ML20056D692

From kanterella
Jump to navigation Jump to search
Amend 113 to License NPF-12,modifying Figures 3.4-2 & 3.4-3 of TS 3/4.4.9 & Removing Table 4.4-5
ML20056D692
Person / Time
Site: Summer 
(NPF-12-A-113)
Issue date: 07/28/1993
From: Bajwa S
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20056D693 List:
References
NUDOCS 9308170334
Download: ML20056D692 (7)


Text

'

[pwo uq UNITED STATES

[

j NUCLEAR REGULATORY COMMISSION

~*

WASHINGTON, o.C. 205E0001

%...../

SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUMMER NUCLEAR STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE y

Amendment No.113 License No. NPF-12 1.

The Nuclear Regulatory Comission (the Comission)' has found that:

A.

The application for amendment by South Carolina Electric & Gas Company (the licensee), dated October 6,1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as i'

amended (the Act), and the Comission's rules and regulations set forth~in 10 CFR Chapter I; j

t B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; a

C.

There ~is reasonable assurance (1) 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 common defense and security or to the health and safety of the public; j

and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commision's regulations and all' applicable requirements ~

have been satisfied.

l t

2.

L Accordingly,!the license' is amended by changes to the Technical i

Specifications, as indicated 'in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No.-

1 NPF-12 is' hereby amended to ' read as-follows:

.j I

9308170334 930728 PDR ADDCK 05000395

.P PDR l

ic

F E

5 i (2)

Technical Specifications and Environmental Protection' Plan i

The Technical Specifications contained. in Appendix A, as revised f

through Amendment No.113', and the Environmental Protection Plan contained in~ Appendix B, are hereby incorporated in the license.

South Carolina Electric & Gas Company shall operate the facility in.

accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION S. Singh Bajwa, Acting Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachment-Changes to the Technical i

Specifications f

Date of Issuance: July 28, 1993

.j h

I I

ll t

i l

l l

t I

ATTACHMENT TO LICENSE AMENDMENT NO.113 TO FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 Replace the follewing pages of 'the Appendix A Technical Specifications with the-enclosed pages. The revised pages are indicated by marginal lines.

.i Remove Paces Insert Paaes 3/4 4-29 3/4 4-29

.f 3/4 4-30 3/4 4-30 3/4 4-31 3/4 4-31 l

3/4 4-32 3/4 4-32 i

I I

I i

~

-l i

5 l

t

.i i

'I l

4

I' aEACTOR COOLANT SYSTEM 3/4 a 9 DRE55URE/TEWPERATURE L:"ITS DEACTCR COOLANT Sv5TEu

.':MITING CCN0!TICH FOR OPERATION

3. a. 9.1 The Reactor Coolant System (except the crassurizer) temocrature one pressure sna11 be limitec in accorcance with tne limit lines snewn on Figures 3.4-2 ano 3.4-3 curing neatuo, coolcown criticality, anc inservice I

lean anc hycrostatte testing with:

A maximum neatuo of 100'F in any one hour certec, a.

A maximum coolcown of 100*F in any one hour certoa, ana l

c.

A maximum temperature enange of less than er ecual to 10*F in any l

one nour cerica curing inservice nyorostatic anc lean testing operations acove the neatuo anc coolcewn limit curves.

ADPLICABILITY:

At all times.

ACTION:

With any of the acove limits exceeces, restore the temperature anc/or pressure 1

j to within the limit within do mirutes: perform an engineertng evaluation to catermine the effects of the out-if-limit concition on the fracture toughness properties of the Reactor Coolant Systes; catermine that the Reactor Coolant System remains acceptacle for continueo operation or be in at least HOT STANDBY within tne next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> anc recuce the RCS T anc pressure to less than 200*F anc 500 psig, respectively, within the* Yellowing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS a. 4. 9.1.1 The Reactor Coolant System temperature and pressure shall be determinec to be within the limits at least once per 30 minutes curing system hettuo, cooldown, and inservice leat anc hycrostatic testing operations.

a.4.9.1.2 The reactor vesses material irractation surveillance specimens shall be removec and examinea, to cetermine changes in material properties, at the intervals recuireo by 10 CFR 50, Appencix H.

The results of these l

examinations shall be used to update Figures 3.4-2 and 3.4-3.

SUMMER - UNIT 1 3/4 4-29 Amendment No. 53, 113

i-t i

r t

THIS PAGE INTENTIONALLY LEFT BLANK t

T SUMMER

. UNIT 1 3/4 4-30 Amendment No! E3,113 I

REACTOR COOLANT SYSTEM h

MATERIAL PROPERTY BASIS CONTROLLING MATERIAL: LOWER SHELL INITIAL RTNDT:

10*F ART AFTER 14 EFPY:

1/4T, 96*F 3/4T, 83*F

w i :-..,

i i,..

.,,,i6 i i i..i....i...

._i, L..,,,..,

i,.,,,, i ;

3

,~,

v i,.,,

,1,

,s....,.

3

. i LEAK TEST LIMIT I '. 1 s4 s'r i,.

m.

.ii 1

i, r

i,...,...

,, i i,

, i 6,,,

i,

,si

. 1 1

s.

i

,.i.,....

,,,, f

, s V

g

{,

I i..

is t

.,i s s i

,...,,, i

,.e i

e i..

& i

...,,.. i i..

1 ij y

J g

... n i

0,.,.

. i i i,,

... 6.

..f,.

1 fi.i.

,,, i.

.. i.,,.

Es

. 1 il i a JL,.,,, s...

,....,,. i.>

l r i i s ACCEPTABLE

+ ' ' ' '

,, 4,,,,,i... 70PERATIM t

.,..4 i

r.

i.. 4

.... i. i.. i *E ' i.

iii i ii4

. :s.

... 1 i i $

i

  • i. i. i

.... i,..,,,

r-ei r!./ :.... e i..

i 1 1,.,....

.i i.,c s

i si 4 i...

.4 UNACCEPTABLE

..,s r

i ir CRITICALITY LIMIT BASED i,,

OPERATION

.','.r i.'i

.' i.

ON HEATUP CURVE UP TO I'

f '# '

i o.: s; i

i.,.,

,,A

, (l rA i

~

,.,<i...i i s,/ !

I N

50*F/HR

.,,.r.ir ri n

eesi t

t?*

O i,,gs g3/ ) if f i

. e..

i e,

i. t i.

i d. :=.

..s

. ]

iE/

s 1

,,. t..

  • 4.
  • I...

+

....,,,if e ft /

,f

,,i

, i..,,.. i... s 1

5 6, i... ri s ir, r.

.ieiii.ii,.........i a

. r..s r i o.

iii

.e.......

.....it

  • t /i

.+'

' #+.'e i.'

CRITICALITY LIMIT BASED

. ' i

=

. 2 r., :

'i+

+#

' ON HEATUP CURVE UP TO HEATUP RATE 5i i >
  • e'#'

/C o

UP TO

.' ' i_' I ' ' # ' ' v..'.'N y

i i i

./HR w

.f,i 1

100.F 50*F/HR 4

,g

,f i,,,

, 3 i,i1 IO0*F/HR

_.f S

s:

i.. i,..

i.

mr....

...,i.,.......

e i <

i r,

ef 1 i..

,.. i

.,iie.

z f

... i.

, i......,

. n.

i,ii..

3,1 4

,.3

.., i i...

.i,

..i6..

it, i.. 6.

. i

,.i

..... 6 iiiiii4

.4

.. 4..

i..

i, 4 +,i+

3 i~ CRITICALITY LIMIT BASED ON i '+*'

, ii

.i INSERVICE HYDROSTATIC TEST 250l.l l,',

','!l,l'l.ll,' TEMPERATURE (237'F) FOR THE ! ' i.' ' '

SERVICE PERIOD UP TO I4 EFPYi

..i,i 4 i..

i i

.,,, i. 4,,,.

,,.... i,....

3.

.6

,,,-... i.

i.

,..i.

6 "O

50 100 150 200 250 300 350 400 450 500 INDICATED TEMPERATURE (oEC.r)

Figure 3.4-2V. C. Summer Unit 1 Reactor ~ Coolant System Heatup Limitations (Heat up rates up to 50 and 100*F/hr) Applicable for the First 14 EFPY (With Margins 10*F and 60 psig For Instrumentation Errors)

SUmER - UNIT 1 3/4 4-31 Amendment No. E3,113 L

REACTOR COOLANT SVSTEM MATERIAL PROPERTY BASIS CONTROLLING MATERIAL:

LOWER SHELL INITIAL RTNDT:

10*F ART AFTER 14 EFPY:

I/4T, 96*F 3/4T, 83*F 2500 t ca m vc-a. e i i

., i,,,,,,i

> + +

-,, i i,

,4 i

,4 4

4,,

I i

' ' i t ' +

.'*.i,#

', ! t i

i

,,, 4.

,4

. i, i i e i

i,,

2250

! ' ' ' '.' ', ' ' i,,,'

i

+. 4 g,

'...... 6.,.

f,,,.

4

', i i +

.i+,6 6,

ii i i,,

r..

4 i,

6, i,,,, i,,,

e i i..., e i,,

,i-n,,,,,,

2000 'ie

'I' i

i * *

  • i iiii e,, i i.. i i..,

,i, i.

t.

,i 6

i,...

e.. i i

,,, i,,,,,

+

. i i i.

,,,, i... ilt a e i e i>i.I i,

. i 4

.4 i

,1 if 4.,i

, i

, j

^

1750 i ' ' ' ' ' ' ',' ' '

  • 4

' ' if '

' ' d i *.i+ie i,

  • t i e 4

i, i i i i

ACCEPTABLE

>i...

i

! i -

i i i eii: i..

t i. '

OPERATION

' ' ' '!**i' i

' ' UNACCEPTABLE

'I i - e i i

  1. i e6 i..,, 6 i l

OPERATION I

' ' i '

' ' 4 ' ' ' '*i i -

i +

' +i i '

1500

.' ' ' ' +, ' e

/

i

+ e i. i sa i i....

_e i

i i

, i ie i

/4 6 i ia,.

  • i e i i

i f,,

j.,,i4 a

,,,, i,,,,,,,,,

iii ii !.. 4,

i.

ie.

c.

., i.

i.i..i,

,f !.

,,,i,, i,, 4, 4,,,,,,,, 3,,,,

u 1250

'.'. ' ' if,I ',' 'a i, ',' ',' i i ',' ',' + 4 6.. i i. -,

=

i.,,

4 i

i

'

  • I '

I 8

I l ' I 8

i 8,

, ifi i f

i,, i, s 4 j j

,4 j, i, ia e j,

ie...i

.e i,

i i e i e f,. e e..,.,,,,,,,,.,,,,,,,,,

o 4.

i f.,

,,,..,.,,,,,,,,,,,,,,i, u

' ' i' E N00 ! - - -,, '

,'.'iii.',,',''*,,

t

  • -, i

+

i.

i -. i..... s i. i.

,.y,,ii o

.,i i u

';e i.,

+... 4 i. is t i,,,

i, i,,,

... i

. t is.,,,..,,,,,,,,,,,i,,,,

i y

750 COOLDOWN RATES

' 9,'l,!lllll ll lll','l,',',

l l

  • F/HR o

Tt <

4,

0 i

i i

.,,i, 25 --

- ia ei >

t i i..

i 500 50 W-

' i i t * +.

t i i e e i 100 ?...'l'.'.'e'

+ i, !...ii,,

4. 4,

3,

i i...

. i 4

.i,...i,,,,,,,,,,,,,,,,

' ' i i ' ! ' ' ' '

250

' ', ',' ',',' ', ', ' i i i i e i..+'-

i i.. i

,i, i

1

,, i

....,,,,,,,,,,,,i, i

' + i#.i

.,i i.,,.,

4 i,i,,,,,..,,,,

it g

,,,4 0

50 100 150 200 250 300 350 400 450 500 i

INDICATCD TCWPERATURC (DEC.F) 4 Figure 3.4-3 V. C. Summer Unit 1 Reactor Coolant System Cooldown (Cooldown j

rates up to 100*F/hr) Limitations Applicable for the First i

14 EFPY (With Margins 10*F and 60 psig For Instrumentation i

Errors)

SUMMER - UNIT 1 3/4 4-32 Amendment No. E3,113

.