ML20127H224

From kanterella
Jump to navigation Jump to search
Forwards Draft Amend to Ol,Se,Notice of Issuance & Kr Goller 750701 Memo.Amend Regards 750325 Proposed TS Changes to Suppression Pool
ML20127H224
Person / Time
Site: Millstone, Hatch, Monticello, Dresden, Peach Bottom, Browns Ferry, Nine Mile Point, Oyster Creek, Cooper, Pilgrim, Brunswick, Vermont Yankee, Duane Arnold, Quad Cities, FitzPatrick
Issue date: 07/15/1975
From: Ziemann D
Office of Nuclear Reactor Regulation
To: Mayer L
NORTHERN STATES POWER CO.
Shared Package
ML20127H228 List:
References
NUDOCS 9211180448
Download: ML20127H224 (11)


Text

.

4 jut.15 1975 DISTRIEUTION ORBr2 Reading WOMiller C-p p M,

occet. o. %-2 6 3 Docket BScharf (15) g gg.

Attorney, OELD TJCarter NRC PDR,

PCb611 ins 016E (3)

SVarga

,r wre t at e9 Power conoas:v Local PDR Cliebron NDube ACRS (14)

ATTI.:

rr. L. O tlayer rirector at Fuclear BJones (4)

-AESteen Support Se rvices JMMcGough GmM Ik_

'd4 ::icollet Pall JSaltzman bec: JRBuchanan Minneapolle, itinnesot a $5401 RMDiggs TBAbernathy Q" BCBuckley i y DLZiemann I

- entleren:

SKari The Con::ission has recuented the feovral Fenister to putslish the enclosec

otice of Fronoseu Issuance of an Amendment t o racility Liciinse ho.

! P E *.

for ti v - or,t icello 'uclear +.morat tnc Plant.

'N eroposed mend-aent includes a caance to the Tecnnical Specitications and is in r esporer.o to your request dat ed !! arch 74, 1975, which was submit ted in renly to our letter-dated February l'.

1975

. :i c em wi t Ucertarm.r:- tla sater t eniv rnt ure firsta wuring (m y -

testine which adds heat to the sucprstenion pool, ( 2) suppression nool

>ater tenterat ure li::ita recuirire manuci cerar et the reac t or. ( ~1 )

suppression pool water temperature limits rescuiring reactor pressure vensel derreasurization. (l. ) aurveillance requirements to runiter uster tencernt ures duriv ooerat ions which add heat to LSe suppression pool snd i

( 5) oxt erntal visual examinat ions et the suppression chattbers followine operations in unich t he pool tenpuraturen exceed 160 f.

Turine our revinw. we discussed with your st at t cert ain modi f icat ions to t ne proposco enanFe bh t eti tr.ey arreed were necessary 'er.Lortfication etnd. complet enes s.

'Ibese nodifications havia.been nade.

iecies ei vur *roceaec'iteense nr.enment. with enances to the Tecanical

." rec i t ic a t ion s, catety rvaluotton are the F.* err.1 les is t e r Tot ic e re la t in -

to this actier al so are enclosea.

it.c c re l y,

iI,

Original Signed by:

~'

Dennia L. Zie:nnn ernio L. ?T7.?

Ti c t ceret u

.%c t v ra r ar.e -

tivisten at Seact or Liebnsine i

I OELD M b

rnetoeures:

m erz sec t L 4. L ewM M

-/cronose, 'feco inre c:ac e h/f/75 e,......

c.,, i.. o,-

'.. cera1 re" t t. r. ot t "

RL:GRd 3/

RL:AD/ ors v Riz:0RBS 2 -

Rir: ORS #2

-RL:0RB#3 r-n f.,

omc=

  • BCBt%kTby CJDeBeve '

DL2 Nm'a n FRGoller

.u,.,a.. d. n suren:

,D Q a._./... /.._7 5

/ 'k/75

)/1/75 j/g" 75~~

/

n'

.q

-.. p.

Foran AEC 51 (Rev. 9 ShWCM 0240

  1. u. e4 eovsawuant enswvine orrics: to74.eas-too 9211180448 750715

~*

PDR ADOCK 05000263 P

PDR

Northern States PowGr Company JUL 3 5 E75 cc w/ encl ures:

Arthur Ren uist, Esquire The Environmental Conservation i

s Vice President - Law Library i

Northern States Power Company Minneapolis Public Library

)

414 Nicollet Mall 300 Nicollet Mall l

l Minneapolis, Minnesota 55401 Minneapolis, Minnesota 55401 Gerald Charnoff Mr. D. S. Douglas, Auditor Shaw, Pittman, Potts, Trowbridge Wright County Board of Commissioners and Madden Buffalo, Minnesota 55313 010 - 17th Street, N. W.

Washington, D. C.

20036 cc w/ enclosures and cy of NSP's i

filing dtd. 3/24/75:

Howard J. Vogel, Esquire Warren R. Lawson, M. D.

Secretary and Executive Officer Legal Counsel 2750 Dean Parkway State Department of licalth Minneapolis, Minnesota 55416 University Campus Minneapolis, Minnesota 55440 Steve Gadler, P. E.

2120 Carter Avenue Mr. Gary Willians St. Paul, Minnesota 55108 Federal Activities Branch Environmental Protection Agency Mr. Daniel L. Ficker 230 South Dearborn Street Assistant City Attorney Chicago, Illinois 6060' 63S City Hall St. Paul, Minnesota 55102 Mr. 1"enneth D:ugan Environmental Planning i

Consultant St. Paul City Planning 421 Wabasha Street St. Paul, Minnesota 55102 Sandra S. Gardebring Special Assistant Attorney General Counsel for Minnesota Pollution Control Agency 1935 W. County Road B2 Roseville, Minnesota 55113 Anthony Z. Roisran, Esquire Berlin, Roisman and Kessler 1712 N Street, N. W.

Washington, D. C.

20036

--q,.--

..,,,, +

w

+.-

p

i l

i.ORTliEltil LTA'atS l oktB CGhl'AbY i

LOCKLT E0.,50-271 PONTICELLO til' CLEAR GE!1EFATING STATIch l

Pl.0P0. FED.. AME.t:I.mtNT. 70. l'ACILITY.OF. F. RAT.ING LICE NSE

/.senotten t Fo.

License 14o. :.Pr-2 2

}

1.

The 1:uclear lieuulatory Comission (the Coc: mission) has found inat:

A.

The aorlicat ion for arnendt,ent by Northern Etates Tower Company (the licen ce.Q

r..'te c'ren ; '.,

l'.' 7 5, conni i es *. i t a tLe st nt'ari s

~

and recuirement s or ine At oriic Eneroy cet et IM4 es attendeo (the Act) and the Cornission's rulos.ind regulottons set torth i t' 1r. Off Charter I; The tacilit y '.ill crercte in ceutorr.ity t it e 1:.e i n lic.:t ten,

the orovisions of tne Act, and tha rules and revulations ot t :w ro-minion;

-o.L (de at t /tt we. u t..cr i :e

... re.. rei.r>u m le.. -n u r t r e s.

i. 2 1 by t his amendrient can to conducted without encaneerinn the nealth ano sately ot the public, ano (ii) tnat such activities will be conducted in conpliance with the commission's regulations.;

and h.

Tae issuance t n i c aceron>c r.t '.i ll not

'e iri:iic il t o t he o.

co-ron detense and secttrity or to tno healto ena cafety of tne r:u b l ic.

7.

Accordinesy t he license is crer. cec t'v a ct4 ante to the Is*c b e t ca l 2 rec i:icat tent, as incleated in t he rit t c.cnrent t.o this license mendr ent ro r :'

a,

c a.. i.

..c.

.o

r.. a. --
l l e +n :

0FF.C E D

==

sv =N a u s

  • oata >

~

Foral AIC.318 (Rev. 9 53) AECM 0240

  1. u. Si GOVERNMENT PRINTING OFFICE 31974 888 848

_ g.

i I

'E.

Technical Specifications The Technical Specifications contained in Appetidix As as revised, are hereby incorporateo in t he license.

The licenseo shall operate the f acility in accordance

'sith tne Technical pecificatienti, as revised by issuad chantes tuereto throut;h Chance !!o.

i 3.

'.h i n license itnendrwnt is etfactive as of tile date ot its i s::t t ace.

(Oh 'Dit i.tALEAh RI.GLllaULY ( Oc.!il%IO!:

4.

G i n cib u s so. Director Civision oi. enct er !uests ian Citico of l'uclear f.eactor Fitaulat tan Attachnent :

Charce t'a.

ta the Tecnnical Spect f ications

. :t e it

": m aco.

ugaes e.

W48 5#'M

'e

-behe" sunwaus

  • D&TS >

=_...e Form AIC.385 (Rev. 9 5H AICM 0240.

W u. a. sovsanutut ensurine orrics sev4.sae-see

-a I

I

,a PROPOSED CilANGE TO TIE TEC194ICAL SPECIFICATIONS i

FACILITY OPERATING LICENSB NO. DPR-22 i

DOCKET NO. 50-263

'the Technical Specifications contained in Appendix A, attached to Facility Operating License No. DPR-22, are hereby changed by replacing pages 139, 140, 157 and 161 with revised pages bearing the same numbers and additional pages 157A and 161A. Changed areas on the revised pages are reflected by marginal lines.

i w

h OFFICE W c..

evanaue >

m_.

+ -

DATEW g

- ~"'

~

Form AFC-Sla (Rev. 9 53) AFbd 0240 W u. e eovanwuswy eningsme opricas seva.eae. toe k

.____...i.

h.O SUh'F.ILUd!CE IG/13IILE51TfS 3 0 LI!Tf1':G CONDITIONS FOR OPERATION 4.7 COUPAIIr1EIrr SYSTFRS

[

3 7 CO?!rAImtr SYSTD'S At.plicability:

Applictbility:

Applic - to the operating status of the prirary Atplies to the primary and secondary ccic'tinment integrity.

and se--onda.y containment systems, Ob.j ec ti ve:

Objective:

To assure the integrity of the primary and To ve rify the integrity of the prim try and secondary containment systems.

seconlary containment.

Specification:

Specification:

A.

Primry Containment.

A.

Primary Centainmer.t.

1.

At any time that the nuclear <ystem is 1.

The suppression chamber water level and temperat ure shall be checked once per day, pressuri::cd almve atmosphe ric or work A cima! inspect ion of the snppression is being done which has the potentiaj ckrd.cr interior incieding water line to drain the vessel, except as permitted re; inns and the interior painted surfaces by specification 3.5.G.4, tha suppres-above the water line shall be made at sion pool water volume and temperature ench refueling outage.

Whenever there is shall be maintained within the following indicar ion of relicf vaIve operat ion which limits.

adis heat to the suppression pool, the pool ter.perature shall be continually (a) Maxit Water Temperature during monitorn! and also olmerved and logged normal operation 90*F.

every 5 ninutes ontil tbc heat addition is teinina:cd.

thonever there is innlication (b) Maximum Water Terperature during any of relief valve operation with the test operation which adds heat to the suppression pool - 100*F and shall not te: perature of the suppression pool reaching 160*: or more and the prima ry coolant be above 90*F for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

systcu,,ressure greater than 200 psig, an extended visual exanination of the suppression (c)

If Torus Water Temperature exceeds IIO*F, ch:,nber shall be conducted before resuning initiate an immediate scram of the Fower operation.

reactor.

Power operation shall not be 1

I resumed until the pool temperature is 3,, n

3.0 LIMITING C0_N'ilTIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS (d) During reactor isolation conditions, the reactor pressure vessel shall be depressurized to less than 200 psig at normal cooldown rates if the torus water temperature exceeds 120*F.

4 r

(e) Minimum Water Volume 68,000 cubic feet.

(f) Maximum Water Volume 77,970 cubic feet.

2.

Primary containment integrity as defined in 2.

The primary containment integrity the Section 1, shall be maintained at all shall be demonstrated as follows:

times when the reactor is critical or when the reactor water temperature is above (a). Integrated Primary Containment 212 F and fuel is in the reactor vessel ex-Leak Test (IPCLT) cept while performing low power physics

. tests at atmospheric pressure during or (1) An integrated leak rate test after refueling at power levels not to ex-chall be performed prior to ceed 5 Mw(t).

initial unit operation at an l

initial test pressure (Pt) of 41 psig.

(2) Subsequent leak rate tests shall be performe! without preliminary leak detection surveys or leak repairs immediately prior to or during the test, at an initial pressure of approximately 41 psig.

(3) Leak repr. irs, if necessary to permit integrated leak rate test-ing, shall be preceded by local leak rate measurements where possible. The leak rate differ-m

~

-m

-,-. m n,

b

.... _ ~.~_

n._ -_:.-_.. - _... - _

_ _ ~ -

_,~.. -~,

. _. ~

n...

i t

4 1 **~

1 A

V U

4 e

w 4

-4 O

O P

k O

)

a 4

e o

a U

ct I < w0C-O 3% Om M c+ 6-3 to H M

v 00 7 C O M

M O *'1

  • v)
  • d u 01. **d.;

O* O

^

Q

b *

~*O P

    • , "t C

% *O PD@

p M

U H

O ce w O OO

  • U O 3. M 0
          • ~e U

M >=

Q O

F*

("a M. ($ Q d #1

  • 1

"* La ?1 O cr C**

M fd *. *O N*

  • 1 M 13 O U n
  • .?

M. O r d' 6

O H M 4 re Oho %

M Y* G

  • 1 7 O O O M n p ' y N

n e+

ow n

w 8 %

h mD Q. ce c

o o.

,. p o

w9 on n

M

'~

oo g

ooM pmL

-a t z

~ ~

u=cw

~0 0

0

.e 2 o

4 a

c M -- :r.-

onun

,a -

,o a n o m M e

n.3 C

1 o

A M O O *? O O L *U N

na.-

O P {J Q%

p n

I * *

  • C" (S *** O N

% s

".: h m *g u

D w'

D 0

re p

0 0 0N x Q

+1 E

g H*4

=

  • 1 C W D w o r, m u 9

5 P

b 'C f'

<+ 4 D D t

e 3

g.

o 1

3 O

'c o m e O % 'd

+ 0M W

9,p O ti M

  • 1 p 4 *,1 uH

-%on-

-awu O p

- r> o u r o v.

5 J

j
3'
a et MenO i

~ ">

i 1

x o,c*.

p o u a H o r.

o

~~ o r+

=~ n.. m - r-E* O n4 o

g mn

-p&

1 m

e. n..O, C,,

a >,, <.

n op n

L n

o n cp :-

PJM O

O W *** O M Et CT j

q g

omyon :; -

U U !4

'Y U N s*.

5 ',.

8

'O

  • G ;., d j{

v..

M f.. "

O *~*

M

  • U M

f! (* C O

e o*

Q W L

t 2

}

p y*

O G

>* C O V l

r+

O ::.

~97M O

8' i

y s* $2 %cm og <*

t' O* 's o

  • ' 0T !!.

O

+ p' e f+ *1 Q s O eU

< 'O 3

.h y.

n -, m o.

p o +-

oo-n D*

b.J) U V

~, _,

p fe -

f

'O O

e -. n n

O ~ n m' n

O 3

D' D G ? Od 1 (1 3

n a r ~. n W&

O +

h o%

.o,1 u = c-oo u n u "e O

O v

c :~* v. v. C g

  • 7 fU

'3 e e o

r+

    • ~<

F' O

..r4 r,

re g

&g 1

  • 3 O Ve f., Q :.:
  • 1 et
)
j 9r o

-- e e n a"s ry-2

  • 1

-j p

Q *

  • 4 y u,, e s.

,c, t

o.

o oo

.,3

-. oe a: r;, n

.. o r.,

~

n oo o

.u

.- e 0G

)

9

  • o yn e

U -} O t

b

=

o urn = n

= n W

  • C "J 1 }

f

= > u a u, a, u.

G *n at

  • d*

C*

.~.

1. n e

- 3 G *~

e, G

  • ,a.

r, 9 ;;

c.

+

Q~~'

    • O M

a nl u

g,;

D e n

54 m

".)

we.

    • tt G yM v.

y Q

p O r *,' U C

r g

g

'*s er M

u o oa e,

C*

c' e. O c = c:... "

0

.p 1

a p

M

  • t",

,a w

    • * % *< ** D a,

'*;+

M,

'A

<s 6

D,.,

} i.a wc 1

C O. h,"

  • U C

q p

^^ q

~*

P~.-..M.

(<

w. e m

y M e,,

M.

u Lg m'1

&W Q C+ Q re m.,.

s.

1 r=

H l

1 L 0

  • 1 O
  • O' **
  • y.

g

- ()

k, C., " < M

< Q fJ h O

4 y

O E

1

  • oe o.a @U9

%.y@L 3,

dg pe wco o

.a e. ; 0 o-m o s "a

- 7.M

,i u "o.u.". ~ o O

w o

e o v. o a

  • 1 6" nd" q

.r' y

M "?.

  • e
a. r p y

nH 9._

.,o u, ' y<.

O

~.

p p o

a l,

e

.J

'g o%

f.

er.

~

r, ge M

s r9

            • .e.a u..

C' -.:

... +..M

.c

  • Q
a -

a -#

Q p g w =. m..

e

%.. O li o3 c+

JD D **

  • * - ~
  • O O y" M

.o o

g. o.4 o

r *~

O r;

t r* O O 9 p 0

r, e,

.a

'1

  • m.-

M o.n.

r+ w C O /*.

O M

'.ra ~

f'.

C

% R L,

il rt E,

o y .

7 O C.

r*

j7 n -. C. ' '

  • 3 H

., -. o

  • *'j f..* W,,,,(*

'.^7 pt" w

i g'

H ej N

b E*)' :.'

  • C'

~' * * ' "I O #

.. O 8

9 l

  • O

. C U

6 M

1 y y*

ed r*

U p

e

,[.

f.

    • 'J.

< W "J

V

'd

  1. d
  • ~'#

M L en M

'y.~$.

e p

'1 %

. = *7 G

6e o T 7,, ****j.~,.),)

n. :D. u n.,

w.

v.*

C p

g *} q

~

g

..: O mQ cs 4

  • / ~

D w

b i *-* O O Q

, g

' ': * !D Pt *~* wU en <

L*

%, y,')

p ps.

Op oVT H-'

. ~

O G G C D.

G O *,; u ej M

e

  • y D

+- C :i

(*

A ".

yw. et H

D C*

Q

(?

U R O n.

O p

)

P 0"

  • y C

f*-

p,,

  • ,4 C N M*

l'" *O D

ct

  • 1

, C r: L

... O G G d rt Q t9 g

D9

t t q

M '"

D G

  • t. %

M.

D'

=

a ;y* e.,

i D

- E S E b.

O

  • O y

g C

gt s

w p

t;j y;-

  • C d : O no u o, G

, m et %

r* O u

on O C 2 O % *.-.

  • C, r "W **

o e

M

  • e

. e a*

n o

o

.a O c- -

a

    • M
  • 4 w
s p ty g*

.x H

.o o,

W D :* ' O +. -

  • n

+ e-w.

..e a o O et*M o

p Q :.' M ::.,

, 5

.+

O.4.d 37 a M d C G

C

/

w Q C q p

p c.,

T G

M

'A ' e O *** C a

U ;* O C**

I o -' ce y

j h

r* r -n

~

s-th gj

~ ~ -

s O

y e

e-t* a" p e,

s-

. " - ** O O M

g

- tv n'

. -s

~

O -

L.

. *: y cg j

g y

O v :.

C.. N O

wq o,

.D..

w

?

'1

  • ? O L F -

i y

P "' f

  • J2 c*
  • a O

.*)

U D 6

1. '

O N

'"" f* :.. Q **2. '

s L

O O

V.

9 2

r.*

AA M

U l'

-1 il G

  • )
  • 1

= :P o

  • rj C ^

o

~

r

~

w a

  • O H

ct O

0*

C C < ;;

a

.'. 7 E Q

- w

~

n M

.u ta, p 79 j ~

t-J p

a w. :

a e

T

~ D :.,

~~ %

O r'

-*p, g

3, n

g 0

r* Q =

C n L :. At

,,-; g O

O

-< r* O p < r o

4 M T "b

c-e,

-e n n

e, -

n

.g_

  • 1&

. :: w

- a c-

  • ~*

pm L' m-a r* O O J e ~,

  • % np 9 y O **

v*

? et

<. pmc

.-- Q g

t a

C r* :"r e :;, c-M r y

.. w ej M e

-r z-p.a n O O O

  • U 0

.G 5 o O

*9 ha o 72 L o - -, o D @a

(: c+ 2

  • ?

C'" O w

e a

]

m 0 O O ::: *

'a' wm u

O O

CD uo

nar, P o4 O
  • 1 O O O *c e m
  • '*a td t1 w

A 4

  • 3 p qm s

e'

  • a O 5 y

P c

O C U" M.

  • O O
  • 1, O N et M H

H' PM p' 6 ;

c' C,-

n e-o AO C* M O' ^

  • 1
? q D' *1 O

5 ag ;

Og D'

HW O P O G M O

  • a >a o n
v. T N

(Q O M V

P a y C* Q C et re M M 41 0 7.:.. n

.An e

O n

7s, i D rt M

cyy

=4 i HO Q*

wQ PO U

.1

.p O'D w.

m o

e e et C

c

  • +J M

-- n.

.m-

Bases Continued:

3.7 A.

Primary Containment If a loss of coolant accident were to occur when the reactor water temperature l's below 330*F, the containment pressure will not exceed the 62 psig design pressure, even if no condensation were to The maximum allowabic pool temperature, whenever the reactor-is above 212*F, shall be governed occur.

by this specification. Thus,'specifying water volume-temperature requirements applicable for reactor-water temperatures above 212*F provides additional margin above that available at 330*F.

l l

1 e

e e

M 157A:

Bases:

4.7 A. Primary Containment The water in the suppression chamber is used only for cooling in the event of an accident; i.e.,

it is not used for normal operaticn; therefore, a weekly check of the temperature and volume is adequate to assure that adequate heat removal capability is present. For additional margin, these will be checked.once per day.

The interiors of the drywell and suppressicn chamber are painted to prevent rusting. The inspec-tion of the paint during each major refueling outage, approxinately once per year, assures the paint is intact and is not deteriorating.

Experience with this type of paint inlientes that the inspection interval is adequate.

Because of the large volume and thermal capacity of the suppression pool, the volume and temperature normally changes very slowly and monitoring these parameters daily is sufficient to establish any temperature trends, By requiring the suppression pool temi crature to be cont inually monitored and frequently logged during periods of significant heat addition, the temperature trends will be closely followed so that appropriate action can he talen. The requirement for an external visual examination following any event where potentially high loadings could occur provides assurance that no significant damage was encountered.

Particular attention should be focused on structural discontinuities in the vicinity of the relief valve discharge since these are expected to be the points of highest stress.

Visual inspection of the suppression chamber inclu ling v.ater line regions each refueling outage is adequate to detect any changes in the suppression chamber structures.

The primary containment preoperational test pressures are based upon the calculated primary containment pressure response in the event of a loss of coolant accident. The paak drywell pressure would be about 41 psic, which uould rapidly reduce to 25 psig within 10 seconds follow-ing the pipe break.

Following the pipe break, the suppression chsmber pressure' rises to 25 psig within 10 seconds, equalizes with drywell pressure and thereafter rapidly decays with the dry-well pressure decay. See Sect;on 5.2 3 FSAR.

The design pressure of the drywell and absorption chrenber is 56 psig. See Section 5.2.3 FSAR.

The design leak rate is O.5%/ day at a pressure of 56 psig. As indicated above, the pressure resIsonse of the drywell and suppression chamber following an aceident would be the same after about 10 seconds. Based on the calculated centsinment pressure response discussed above, the

~

primary containment preoperational. test pressures were chosen.

Also, Lase <1 on the primary containment pressure response and the fact that the drywell and suppression chamber function as a unit, the primary containment will be tested as a unit rather than the individual compo-nents separately.

161

a k

s f

r r

i Bases Continued:

4.7 A.

Primary Containment

.i l

The design basis loss of coolant accident was evaluated at the primary containment maximum i

allowable accident leak rate of 1.5% day at 41 psig. The analysis showed that with this leak i

4 J

s i

i

?

1 I

j

'I 1

l j

=

h 9

1 1

l 161A f

Tg-~t+=--m ir y+r-m a-ww&6-v

,ow-m1 etg y3.M7-e--'m--e-m,-s

+--Ww g-3 egm y-mM-p'e+

%,-eymV.-eg-e q-m1%v+ M ity ytM-

-'qp_-

p

- wg-y..

-1gg M T

    • tr n y ' St ig-

"* " ' =" p

'M F

W

"&77M T5--T'*'T V

7-7