ML20148A961
| ML20148A961 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 01/04/1978 |
| From: | Goller K Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20148A955 | List: |
| References | |
| NUDOCS 8001160145 | |
| Download: ML20148A961 (10) | |
Text
h_
(;:.
~*qs.m terug#e CE-UNITED STATES
[::
g5 y
,},,,(g*7,
NUCLEAR REGULATORY CCMMisSIOi4
- 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
=
supplemented by filinos cated October 7 and 19,1977, November 1, L
L 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.-
l9 '
the Commission; 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=
E.
The issuance of this amendment is in accordance with 10 CFR Part i
51 of the Consission's reculations and all applicable requirements have been sa'.isfied.
l 99026114 ridedehib a
(:..
)
E"
..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.
amenciment and Paragraph 2.C(20 c'.. acility License flo. DPR-53 is
~ l hereby amended to read as feli:ns:
..I
~
(2) Technical Soecifications
']
The Technical Specificatfors contained in Appendices A and B, as revised throcgh Am. endment flo. 27, are i..
hereby incorporated in the ifcense. The licensee 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::
, =
- .5 N
1-maammme 90026115 l
' ~ ~ " '
- lll"
- .i ',,;;;.
i
(
- g t.
e j:j Er
~
ATTACFy.ENT TO LICE!!SE A'4END;4E!iT I 0.27 p::.:
FACILITY OPERATING LICENSE NO. DPR-53 4
~
..)
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 The number and contains verti:a1 lines indicating the ares of change.
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::
- A
--l
..,.i
..z
- .1 M
i=
";o 90026116 7
2:..:...
... - ~ -
~ ~ ' ' -. 1
- * ~ ~'
-~L'
^
l';;;;
~
~. ~.. ~.
g.
C.'.'
~,
DESIGN FEATURES Sif VOLUME 5.4.2 The total water and steam volume of the 9 actor coolant system is
' Eff 10,614 + 460 cubic feet at a nominal T Of 52F.
avg s-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.=
5.6.1 The spent fuel storage racks are designe: and shall be caintained 1===l with a minim 6:n 12.5 x 13 inch center-to-cen er :istance between fuel
...[.'.
assemblies placed in the storage racks to er: sura a k< 0.95 with the s e
~"
The k of 7 0.95 ir.cludes the conservative allowances for uncertainties deINibed
'i Tn Section 9.7.2 of' the FSAR.
In additier., fue* in the storage pool 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 will not exceed 0.98 when fusi *aving a maximum enricF. ent
,IE such that k,,fof 4.0 weignt percent U-235 is in place ar.d ac. ecus foam moderation is i
ass umed. The k_
of < 0.98 includes the c:nss vative allowance fcr uncertainties dEd, ribeli in Section 9.7.2 :f tre FSAR.
I.
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
_ Cyclic or Transient Lirit Design Cycle or Transient
,c._
_Co_mp_o_ne n t 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 10 Primary llydrostatic Tests 3125 psia and 60*F > tillTT c
-u 320 Primary leak Test,s 2500 psia and 60*F > NDTT Y'
Steam Generator 10 Secondary llydrostatic T.ests 1250 psia Secondary Side and tes'perature > 100*F m
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
!' '..l j
[
- 1
,I
/,
e
- \\\\ll, e
8
,tw nu
.w.
nw v
l
',8 1 uN TED STATES EU a
f, eM,%,., g/ 't, NUCLEAR REGULATORY CO?S tsSION E
.,2 4: E wAssirecTon, o. c. 2:555
~
- %:.:'. 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
.. = -
AfiENDMENT TO FACILIIY OPERATING LICEllSE E==
=
i!S zm Acencnent !!o.12 i.(Es License !!o. DPR-69 EEsf 1.
The Huclear Regulatory Cc aission (the Cennission) has found that:
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 if-4,16 and 17,1977, and December 7.,1977, :o :Diy with the stancords 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 -
l health anc safety of the ':ublic, and (i") -hat such activities r
(.
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 53 the public; and 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 E._.
have been satisn ec.
2 1._:.f
=
90026119
..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 i ;.sj
'j
, The Technical Specifications contained in Appendices 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 The revised pace is identifiec by Amandaen:
with the enclosed page.
The
. '::2 number and contains vertical lines indicating -he area of' char.;e.
corresponding overleaf page 5-6 is also provided to maintain document
=
[=E M
completeness.
No changes were made en 5-6.
'6.:..:.
=
Pace e=.-i
- ==
[5}
5-5
!==
ih.
~
n=4
}
- =
4 3.;< -
G O
L::.
V:::~::e1
.v.
I'TT]
=:M
- ."~'.
==::
":)
i 90026121 L
j.
/_
.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 of 532*F.
7 3yg 5.5 METEOROLOGICAL TOWER LOCATION _
- 5 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
g==
22=
5.6 FUEL STORAGE
=
CRITICALITY - SPENT FUEL l
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 to
< 0.95 with the storage pool filled with unborated wa The k of
.. E
< 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
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$b, percent U-235 is in place and aqueous foam The K of < 0.98 includes the cense-vative moderation is assumed.
allowance fer uncertainties d$s$ribec in Section 9.7.2 of -he FSAR.
_.. L DRAINAGE D&
.is=
5.6.3 The spent fuel storage pool is designed and shall t>e caintained 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 cccDined storage ca:acity, for b::n Units 1 ar.d 2, limi ec.: no more j
than 1056 fuel assemblies.
96026122 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.
CALVERT CLIFFS UNIT 2 5-5 Amendment No. II
TABLE 5.7-1 g
G m
COMPONENT CYCLIC OR TRANSIENT LIMITS s-n q
Component Cyclic or Transient Limit Design Cycle or Transient Y
~
Readlo'rCoolantSystem 500 heatup and cooldown cycles 70*F to 532*F to 70*F F.
!d i
400 reactor trip cycles 1001 to 0% RATED TilERMAL POWER
-8 w
10 Primary llydrostatic Tests 3125 psia and 60*F > NDTT 320 Primary Leak Tests 2500 psia and 60*F > NDTT US l
5.
Steam Generator 10 Secondary llydrostatic Tests 1250 psia Secondary Side and 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"
~~
a:
s g-B i
o ll s
o, N026123 t
. : w n, ___ - ______ _ ___ __,.
,nn m.yp_l e,,.
nn nu m
_