Text

Amend 37 to License NPF-12,modifying Tech Specs to Define Allowable Power Levels for RCS Flow Rates Less than 100% of Thermal Design Flow
	ML20106B646
Person / Time
Site:	Summer
Issue date:	01/31/1985
From:	Adensam E; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20106B650	List: ML20106B646; ML20106B652;
References
	NUDOCS 8502120003
	Download: ML20106B646 (7)
	v • d • e

-

/

%^ ^ -

UNITED STATES O

4 W

E NUCLEAR REGULATORY COMMISSION

& !$ I WASHINGTON, D. C. 20655

\\p..... f.

t SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1

~

AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 37 License No. NPF-12 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment to the Virgil C. Summer Nuclear Station, Unit No.1 (the facility) Facility Operating License No. NPF-12 filed by the South Caro 1~ina Electric & Gas Comp (any acting for itself and South Carolina Public Service Authority the licensees), dated 3

June 19, 1984, and revised November 29, 1984, complies with the stan-t dards 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; 4

B.

The facility will operate in conformity with the application, as amended, the provisions or the Act, and the regulations of the Commission; 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 Ccm ission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this license amendment will not be inimical to the common 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 i

Part 51 of the Commission's regulations and all applicabl.e require-ments have been satisfied.

.i 2.

Accordinoly, the license is hereby a'nended by page chances to the Technical Specifications as indicated in the attachments to this license amendment and i

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.37 are hereby incorporated into this license.

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

8502120003 850131 PDR ADOCK 05000395 p

PDR m

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION p f ie. f ye, h <"

Elinor G. Kdensam, Chief b Licensing Branch No. 4 Division of Licensing.

Enclosure:

Technical Specification Changes Date.of Issuance: January 31, 1985 i

1 l

i e

e l

6-

---.e y

4

,m

- -- ~.,

r _ _.- -,

I ATTACHMENT TO LICENSE AMENDMENT NO. 37 FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 56 395 Replace the following pages of the Appendix "A" Technii:a1 Specifications with the enclosed pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. Corresponding overleaf pages are also provided to maintain document completeness.

Amended Overleaf Pages Pages 2-2 2-1 3/4 2-10 3/4 2-9 J*

e l

l l

j O

I l

1 l

j l

l l

\\

2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 ' SAFETY LIMITS REACTOR CORE l

2.1.1 The combination of THERMAL POWER, pressurizer pressure, and the highest shall not exceed the limits shown in l

operating loop coolant temperature (TFigures2.1-1and2.1-2for3and2185$) operatio l

APPLICA8ILITY:

MODES 1 and 2.

ACTION:

Whenever the point. defined by the combination of the highest operating loop average temperature and THERMAL POWER has exceeded the appropriate pressurizer pressure line, be in HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and comply with the require-ments of Specification 6.7.1.

~

REACTOR COOLANT SYSTEM PRESSURE 2.1.2 The Reactor Coolant System pressure shall not exceed 2735 psig.

APPLICABILITY: MODES 1, 2, 3, 4 and 5.

ACTION:

j MODES 1 and 2 Whenever the Reactor Coolant System pressure has exceeded 2735 psig, be

'in H0T STANDBY with the Reactor Coolant System pressure within its limit within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and comply with the requirements of Specification 6.7.1.

MODES 3, 4 and 5 Whenever the Reactor Coolant System pressure has exceeded 2735 psig, reduce the Reactor Coolant System pressure to within its limit within 5 4

minutes, and comply with the requirements of Specification 6.7.1.

6 l

l

(.

SUPMER - UNIT 1 2-1

\\

(

680

.;.-: h. n.. :.

- u. n

.u --

u

.n

~

=Eiiiji;~

M

' OPERATION UNACCEPTABLE

~ ' ~"

~~

E.~52:r

.=:::---

=_.

n :-::. n (25,661.5),:--

a:. ::n.=.:n-

-. - ~

i

..: sa;r. - :-

n--

-- nr g

~

~ ~ ~'~~

~~"~~~

~

~~

^~

?-

660

~~

.n un

u:==&_

%.....c

== =

m y;.-, p.

2400::..

..- :=tg_7,; :====:

.. p....

.._pn nu.==

n.ng cPSIA

-- - + :.n.

.;:2 un.. -

g

'" =I:=

- - --e r -- me :-

(2%.,652.) :

l.1 : ::

- = - -

cc

.. [.

_" m.-

_.... y_

n..

sn,mg (80%,639);: ;n,,

m a.

b

~

~"

I

~

i (2%,635)u.

..3 - "larfi..f2...heEU; - ". 4.._.. ".. __'..V~ ~.,O, _ tn.i.

r

~T

.... 2000_.

... W~;"2"3 =N-.. _..-..s iM PSIA. "IU#

M3

$-- NI; E

^

'g:{:

l*:

pgg

..n E

C

.Q:

4* n(. u t.

..l:

.. j....

t t. :!:':

2250 + _":-

r......:

u a...

h 620 N ~2nu n= r -

tt:%:g-a r-2

-(2%,,625) - } ^%m= s :.- =.._:ii : "

--A

t ;

_. g 4.

MQ:;g (

ll: - D Qi zij.$%ii. ;ijijiiii H

~4--

..:t.

..;. ::::.nng::h;-

n.

860 M..p-Fiqui --hw-g

..k s

1 M

n:

m.. :.,

.. (9. ;8%,607).%.

L........

.~.

z

.i

... PSI A :.

.. =..,,..

. r_......_....n..~:. g;,

e

@Q:

Qjgg y

q

...aj:a a.:..:. m, N.a g n. (120%,594) g o

.i u--

... au o

i.

.. f.:.... -....

_....... (104%,593)-

"A~

t-

p"- ' ' ": '-

r:n- : : p....

...g.

~ X-sn g-- (120%,587) 0-

~

~ " ~

r :Y V o

..; ACCEPTABLE ~

"#~

"3 U

OPE R. A.,T..I.O. N_.:

1".. ' M :--

~~<

.n

-- n

=

=:.

t 2:

2 rn 4 580 5TM 5b5! ii.i:ii" 5 155515 didi i

l

li

6 ";

' ih.. -

. T"....Ch..

(120%,575)

k...

R

~ - "

"-i;;ii-fr

~... ::

.E..

i i

i

"; :f T

- in.--

I5!' "il M (120%,568)

M' i5N.5

-!lil 5 i'..:

-- I-

.l.

.:l:.

~"

auhi

. ~~:::

~ '

..=

560 0

20 40 60 80 100*

120 POWER (PERCENT)

Figure 2.1 1 Reactor Core Safety Limit Three Loops in Operation

Fhen operating in Region III of Technical Specification 3.2.3 (Figure 3.2-3), the restricted power level must be considered 100% RTP for this figure.

t i

SUMMER - UNIT 1 2-2 Amendment No. 37

POWERDISTRIBUTIONLIMITS-ACTION:

(Continued) b.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of init.ially being outside the above limits, verify through incore flux mapping and RCS total flow rate comparison that r

the combination of R R and RCS total flow rate ate restored to withintheab;.velimNs,2or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

c.

Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced THERMAL POWER limit required by ACTION items a.2. and/or b. above; subsequent POWER OPERATION may proceed provided that the combination of R, R, and 3

indicated RCS total flow rate are demonstrated, through incore flux mapping and RCS total flow rate comparison, to be within the region of acceptable operation shown on Figure 3.2-3 prior to exceeding the following THERMAL POWER levels:

1.

A nominal 50% of RATED THERMAL POWER, 2.

A nominal 75% of RATED THERMAL POWER, and I

3.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of attaining greater than or equal to 95% of RATED THERMAL POWER.

j SURVEILLANCE REQUIREMENTS I

a 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.

4.2.3.2 The combination'of indicated RCS total flow rate and R, R, shall be' 3

i determined to be within the region of acceptable operation of Figurn 3.2-3:

a.

Prior to operation above 75% of RATED THERMAL POWER after each fuel loading, and b.

At least once per 31 Effective Full Power Days.

4.2.3.3 The indicated RCS total flow rate shall be verified.to be within the region of acceptable operation of Figure 3.2-3 at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the most recently obtained values of R and R, obtained per Specification y

2 4.2.3.2, are assumed'to exist.

4.2.3.4 The RCS total flow rate indicators shall be subjected to a CHANNEL CALIBRATION at least once per 18 months.

4.2.3.5 The RCS total flow rate shall be determined by measurement at least once per 18 months.

L SulNER - UNIT 1 3/4 2-9

.-r-

--,,n-,

i41 iiillitimIFuts+:+.fi+mIRilLTIHHHHHHMininifiHM4THHiWtHHH -jEi

~-~

t -:

MEASUREMENT UNCERTAINTIES OF 3.5% FOR FLOW

!N AND 4.0% FOR INCORE MEASUREMENT OF F"H~iNDEUDE'D

!N

' t:if A

g:

i_. W. 4

-i+t itiT* tit *i!+4+-

-t-O

u im 4

~

4,

@g;;*:

g 29 i rt+

tjr.

3 jg!

m+.4 p 1 :

. J+

t.I w 42.

5 i"

4..

t

17 p:.

>t 1

1 i:

itd* it jii[ g;

- 4

' et H1 +t*++Hf ttii WT

' pit Ni "REdidH

" **'3N.TC

th 1

REGION I It" t 4:

It t ACCEPTABLE y.r -g3]j*! II ACCEPTABLE 2fT4:22 :

h.. }u.y1 OPERATION REGION

.~.

T",..:::

FOR R R

~

2:

E

t. FOR R 'ONLY

~:r..m.. :.'_4-

~

tw t..

. 4 2

.u.

as m "i m ~y %.,,

.:H.i j 4~

iik_-t-L

.;a.. n._::

t. t. i.

L.. <_.1.-S.'.m.i. [

tt'it j

>+. u+

1

.3 t

.m -

..f i *-

..t.

.~. i. it

.t ---

m.

.. ~... niEEli !!!! 'i!!i if!!FEi ;iEllin; Uit -dit.E >

i 4*E' '

n.

iiii !.I ilH$

2

4-l'it tie ~:

.fli. l. iii:35 UNACCEPTABLE BEi

..,. m;

........u.

!!H ! !Li i-tui2EHIS ini itti $iMEi !Oi

]i,at

~~

i 't:.

f.rti C-lii OPERATION

d..gh t"

t:-

t a.

t!i:: =;n iiiltn REGION

n 2

W tit:

Tn: ::::

g rtu

/> bkU8:3$ Ek

!$1!h. [..._.

i44 i++

1 InI I'I1

i r'Ii N

.I

-. +. -.-+

i 1

S t ut !! I !

.;r++Tt '*tjttir n:

at*.

C 1:

~

..*

hIII1 '

.IiTI M.

-.44 + -

p

- I*

1, N }$

lL

' 6I '[III' gj

,*IIII It l

[

~"

I ha

,;t r **

+ + - -+---~tt++

.- ;g; n.g 3

,: ::p;:3 4

rn:1 23... -

5-

-+++-

y y}";;* t r.ttg

-m 1

G:

++

---+--

r:

n. ;; ;=

34

a

rr m

.2_

n:

t :p::=::::::2 ;. :n::}

I=: 4: ::=

~~

1 4._g O

n: rt t1 Ldi et.::

m tr:r-me

t+-

.t;' '.n:-:c: :n

..'l?.:t.h h

gi

!E;i;nN

!.!i.i..j ;! E.,.i 3..E~;~ii i.!'E"[IL.i

--'*-+-

. 11,_

t**- ***;

t... u. u.

.a

.... -_ :=..

.+In::1:..* I;

I,tt.. !. It, i.t,+*E.

-.. u:=. :. :-

in.-.

n,.+.t-eT..:+t, +;.-:::-

.74

.+

+

w

+.i.. 4.-

Q

.t fn,:.:w,f.-

r t ti.t n...a :n-i $ - 4.i.

h.022,N.1M II dI4.

m it:4 -: :nt v3

tt t

~

ntr O

i.p..i iHi _g.14L:: '74; tV-

--~*'

i,}!] KM i

,t.

.m42u

.m 1

a+s+. 7_2s.

.- ::=

t::n..

ll ula

tp itt

t+r:.

m E. -

4

11: t:

5 i lui

tit

n+'.ut ;t.

a

.22.

a

'nH tII r.#

r 1

y

ng r,

- mm m

m

~. "

'.:n; rt

. b Mite

+

1 1

'i 1.0, 30.43)

- (1_.0,30.12) a m

m..ai.. -u.-

1 g

30 a 9, i

i

(1.0,29.82) tn

r.'R"E"GION 111 m., :

m o9,

.-i(1.0,29.52) r-V

.......,.r 79' e'

. = ~. - _ +. - _ _

.l (1.0,29 21) 4.:.-

'+..++H t- - --+- :

.,....u. g

r. >........._.1y

.g ut im.m.

....y..

iil!llM ij}i:Wi L **~" WIEEE~:iEftiEn.'FH"[ k ui

", !I *-+ $5 i!i 412;4 't$?=_ _

.4iL1$..-.i..ii.!.IIEiii' tW. =..+. d. '.

..a...a....i$_.@..

@-j

!.!{2e.Q!.S.4 g.

4.

ut 2.

28 g.gg

,m,.,

m.

j 3.

_:1ta=:::tti q: g;: tm+

,m y

+-

m.

." t:

int

..==

4

1114 jMn1 gE;t21.:t- ~~-~~t r- :.ut.:;;; 7--+

n-re-

g3: :;u n-2n.am u

i

.l.r

-~

2.+

, !,t'

.. I'pM..ifN, iflili M.ENE_.UU i +t,4 i

$r.

Mi!i$

.7 i:;

pt.u.

i 4gr4;pc Htr-+r-n i +- mt i

1 1

n 1

1 a

u.

0.90 4.96 1.00 1.06

'1.10 f R, = F,"g[.#@.M.2 0.k R,= R[1.0-RBP (BU)]

NOTE: When operating in Region lit, the restricted power levels shall be considered to be 100% of Rated Thartnal Powar (RTP) for l

Figure 2.1 1.

i Figure 3.2 3 RCS FLOW RATE VERSUS R SUMMER.- UNIT 1 3/4 2-10 AmendiEiht No - 37

- -

ML20106B646

Text

Enclosure:

Navigation menu

Search