron injection system ensures that negative reactivity control is available during each mode of facility operation. The components required to perform this function include 1) borated water sources, 2) charging pumps,

3) separate flow paths, 4) boric acid transfer pumps, and 5) an emergency power supply from OPERABLE diesel generators.

With the RCS average temperature above 200 F, a minimum of two boron injection flow paths are required to ensure single functional capability in the event an assumed failure renders one of the flow paths inoperable. The boration capability of either flow path is sufficient to provide a SHUTDOWN k

SUMER - UNIT 1 B 3/4 1-2

ML20136B216

Text

Enclosure:

Navigation menu

Search