ML20065R979
| ML20065R979 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/20/1982 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Toledo Edison Co, Cleveland Electric Illuminating Co |
| Shared Package | |
| ML20065R982 | List: |
| References | |
| TAC 48403, NPF-03-A-048 NUDOCS 8210290382 | |
| Download: ML20065R979 (7) | |
Text
.:=
x-a
=
[ piety \\
UNITED STATES p
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
e.,, e
- THE TOLED0 EDISON COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 U
DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 o
AMENDMENT TO FACILITY OPERATING LICENSE J
Amendment No. 48 License No. NPF-3 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by The Toledo Edison Company and The Cleveland Electric Illuminating Company (the licensees) i dated May 5,1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application,
,1 the provisions of the Act, and the rules and regulations of
}
the Commission; J-C.
There is reasonable assurance (i) that the activities authorized J
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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and J'
E.
The issuance of this amendment is in accordance with 10 CFR Part I-51 of the Commission's regulations and all applicable requirements I'
have been satisfied.
V e
i L
i 8210290382 821020 a
DR ADOCK 05000346 P
. -. __.. - _ _..... ~ -.
l
.? ; <.
1,
-2 2.
Accordingly. Facility Operating License No. NPF-3. is hereby amended as indicated below and by changes to the Technical Specifications as indicated in the attachment to this license amendment:
Revise paragraph 2.C.(2) to read as follows:
l l
Technical Specifications The Technical Specifications contained in Appendices A and B as revised through Amendment No. 48, are hereby incorporated in the license.
The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effectiv'e as of the date of its issuance.
R THE NUCLEAR REGULATORY C01911SSION
/ A J6
. Stolz' Chief Op trating Reactors Branch #4 irision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 20, 1982 l
..N1<NUCN'Y,s ',,
--;- _ i 4 ~~' (%.T, e, g 7 - - L.
= ; T '--...
'L.
F n&
T I
- ] _v.'
.n "
-T sT
w-,
=-
~
i...
=~ 2
+v.-
ATTACHMENT TO LICENSE AME?M ENT NO. 48 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 L
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment nunber and contain vertical lines indicating the area of j
The corresponding overleaf pages are also provided to maintain change.
doctanent completeness.
[
Pages 3/4 7-2 r
B3/4 7-1 i
i l
l I
I o
i I
i rf i
.=.
_c
_a_
1
[
3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line code safety valves shall be OPERABLE.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
With one or more main steam line code safety valves inoperable, operation in MODES 1, 2 and 3 may proceed provided, that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to OPERABLE status or the High Flux Trip Setpoint is reduced per Table 3.7-1; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.1.1 No additional Surveillance Requirements other than those required by Specification 4.0.5, are applicable for the main steam line code safety valves of Table 4.7-1.
1, l
j DAVIS-BESSE, UNIT 1 3/4 7-1 5
)
n d
g.- - g =s:, a g a-w =, _...
m-
= ~ ~
s h',
3 11 g..r f.
g TABLE 3.7-1 4'g -
- 5 MAXIMUM ALLOWABLE HIGH FLUX TRIP SETPOINT WITil INOPERABLE un I
g STEAri LINE SAFETY VALVES y
v, IJ Q
i h
Maximum Allowable l
.j Maximum Number of Inoperable Safety High Flux Trip Setpoint*
8 d
.[
-4 Valves on Any Steam Generator (Percent of RATED THERMAL POWER) g Q
1 0.95W
, t;
~
i ti-t
- .f
$ *4 y
2 0.82W k
i 3
3 0.69W 3
9 3[
w t
I4 1
2 4
0.56W r,
y A,
i lf.
c a
M 5
0.43W Q
m Ul k
O.31W 6-in
=
((.:
a 7
0.iaW
.i; i[
I b,
'W j
3 i'
f6.
j
- Based on High Flux Trip Setpoint for four pump operation. W. as per Table 2.2-1.
t
- \\
h
.i i!
\\n
. iC i.
- s. E
' lI
~
_~~'
r
=__3
~f
~,
1: 1' ~.
.. _a 3/4.7 PLANT SYSTEMS BASES 3/4.7.1 TURBINE CYCLE
~
3/4.7.1.1. SAFETY VALVES The OPERABILITY of the main steam line code safety valves ensures that the secondary system pressure will be limited to within 110% its design pressure of 1050 psig during the most severe anticipated system operational transient. The maximum relieving capacity is a,ssociated with a turbine trip from 100% RATED THERMAL POWER coincide.nt with an assumed loss of condenser heat sink (i.e., no steam bypass to the condenser).
The specified valve lift settings and relieving capacities are in accordance with the requirements of Section III of the ASME Boiler and 4
f Pressure Vessel Code,1971 Edition. The total relieving capacity for all valves on all of the steam lines is 14,175,000 lbs/hr which is 120 percent of the total secondary steam flow of 11,760,000 lbs/hr at 100% RATED THERMAL POWER. A minimum of 2 OPERABLE safety valves per steam generator ensures that sufficient relieving capacity is available for the allowable THERMAL POWER restriction in Table 3.7-1.
3
{
STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ACTION requirenents on the basis of the reduction in secondary system steam flow and THERMAL POWER required o
by the reduced reactor trip settings of the High Flux channels. The reactor trip setpoint reductions are derived on the following bases:
3p,(X) - (Y)(V) y Z
where:
H SP = reduced Trip Setpoint in percent of RATED THERMAL POWER (Not to Exceed W)
V = maximum number of inoperable safety valves per steam u
f generator 3
W = High Flux Trip Setpoint for four pump operation as specified
~
5 in Table 2.2-1
{
r X = Total relieving capacity of all safety valves per steam generator in lbs/ hour, 7,087,500 lbs/ hour Y = Maximum relieving capacity of any one safety valve in 1bs/ hour, 845,759 lbs/ hour Z = Required relieving capacity per steam generator in Ibs/hr, f
6,585,600 lbs/hr.
t DAVIS-BESSE, UNIT 1 B 3/4 7-1 Amendment No.48
?
.,w
.+-%
.A
- ./S-eAE L
"-**O^
m
=
PLANT SYSTEMS BASES I
3/4.7.1.2 AUXILIARY FEEDWATER SYSTEMS The OPERABILITY of the auxiliary feedwater systems ensures that the Reactor Coolant System can be cooled down to less than 280*F from normal operating conditions in the event of a total loss of offsite power.
Each steam driven auxiliary feedwater pump is capable of delivering L
a total feedwater flow of 850 gpm at a pressure of 1035 psig to the 4
entrance of the steam generators. This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than 280'F where the Decay j
Heat Removal System may be placed into operation.
I 3/4.7.1.3 CONDENSATE STORAGE FACILITIES
}*
The OPERABILITY of the condensate storage tank with the and to minimum uter volume ensures that sufficient water is available.to maintain the RCS at HOT STANDBY conditions for 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> with steam discharge to y
atmosphere and to cooldown the Reactor Coolant System to less than 280'F in the event of a total loss of offsite power or of the main feedwater system. The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other r
physical characteristics.
9
[
3/4.7.1.4 ACTIVITY D
The limitations on secondary system specific activity ensure that r
the resultant offsite radiation dose will be limited to a small fraction i
of 10 CFR Part 100 limits in the event of a steam line rupture. This i
dose includes the effects of a coincident 1.0 GPM primary to secondary i
tube leak in the steam gene.ator of the affected steam line. These
{
values are consistent with the assumptions used in the safety analyses.
{
3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVES f
The OPERABILITY of the main steam line isolation' valves ensures f
that no more than one steam generator will blowdown in the event of a
?..,
{
steam line rupture. This restriction is required to 1) minimize the f
I
[
a
(
h DAVIS-BESSE, UNIT 1 8 3/4 7-2 f,
3 nM,,_E;.;,adQ[37FzdE3 Ti$diMNE'OUAd@%6E W.'L'DMAWNI" a ' 5 *;df/-- I m.
. - ~ ~ ~ - - - ~. - ~ - - - ~ ~ - - - -. ~ - -
- - - - -