ML20236F674

From kanterella
Jump to navigation Jump to search
Amend 8 to License NPF-36,changing Tech Specs Re Location of Two Meteorological Towers
ML20236F674
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 10/19/1987
From: Butler W
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20236F650 List:
References
NUDOCS 8711020259
Download: ML20236F674 (12)
v • d • e


Text

't v -m

]y ;#

p

,,r m

g,, -

L

. [ UNITED STATES j

.j[

p.4

4
NUCLEAR REGULATORY. COMMISSION,:

1

g,,

Q WASHINGTON, D. C. 20665 ;

ii

-? (...;. 45 l

LONG ISLAND' LIGHTING' COMPANY' 4

j DOCKET NO. 50-3223..

SHOREHAM NUCLEAR POWER STATION AMENDMENT-TD FACILITY OPERATING LICENSE' l

M AmindmentlNd.: 81..

LicenseNopNPF-36l j

3 1.

The Nuclear Regulatory Comission (the Comission) has;found(tha'tj j

1:2....

d A.

The! application for amendment by Long; Island: Lighting Company a

A L

(thelicensee),'datedJanuary:12,.1987,' complies with the. ~

standards and requirements of theJ Atomic Energy Act of 1954, as::

- amended (the Act), and> the Comission's rules.and?regulationsiset.

forth in.10 CFR Chapter I;1 B...The facility will. operate,in cohfomity With)the1 application,ithel provisions.of the Act, and the rules and:regulationstof the 1

Comission; 1

C.

There is reasonable.assur'ance (i)"that thelactivitiestauthorized by;

.)

this amendment can be conducted.without endangering the health and E.

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).

s q

defense and security or to the.healthiand: safety of the;public;: and-E.

'Theissuance'ofthisamendmentisinaccordancewith!10'CFRPart51 1

of the Comission's regulationscand all applicable.requirementsLhave ~

R been' satisfied.

2.

Accordingly, the license'is amended by changes to theITechnical Specifications l

as indicated in the attachment to this license. amendment, sand; paragraph 2.C.~(2);

of Facility Operating License No.1NPF-36._is;hereby amended to read as;follows:

j Technical' Specifications j

The TechnicalJSpecifications contained in;Ap'pendix'A'and the' l

Environmental: Protection. Plan contained fin: Appendix l B,Las revised

~

U N

through Amendment No..8 are.hereby incorporated into5thislicense.

Long; Island Lighting Company shall? operate:the;facilityLint n

accordance with the Technical Specifications:andithe Environmental; Protection-Plan.-

4 1

Op d

7 p

7

~

.=

"' =

n,

h'h.

j.

f.

I l

(---

Ap,

/

, /

q;g, y;

, h,.

  1. ;]W,1

=' '

s

,s i

G.hi.' _ !; r

.M j

z,,

r a

l

'\\)

,'g-'

h s

m_.,

' Jy f&

]'l '

_ { \\

e :-

t _

k (\\ ?!

4 L

i

'y. '

.a Mk$, h [,.',

N I.,

t, p i- [ ',

4

.f

/, 1

...j.

..h, s

(

')

i J

,,r;

,Y m

m

,, ik I[. :$

r d,.,

t.r-t J

t.

c w.

,3.

.2

.o e a

.gs r

h-

.I.

i'

. ~...., -.,

,5

,f3.V OTh~isilidense amendment is' effective 'astof11ts datetofdssuance.z A,

p 4

s.

)

g j

r

.,,,,r c

1 g

FOR ;THE NUCL EAR. REGUL ATORYJ COMMISSION !

~

d y<

w g

s..,

1 f,'.;M, W, ' '

(;w 6,

J6

.-Q._,.

i..

?t' s

s'.

3

, 1/s/

L Q

~

.. ~...

w

,Walte'ri R. T Butleri; Director (,

W eProject. Directorate?I-24....n e/.

G-W0 d

~

' Divisionlof Reactor 1ProjectsEI/IIi*

),

f

, s. <.,..

- w@,

1 J d y

Attachment:

l 1,

+

Changes:to theLTechnical i

iSpecificationst 67

'M Oimd r

Y"'

p L

Date ofrIssuance:1 October!19, 1987 n

~

(

t 't l

4 4

5 q

Mh

'I ' -l

[ 9,.,

t -

g q.

g l=

i s

\\

n.,

1 :.

.~

+

1

~

w c,

c i.

+

-a$.

L 9

s3

.i..

/'

n r-t

?

1' i

h ?'

Y' l

V i

s

,9 -

), '

i t

. ', y,, ; a. cp g.

8 e

.t.

1 1

m'-

r 1

'N.

)

1

,e 9

.e 9

p 1

C2 a

t

,q c

\\

<w.

..~-

- g c:p 1.j i

r s

-r

f. )

m i -

,,n y:. 2 d]

2 lg

V 1

e

..; g; PD PDI-2/

OGC zPDI-2/D E

s 1

i

' WButler RLo:c p [87E l0/ [ 87-7 jo/f/87;.go /gja7_."

b:, <

+,1 c-0 1

,s i

l, __

l' t.

s

. +., ;p ;

1

<,, r 4

[.,"

3 f

t el f.

2 ilp?

W-4 n!r 79

~,

^

~.l.;

A&

$ i! 7'*"

g,.

1, )! <. c: ( ' 4 j% r ~, Q[ ff T - c "n ,~ Se s - 4 7 y isn:r-- s - -i <'n';

J + .. 2 - 3. This. license amendment is effective as of its date of issuance. FOR THE. NUCLEAR PEGULATORY COMMISSION' L Walter R. Butler, Director.c Project Directorate I-2 Division of. Reactor, Projects 1/II

Attachment:

Changes to the Technical Specifications Date of Issuance: October 19, 1987 -l 'l

' :1 3. u'- ( y. k ATTACHMENT TO LICENSE. AMENDMENT NO. 8 FACILITY OPERATING LICENSE.NO. NPF-36 [ DOCKET NO. 50-322 1 Replace the following pages of the Appendix "A"1TechnicalJSpec'ifications with' the' attached pages. The revised pages are identified by Amendment number ands contain vertical. lines. indicating.the area of change. Overleaf pages provided " ' to maintain docurrent completeness.*' 'i Remove Insert-1 5-3 5-3L il 5-4* 5-4* l-5-5 5-5' 5-6* '5-6* 5-7 5-7 t 5-8* 5-8* 6-5* 6-5* 6-6 6-6 l l 1 1 i t a l .I j l. t-J.-' : ^'

L0NG / S L A N-D S O U N D. oY b f 7.. P$EKfNG l --],o N \\ 's f \\ \\ 5-K NG P Y I BARGE 'in*e8h" sw ^ ,EL - 2.O' \\ g tQ 'N W % p)V2 e ~L $ $$o omet I E l stos. g w f CO,gR L E x w*0# 4;e l s f / ,.~. 4 Mg EL.H.0*. / 'g )s Fow"! ' **^' 33 poot m SHORENAM - UNIT 1 5-3 Amendment No. 8- = _ _ - _ - _ _ _ _ _ _ _ _

7 , g-y. 1 z q m., .g - s.n.w I g, I. \\ t i .f .{ ~ l 9.{' A gb 4.t p'&, ?.'! . /. $.\\xY, < I [. - d. 'p i.

    • +,

'\\ 11 1 s'$1 ) ' ?.T .{ 3: ,.On 3. Q*.Of c> .nu -' Yj ' +.gL $1 c.n.x .....r c 4 e ~ .{ ~ ~ x-4 i e 1 H. 0 .,Q4 ~ 3 k l r,, hb 'e T1 ?. h,,O. u~y

w, -

s a y{ggy, dd g g$ l Il. ;g /. S,*67@r. f, N, e 9L 1 =, g ui l ..,,..a_

n..,.,. - w.a a

,. A..w . g... Ty of s w_e.. ;... 9 w 2 w j j 4, 91. i'y ,g.,j, p$%.% g .p A )J p- ).. e.,i 4.' 9l.,p; i ; W h f' = y s=

'.- ~ s\\

y 2 e

z..., m,

I r4 i,.g . j,g ~- ~i ~ ' ' ' g. ftf ,1 ~ i .f 'i j . s-e x s I. o. E. I. p [. s i d b) i . &_?bhkh*.E5 SHOREHAM - UNIT-1 5-4 l p

l. W ~ ,,6 a na. 1g 4 soir*8 y g r ***. ",h j, h-~. i f n=;=:::r6 a ? 'l _ '*? ) /+ F i I' ~} l !/ I g? ,( / 5p7% 1 e

  1. h o"

ps ?, k t' f 9 V .g*

fkf, 3

\\,. ^ b. f.d w / 6 f l.~,,)f N- { . c.- t q mm ?&*Wf ) \\ y C) / ~ ~...

  • k' G *
  • ll.

b ~ ~;

  • T."',,,,,,,,,

H h- ] i G: LOCATION PLAN xgy pus ~- T$'deohn, y 6,: dM i SITE BOUNDARY FOR RADIOACTIVE GASEQUS AND LIQUID EFFLUENTS FIGURE 5.1.3-1 SMORENAM'- UNIT'1 5-5 meerdment 2. ' 8L 1

DESIGN FEATURES 1

5. 3 REACTOR CORE FUEL ASSEMBLIES e #w@+ ~/4 %.co' 5.3.1 The reactor core shall contain 560 fuel assem&ttes.3withieadhtfuel' I

assembly containing 62 fuel rods and two water rods clad with Zircaloy-2. -{ Each fuel rod shall have a nominal active fuel. length of 150-inches. The:. . initial core loading shall-have a maximum average enrichment of 1.90l weight percent U-235. Reload fuel.shall be similar.in physical design;to the initial 1 core loading, j 1 4 CONTROL ROD ASSEMBLIES i 5.3.2_ The reactor core shall contain 137 control rod assemblies, each-l consisting of a cruciform array of-stainless steel tubes containing=143 inches j of boron carbide, 8 C, powder surrounded.by a cruciform shaped stainless steel j 4 J sheath. 5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE l 5.4.1 The reactor coolant system is designed and shall be maintained: In accordance with the code requirements specified in Section (5.2)' I a. of the FSAR, with allowance for normal degradation pursuant to the i applicable surveillance requirements, i b. For a pressure of: d 1. 1150 psig on the suction side-of the recirculation pump, 2. 1325 psig from the recirculation pump discharge to the' outlet side of the discharge shutoff valve. 3. 1325 psig from the discharge shutoff valve to the jet pumps, c. For a temperature of 562*F. VOLUME 5.4.2 The total water and steam volume of the reactor vessel and recirculation system is.approximately 16.410 cubic feet at a nominal T;y, of 533*F. gp gWh I L .SHOREHAM - UNIT 1 5-6 .__[._____.__________._______________________________._ _'s__ ____m____

. -.__3..-.~_--.-._n_._....__-._._-_... 4 1, k u_ ___,.s DESIGN' FEATURES 5.5 METEOROLOGICAL TOWER LOCATION ~ f - 5.5.1 The 33 foot. meteorological tower shall;be located as shown on Figure 5.1.1-1. -The 400Lfoot. meteorological tower shall,beflocated as shown' on Figure 5.1.3-1 5.6 FUEL STORAGE CRITICALITY 5.6.1 The spent fuel storage racks-are: designed and sha11Lbe maintained with: A k,ff equivalent to less than or'equalito 0.95 when; flooded with-a. ~ unborated water, which indludes a ~ conservative allowance of:1.0%i delta k/k for' uncertainties'as described in Appendix 9A ofithe FSAR. b. A nominal 6 inches inlone direction a'd 9.25 inches.in the other. n direction center-to-center distance between fueliassemblies. U placed in the storage racks. 5.6.1.2 The k,ff for new fuel for.the first core loading stored' dry in the ~ spent fuel storage racks'shall'not exceed 0.98 when aqueous moderstion-is assumed. DRAINAGE 5.6.2 1he' spent fuel storage pool _isidesigned and shall be maintained.to prevent inadvertent draining of the pool below elevation 152'-4 ". - Os ~1E ^ CAPACITY ** 5.6.3 The spent fuel storage pool is designed and shall:be. maintained with a storage capacity limited to no more than 2176 fuel assemblies.- r 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT-5.7.1 The components identified in Table 5.7;1-11are designed and shall-bes maintained within.the cyclic or transient-limits of Table 5.7.1-1. L

a. * *w (

9.]

SHOREHAM - UNIT 1 5-7 Amendment' No.; 8 L m

WO s P r e L t A a M e R d h E n 'r T -a H F 0 t D 3 e 0 7 a E 9 w T e o d A t e R e o - ~ F f f t ET o LN 0 l dg ei CE 6 l YI 5 a 0 zs CS ~ ip N o f o r NA t o t u0 s5 GR s' s2 I T F S - s 0 e1 S ER 0 o 0 r; T DO 7 L 1 P< I M I L TN E I 1 S N s 1 A e R l d 7 T c n y a 5 R c O e E n s r L C w e u B I o s l s A L d e c s T C l l y e Y o c c r C ,T o y p I c c p c T M i N RI d e r i E OL n g t t N a n t. a CI a r e O 2 P I N p h o ss M LE u c t ot O CI t c 'rs C YS a p a d e CN e e e yt - A h t r h R s_ k T 0 0 0a 2 0 8 3 e 1 8 1 1 l. 1 TN E r N o O t P c M a O e C R w g =: g E ' c 3 " w T. ^ i

. c _= - . h. ) ' ,p,. -H ] i ,Q 4 j 'g .g y, t m i 1 g 5 r m l . TABLE 6J2.2 C -y N l MINIMUM SHIFTICREW COMPOSITION ~ E .i SINGLEruNIT" FACILITY: i' h.y NUMBER'0F INDIVID'UALS REQUIRE 0 TO FILL POSITION! T S ~ i -POSITION- ~ . CONDITION 1, 2, or'3 CONDITION 4 Lor 5' 1 ..;j 1 4 o WE: L1- -None:

SRO'
1:.

21; 1 R0 12 EO-2 . 11 STA 1 lNone:- ~ 'l s, TABLE N'OTATI'ON, L Watch Engineer with-a Se'nior Reactorc0perators license lonLUnit 1.- WE SRO - Individual with a Senior Reactor Operatorsilicense on: Unit'1. u H Individual with a Reactor-Operators license on Unit 1. RO Equipment' Operator M a EO STA - Shift Technical Advisor Except for.the Watch Engineer, the shift crew composition may befone less/than. H the mi'nimum' requirements of Table 6.2.2-1.for a. period'offtime;not)tofexceedl2 hours in order to accommodate unexpectedJabsence ofion-duty; shift: crew members" provided immediate action is.taken to. restore the.shiftJerew composition:.to ,3 within the' minimum requirements of Table:6'.2.2-1.. This' provision does not-permit any shif t crew position tolbe-unmanned: upon 'shif t chanoejdue' tojan) oncoming shift crewman beingl late or' absent. Ouring'any absence..of'the Watch Engineer from1the control roo'm whileithe' unit- ~ is in OPERATIONAL CONDITION 1. 2'or 3,.an individual-(other.-than the Shifts.. a Technical Advisor) with a ' valid.: Senior Reactor: Operator license)shall bejdesig-" 3 nated to assume the control room command function; During any absence of<the. Watch Engineer from the control."roomLwhile the unit-is in' OPERATIONAL' CONDITION.'4" or' 5~, an individual with a valid:Seni.or' Reactori0peratorLlicense: or:. Reactorc Operator: license shall be designated /to" assume?the control ^ room command function, l-SHOREHAM - UNIT l' 6h5~ p ;.a 1 5 _.j l __._.____m_ m_ _ _ _ _ __ m.i.' 'l (

}, uw y. p ', 'fy f m e i 4 a ? ADMINISTRATIVE CONTROLS 1612'.3" INDEPENDENT SAFETY ENGINEERING' GROUP (ISEG)- -FUNCTION . 6.2.3;11The TSEG 'sh'all' function 1to' examine unit: operating. characteristics,- NRCissuances",fi'n'dustryadvisories,ohicenseeEvent:Reposts,andother.' sources?, of unit design and. operating; experience.information, includingiunits of'similar. J design,-which may indicate areas for improving unitisafety. The,ISEG;shall, 'make detailed recommendations for revised procedures -equipment;modificatic"ns,_ maintenance activities, operationt<acti,vities'or other means'o.f improvingzunit safety,to the Director,(Quality Assurance, Safety and Compliance; '~ 1 1 COMPOSITION -The ISEG shall be composed of at le&st.five,'dedihated,l multi-; i + 6.2.3.2 . discipl.ined, full-time engineers located: onl site..; Each shall :have:a' bachelor's 1 l-degree in engineering or related science,1or: equivalent, land'at least'2 yearsi - professional experience _in his field,;at,least 1,yearLof which experience;shall be in the~ nuclear field. RESPONSIBILITIES 6.2.3.3 ~The ISEG shall'be responsible for. maintaining surveillance of unit ~ + activities to provide independent. verification

  • that-these; activities-are'per--

formed correctly and that human. errors 3 are reduced'as much as practical. Ny RECORDS i i 6.2.3.4 Records of activities performed by the IS'EG shall:be prepared,' main-tained, and forwarded each calendar month to the; Director,-Quality Assurance, Safety and, Compliance. 6.2.4 SHIFT TECHNICAL ADVISOR 1 6.2.4.1 TherShift" Technical,Advisorshallprovideadvisoryitechhicalsupport to the WatchiEnginder.in the' areas:of thermal' hydraulics,: reactor engineering, and plant analysis with regard to safe operation of the unit. The Shift

  • l l

Technical Advisor.shall have a bachelor's' degree or_equivale'ntLin'.a scientific < or engineering discipline and shall have' received specific. training'in theJ response and analysis of the unit for transients andiaccidents,;and in_ unit' o design and layout, including the capabilities of instrumentation'and: controls' in the control room.- ] 6.3' UNIT STAFF QUALIFICATIONS 6.3.1 Each member of-the unit:stafffshal'1 meet ortexceed thelminimum qualifi.- ~ cations of ANSI N18.1-1971 for comparable. positions and the: supplemental;. requirements'specified.in SectionsiA andiC;.of Enclosure 1Lof the March 28, 1980 NRC letter to all licensees..'except for:the Health Physics.: Engineer who shall: -[ meet or exceed the qualifications-of Regulatory Guidefl.8,:Septemberfl975. L The licensed Operators and Senior 10perators sha114alsoTeeeteor exceed the mini-- num' qualifications of the supplemental requirements specified in:. Sections A. and C'of Enclosure 1 of the March-28, 1980;NRC)1etter.to all licensees.,

  • Not' responsible for sign-offLfunction.-

I -6 Amendment mo; 8f SH0REHAM - UNIT _l' 6 t b 6 g}}

Retrieved from "https://kanterella.com/w/index.php?title=ML20236F674&oldid=3939711"