ML20148A961

From kanterella
Jump to navigation Jump to search
Amends 27 & 12 to Licenses DPR-53 & DPR-69,respectively, Replacing App A,Page 5-5 W/Encl Page to Allow for Increase in Spent Fuel Storage Capability Up to Max of 1,056 Fuel Assemblies
ML20148A961
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 01/04/1978
From: Goller K
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20148A955 List:
References
NUDOCS 8001160145
Download: ML20148A961 (10)
v • d • e


Text

CE-(;:. '

h_

~*qs.m terug#e UNITED STATES [::

g5 NUCLEAR REGULATORY CCMMisSIOi4 y ,}, ,,(g*7 ,

7. MG/. g E WASHINGTON. D. C. 20:55

.{o <

.c - -

BALTI!10RE GAS & ELECTRIC C0P.PANY .=...

- DOCKET N0. 50-317 -

CALVERT CLIFFS tlNIT NO.'1 ,

5 NEISENT TO FACILITY OPERATING LICENSE Amendment Ho. 27 r.c "

License No. DPR-53 g. . .

i.= ,

1. The !!uclear Regulatory Cc= mission (the Commission) has found that: ,

A. The a)plications for amendment by Baltimore Gas & Electric Company =

(the licensee) dated August 5,1977, and September.7,1977, as L L supplemented by filinos cated October 7 and 19,1977, November 1, 4,16 and 17,1977, and December 7,1977, ccmply with the standards  :

- and requirecents of the Atoniic Energy Act of 1954, as amendec  ;

(the Act), and the Commission's rules and regulations set forth

~

f n 10 CFR Chapter I; . . 7

~

B. The facility will operate in confo'rmity with the applflation, ik the provisions of the Act, and the rules and regulations.of.-

- the Commission; ,

l9 '

C. There is reasenanle assurance (i) that the activities authorized by this arenc:ent can ce conducted without endangering the ,

healtn and safety cf the pubif e, and (ii) that such activities ,

will oe concucted in compliance with the Commission's regulations; -

D. The issuance cf this amendment will not be inimical to'the common defense and security or to the health and safety of the public; and  :

E=

i E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Consission's reculations and all applicable requirements have been sa'.isfied.

l 99026114  :

ridedehib a .

(:. .

)

' E" .

l

.L E. _

2. Accordingly, the license is a.2nded by changes to the Technical' ".

.m Specifications as indicated i= t a attachment to this license i.

~l amenciment and Paragraph 2.C(20 c' .. acility License flo. DPR-53 is hereby amended to read as feli:ns: ~

. .I i

(2) Technical Soecifications '] ,

The Technical Specificatfors contained in Appendices  !

A and B, as revised throcgh Am. endment flo. 27, are  !

hereby incorporated in the ifcense. The licensee i ..

shall o;;erate the facility in accordance with the ,-

Technical Sr.ecifications. .

3. This license amendment is effec-ive as of the date of its issuance.

FOR T.-E Et 0 LEAR ?.EGULATORY C0fE11SSIO!! .

\ ~~W Karl L Gcller, Assistar.t Director for 0;serating Reactors i Divisico of Operating Reactors i

Attachment:

Chang.es to the Technical .

Specifications . . .

. ['

Date of Issuance: January 4, 1973

[h c::

=

N

.5 1-maammme ,

90026115

' ' " ' ' ~ ~ " '

  • lll"  ::,,.;. .. . .  ;.i ',,;;;.  :::;;;;
  • l  ::':.

':> . ' i

(. . . :g

  • e t.

Er j:j

~

- ATTACFy.ENT TO LICE!!SE A'4END;4E!iT I 0.27 p::.:

~ 4 FACILITY OPERATING LICENSE NO. DPR-53 ..)

DOCKET !!0. 50-317 Replace the following page of the dppendix "A" Te:hnical Specifications

  • with the enclosed page. Tne' revised page is identified by Amendment number and contains verti:a1 lines indicating the ares of change. The correspending overierf pa;e 5-6 is also prcvided to maintain document -

completeness. i;o changes were made on 5-6.  ::.

~:

Page 1 5-5 . r::

.1
A

--l

  • ..,.i
  • . .z

,  :.1 M

i=

";o 90026116 7

...-~-

^

~ ~ ' ' -. 1 * * ~ ~' -~L' l';;;; ,,;;. . .. 2:..:. . .

~

~.~..~.

. g.

C.'.'

~,

DESIGN FEATURES Sif VOLUME 5.4.2 The total water and steam volume of the 9 actor coolant system is ' s- Eff 10,614 + 460 cubic feet at a nominal T avg Of 52F.

I..

5.5 HETEOROLOGICAt. TOWER LOCATION ,

5. 5.1 The meteorological tower [shall be located as shown on Figure 5.1-1.

5.6 FUEL STORAGE , . . ...

ifu CRITICALITY - SPENT FUEL j.=

The spent fuel storage racks are designe: and shall be caintained 1===l 5.6.1 with a minim 6:n 12.5 x 13 inch center-to-cen er :istance between e fuel . . .[.'.

assemblies placed in the storage racks to er: sura The ak k< of0.95 with the s

~"

'i 7 0.95 ir.cludes the conservative allowances In additier., fue* in the for uncertainties storage pool deINibed ....

Tn Section 9.7.2 of' the FSAR. i;; ,

shall have a U-235 loading of < 44.0 grams cf t'-235 per axial centimeter

~

il--

of fuel assembly. c%i CRITICALITY - NEW FUEL _

0 5.6.2 The new fuel storage racks are desigined and shall be maintained with .:

a nominal 18 inch center-to-center distan:e be:veen new fuel assemblies ,IE will not exceed 0.98 when fusi *aving a maximum enricF. ent .

such that k,,fof 4.0 weignt percent U-235 is in place ar.d ac. ecus foam moderation i is ass umed . The k_ of < 0.98 includes the c:nss vative allowance fcr I.

uncertainties dEd, ribeli in Section 9.7.2 :f tre FSAR. ,

1-DRAINAGE 5.6.3 The spent fuel storage pool is designed and shall be maintained I [= ...

to prevent inadvertent draining of the pool be'ow elevation 63 feet. ("~"

E 2

CAPACITY s...

~"

5.6.4 The fuel storage pool is designed arid : all be maintained with a combined storage capacity, for both Units i tr: 2, limited to no mere _

than 1056 fuel assemblies. ..

5.7 CCv70NENT CYCLIC OR TRANSII' ~ L:MITI 5.7.1 Tr.e ecm:enents identified in Tacie E .7 ' are designed and s .a'.i :e maintained witnin the cyclic or ransfer. i- :3 of Tabl e 5.7-1.

5- 5 A enc:er.: N: . 27 CALVERT CLIFFS - UNIT 1 90026117 - ..

y l

i l

l T..AB. LE 5.7.-1 h C0lli'ONENT CYCLIC OR TRAtlSIENT LIMITS m

n  : .. .

-i .

, _Co_mp_o_ne n t _ Cyclic or Transient Lirit Design Cycle or Transient

,c._

l

  • ~*

l ll itcactor Coolant System 500 heatup and cooldown cycles . 70*F to 532*F to 70*F l

. en ,

-. . , ,.c

.Ti 400 reactor trip cycles 100% to 0% RATED TIIERMt.L POWER ii i . a .

c 10 Primary llydrostatic Tests 3125 psia and 60*F > tillTT

-u 2500 psia and 60*F > NDTT 320 Primary leak Test,s Y' Steam Generator 10 Secondary llydrostatic T.ests 1250 psia Secondary Side and m tes'perature > 100*F i

320 Secondary Leak Tes,ts 1000 psia. Secondary Side With

- - Primary - Secondary Ap of 820 psi and shell side temperature between 100*F and !*

200*F l . .

. L f

j .  !' '..l

[ ,

  • 1 ,I

/, .

e

- \\ll, e 8

,tw nu

.w . v .; _ : , nw

l a uN TED STATES

',8 1 NUCLEAR REGULATORY CO?S tsSION EU f, eM,%

. ,2 4:,.,Eg/ 't, wAssirecTon, o. c. 2:555 E

  • ~
  • %:.:'. 4 / 4 G-

% .. n p y;_

!k

=r

.... = . .

.fE

..=.

BALTIliORE GAS & ELECTRIC C0"PA! Y -

- : n -;

=_.

DOCKET 1:0. 50-318 .Jg;

- k+2 CALYERT CLIFFS U!!IT HO. 2 jai

..=-

' E==

AfiENDMENT TO FACILIIY OPERATING LICEllSE

- ===

i!S zm Acencnent !!o.12 i.(Es License !!o. DPR-69 EE The Huclear Regulatory Cc aission (the Cennission) has found that:

sf

1. y A. The applications for amend:ent by Saltimore Gas & Electric Company 33 (the licensee) dated August 5,1977, and Septe:ber 7,1977, as  :=$

supplemented by filines cated Octo:cr 7 ar.d 19,1977, !!cvember 1, i=5 4,16 and 17,1977, and December 7.,1977, :o :Diy with the stancords .

if-and requirements of the At:mic,Enargy Act of 1954, as acended iL'_

(the Act), and the Cocaission's rules and regulations set forth :EZ in 10 CFR Chapter I; - 4E=

==

B. The facility will operate in confomity with the application, j=

the provisions of tiie Act, and the rules and regulations of #Es the Commission; g .=

C. There is reasonsole assurance (i) that the activities authorized E by this acendi.ent can De corcuctec vi-bcut encancering the (1 -

health anc safety of the ':ublic, and (i") -hat such activities r l

will be concucteo in conpliance with : e C:.r.ission's regulations; (.

l.... 4 D. The issuance of this amendment will not be ininical to the  ?:S common defense and security or to the health and safety of 55 the public; and 53 72 E. The issuance of this ar'endnent is in accordance with 10 CFP. Part M 51 of the Connissien's regulations anc ali applicable requirements Es have been satisn ec. E2 ._.

1._:.f l

=

l l

l 90026119 l l

1 l

-. ..L..

m . _

- G fC_ . [. i

. . F. -

6 iE

2. Accordingly, the license is acended by changes to the Technical j,ij . i

- Specifications as indicated in the attachment to nis licer.se p4 amendmenc and Paragraph 2.C(2) of Facility License i:o. CPR-69 is s' hereby amended to read as follows: , E-

=:

(2) Technical Soecifications

.sj

'j , The Technical Specifications contained in Appendices i A and B, as revised through Amendment flo.12, are q:

=

hereby incorporated in the license. The licensee shall operate the facility in accordance witn the Technical Specification,s.

- - 3. This license acendment is effective as of the date of its issuance.

, FOR THE !!UCLEAR REGULATORY Cor511SSIO!r

/. / 0 / .

\eM /f- (_7-2 .>W .

- Karl R. Goller, Assistant Director .  :

for Operating Recctors -

. Division of Operating Reactors -

Attachment:

Changes to the Technical .

Specifications ,

Date of Issuance: January 4,1978 i.:.:

=

t Ul Ei' '

- 96026120

p..

+m:g_

m.=

mi ATTACHMENT TO LICC'SE AMECMENT NC.12  :=:=-

rad!

FACILITY OPERATING LICENSE NO. DPR-69 ==E

. ==

DOCKET NO. 50-318 = =-

iiE?

E::=

E==

Repla:e the following page of the Aopendix "A" Technical Specificatier.s "T'E with the enclosed page. The revised pace is identifiec by Amandaen: '

number and contains vertical lines indicating -he area of' char.;e. The . '::2

=

corresponding overleaf page 5-6 is also provided to maintain document [=EM completeness. No changes were made en 5-6. '6.:..:.:

. ===

Pace e=.-i

.  :==

5-5

[5}

! ==

~

ih.

n=4

=

}

4 3.;< -

G O L::.

.v.

V:::~::e1 I'TT]

=:M

  • ."~'.

==::

":)

i 90026121 j.

L . . . . .- - - -

/_

.s ,

p.

DESIGN FEATURES VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 10,614 + 460 cubic feet at a nominal T 3yg of 532*F.

7 5.5 METEOROLOGICAL TOWER LOCATION _

5 g==

5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.

22=

=

5.6 FUEL STORAGE l

CRITICALITY - SPENT FUEL

[_

5.6.1 The spent fuel storage racks are designed and shall be maintained be.2 with a minimum 12.5 x 13 inch center-to-center distance between fuel e 1.M assemblies placed in the storage racks to ensure a k,Nr.quivalent The k toof .. E

< 0.95 with the storage pool filled with unborated wa

< 0.95 includes the conservative allowances for uncertainties dei,,Hbed c

in Section 9.7.2 of the FSAR. In addition, fuel in the storage pool shall =g

E have a U-235 loading of < 44.0 grams of U-235 per axial centiceter of fuel assembly.

~

- gfE Sl@

m CRITICALITY - NEW FUEL -

= . =_

1d 5.6.2 The new fuel storage racks are designed and shall be caintained ,'

)

with a nominal 18 inch center-to-center distance between new fuel assemblies such that X will not exceed 0.95 when fuel having a maximum i enrichment of 4.0 weig$b, percent U-235 is in place and aqueous foam  :

moderation is assumed. The K of < 0.98 includes the cense-vative "

allowance fer uncertainties d$s$ribec in Section 9.7.2 of -he FSAR. _.. L DRAINAGE D&

5.6.3 The spent fuel storage pool is designed and shall t>e caintained

. .is=

to prevent inadvertent draining cf the pool below elevation 63 feet. @

.s CAPACITY 5.5.0 The fuel storage pool is designec and snall be mair a'ned with a  ;

j

- cccDined storage ca:acity, for b::n Units 1 ar.d 2, limi ec .: no more ,

than 1056 fuel assemblies.

96026122 l) 5.7 CCMPONENT CYCLIC OR TRANS!ENT LIM:~5 5.7.1 The c:moonents identifisc in Table 5.7-1 are desig ec and shall be maintained within the cyclic cr transier.t '.imi:s of Tatie 5.7-1.

5-5 Amendment No. II CALVERT CLIFFS UNIT 2

g TABLE 5.7-1 G m s- COMPONENT CYCLIC OR TRANSIENT LIMITS n .

q Component Cyclic or Transient Limit Design Cycle or Transient

~

Y 500 heatup and cooldown cycles 70*F to 532*F to 70*F Readlo'rCoolantSystem F. !d i ..

-8 400 reactor trip cycles 1001 to 0% RATED TilERMAL POWER w .

10 Primary llydrostatic Tests 3125 psia and 60*F > NDTT 320 Primary Leak Tests 2500 psia and 60*F > NDTT US l

5. 1250 psia Secondary Side and Steam Generator 10 Secondary llydrostatic Tests

' temperature > 100*F l

' 320 Secondary Leak Tests 1000 psia Secondary Side With Primary - Secondary Ap of ,.

820 psi and shell side t i~,;

temperature between 100*F and 200*F h" ' '

s

~~

a: .

g-B i  ;. o . .

s ll o,

N026123 _

t _- _ .

__-.____;_... . : w n , ___ - ______ _ ___ __,. nu m

,nn nn e ,,.

m.yp_l _ __ _

-

Retrieved from "https://kanterella.com/w/index.php?title=ML20148A961&oldid=2849900"