ML20244C411
| ML20244C411 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/11/1989 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20244C413 | List: |
| References | |
| NUDOCS 8904200198 | |
| Download: ML20244C411 (10) | |
Text
,
t
.s I
' # "?%.
f UNITED STATES y'
1 NUCLEAR REGULATORY COMMISSION g
j WASHINGTON, D. C. 20555
\\
/
DUKE POWER COMPANY 1
NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 60 License No. NPF-35 1..
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the Duke Power Company acting for itself, North Carolina Electric Membership) Corporation and Saluda River Electric Cooperative, Inc.,
(licensees dated January 17, 1989, complies with the standards and requirements of the Atomic Cnergy Act of 1954, as amended (the Act),
and the Comission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized 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 set forth in 10 CFR Chapter I; 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 E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
8904200198B[ohis j
PDR ADOCK O pgy P
. = _ _
4
' 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment, ar.d Paragraph 2.C.(2) of Facility Operating License No. NPF-35 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendin A, asl revised through Amendment ?!o.
60, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
l FOR THE NUCLEAR REGULATORY COMMISSION Lawrence P. Crocker/for i
David B. Matthews, Director Project Directorate 11-3
-Division of Reactor Projects-I/II l
Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: April 11, 1989 l
1 l
0FFICIAL RECORD COPY r
PM:PDTI-3 NR.SPLD OGCMX PDII-3 LA:7pII-3 itf$M KJabbour:swhJCraig J 4 Leff d atthews 3gh /89 7 /t4/89 1; 3 /27/89 F/)</89
% / 7 /89 5
i,-
- /
o,j
= UNITED STATES NUCLEAR REGULATORY COMMISSION j
o 5
j
' WASHINGTON, D. C. 20655
\\
/.
DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENS Amendment No. 54 License No. NPF-52 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility) Facility Operating License No'. NPF-52 filed by the Duke. Power Company acting for itself, North Carolina Municipal Power Agency No. I and Piedmont Municipal Power Agency,-(licensees) dated January 17, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; l
C.
There-is reasonable assurance (i) that the activities authorized by l
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 set forth in 10 CFR Chapter I; 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 E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have
{
been satisfied.
L 1
l
.4 y..
2.
. Accordingly, the license.'is hereby amended by page. changes..to the Technical Specifications as indicatsd in the' attachments.to.this-license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-52 is hereby amended to'. read as follows:
L (2) :Techn'ical Specifications Th'e Technical. Specifications contained in Appendix'A, as revised-through Amendment No.
54,, are hereby incorporated'into the license.
The licensee shall operate the facility.'inaccordance with the
~ Technical Specifications and the Environmental Protection' Plan.
p 3.'
This license amendment,is effective as of its ' ate of: issuance.
d t
l FOR THE NUCLEAR REGULATORY' COMMISSION Lawrence P. Crocker/for David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
. Technical Specification Changes Date of Issuance:
April 11,'1989 0FFICIAL~ RECORD COPY D:PDII-3 tj.L-11 PM:PDII-3 NRR:SPLB-OG Mo KJabbour: sw JCraig f LMV
[Dfiatthews
. J/&/89
$/f4/89 3 /27/89 f/f/89 ef /7 /89 l
Y
_l______
L
[
ATTACHMENT TO LICENSE AMENDMENT NO. 60 t
FACILITY OPERATING LICENSE NO. NPF-35 i
DOCKET NO. 50-413 AND TO LICENSE AMENDMENT NO. 54 FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO. 50-414 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and.
contain vertical lines indicating the areas of change..The corresponding over-leaf pages are also provided to maintain document completeness.
Amended Page Overleaf Page 3/4 3-40 3/4 3-39 3/4 3-41 3/4'3-42 3/4 7-5 1
i e
__2_.________..
____1_
TABLE 3.3-5(Continued]
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 4.
Steam Line Pressure-low (Continued) 10)
Control Room Area Ventilation N.A.
Operation 11)
' Annulus Ventilation Operation 5 23-12)
Auxiliary Building Filtered Exhaust. Isolation N. A.
13)
Containment Sump Recirculation N. A.
b.
Steam Line Isolation 57 5 '.
Containment Pressure-High-High a.
Containment Spray 5 45 b.
Phase "B" Isolation 5 65(3)/76(4)
Nuclear Service Water Operation N.A.
c.
Steam Line Isolation 57 d.
Containment Air Return and Hydrogen
-< 600 Skimmer Operation 6.
Steam Line Pressure - Negative Rate-High Steam Line Isolation 37 7.
Steam Generator Water Level-High-High a.
Turbine Trip 13 b.
Feedwater Isolation 57 8.
T,yg-Low L
Feedwater Isolation N.A.
r 9.
Doghouse Water Level-High j
Feedwater Isolation N.A.
10.
Start Permissive Containment Pressure Control System N.A.
11.
Termination Containment Pressure Control System N.A.
l l'
CATAWBA - UNITS 1 & 2 3/4 3-39
4 7
TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 12.
Steam Generator Water Level-Low-Low a.
Motor-Driven Auxiliary Feedwater Pumps 5 60 b.
Turbine-Driven Auxiliary Feedwater Pump 1 60 13.
Loss-of-Offsite Power a.
Motor-Driven Auxiliary Feedwater Pumps 5 60 b.
Turbine-Driven Auxiliary Feedwater Pumps 5 60 c.
Control Room Area Ventilation Operation N.A.
d.
Emergency Diesel Generator Operation 5 11
- 1) Diesel Building Ventilation Operation N.A.
- 2) Nuclear Service Water Operation 5 65(3)/76(4) 14.
Trip of All Main Feedwater Pumps i
a.
Motor-Driven Auxiliary Feedwater Pumps 5 60 b.
Turbine Trip N.A.
15.
Auxiliary Feedwater Suction Pressure-Low Auxiliary Feedwater (Suction Supply 5 16(0)
Automatic Realignment) 16.
Refueling Water Storage Tank Level-Low Coincident with Safety Injection Signal (Automatic Switchover to Containment Sump)
$ 60 17.
Loss of Power a.
4 kV Bus Undervoltage -
58.5 Loss of Voltage b.
4 kV Bus Undervoltage-
-< 600 Grid Degraded Voltage 18.
Suction Transfer-Low Pit Level Nuclear Service Water Operation N.A.
CATAWBA - UNITS 1 & 2 3/4 3-40 Amendment No. 60 (Unit 1)
Amendment No. 54 (Unit 2) 4
I e
TABLE 3.3-5 (Continued)
TABLE NOTATIONS (1) Diesel generator starting and sequence loading delays included.
Response
time limit includes opening of valves to establish Safety Injection path and attainment of discharge pressure for centrifugal charging pumps, Safety Injection and residual heat removal pumps.
(2) Valves KC305B snd KC315B are exceptions to the response times listed in the table.
The following response times in seconds are the required values for these valves for the initiating signal and function indicated:
< 30(3) 7 30(3)/40(4) 2.d 3.d 4.d 7 30(3)/40(4)
(3) Diesel generator starting and sequence loading delays not included.
Offsite power available.
Response time limit includes opening of valves to establish Safety Injection path and attainment of discharge pressure for centrifugal charging pumps.
(4) Diesel generator starting and sequence loading delays included.
Response
time. limit includes opening of valves to establish Safety Injection path and attainment'of discharge presst're for centrifugal charging pumps.
(5) Response time for motor-driven auxiliary feedwater pumps on all Safety-Injection signals shall be less than or equal to 60 seconds.
Response
time limit includes attainment of discharge pressure for auxiliary feedwater pumps.
(6) Response time includes a time delay of up to 6 seconds.
l l
l CATAWBA - UNITS 1 & 2 3/4 3-41 Amendment No.60 (Unit 1)
Amendment No.54 (Unit 2) l l
L__._____u_________
..__________________._a
MFSI 1
EY -
VAT ALS A.
A.
A.
A.
A.
LEE
+
SRT N Q N
N N
N Q REY
)
)
A.
A.
1 TAT A.
A.
A.
1 SLS
(
AEE
(
MRT N M N
N N
N M T
NS N
OE O
IT I
T T
)
)
A UI A.
A.
A.
A.
1 T
TG A.
1
(
N CO
(
E AL N M N
N.
N N M M
U R
L T
A S
G N
N N
O I
I I
TET M-ACA ES PUIRT A.
A.
TT ITVES A.
A.
A.
SN RCEPE YE TADOT R N N
N N
R N SME NR L
2 OI A
IU N
3 TQ O
AE LI 4
UR GET T
ONA E
CE LNRT L
AC AAES A.
A.
A.
A B
N NHPE A
SA ACOT N M M
M M
N N T
EL RL UI N
TE O
AV I
ER T
FU LA S
ER Y
NB T
NI E
AL A.
A.
A.
A F
HA A
CC N N R
R R
N N S
y e
r n
D L
pr a
i E
E ie i
n
,b
,o y
r R
NK rt al E
NC T a ei p nid c n u E
AE wrxmot enoT A.
A.
A.
A N
HH rdAuuiarei e
I CC oe A P t r e gt
,c N N S
5 S
N N G
t em aet rari N
cF o
,nl pl erev E
a oneoOimet r n
n e
,R ovs FE pae o -
s o -
i a i a y
,OWS R n iiI n t uda t uda
( ol tr og o a 0 ti n n s g r a t nl h
y a t nl i
ntrr-sti orna) i cae g
w w a i cae oat e r u a di oi e n t A R
ti ro o r t A il npoal l ttl l o i c
nH eL eL p i t ooOthii aaoci n cin e-z-
n-S n cin T
csC oxt urrout I
igo me ie i e I
ig I
eI nMEnBeeCNa t oi nr rr L r t t
N j
,o-e pn r
l alt i u uu u n l
a U
n" ni r d V yO e t d e a m a as ss ms e a m IAot en r
Gnnp u onu t s ss as m u onu i at asat eaO n t ot ne ee ee n n t ot LL y"
tl a uisl n a uic or rr t r i a uic l ueo
,r M AtA CP PP SP a M AtA EA NN t eaiwel NO esl tdguiasppe t
AI f aonernxh emit no HT ah s e e u n u xi o r a CC SPIVFPAAEDCTW a b c
d e
C a b N
U 2
F 1
EZ*"e" wi w1" S$$
f'
-)
. l, PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 3)
Verifying that each non-automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in its correct position; 4)
Verifying that each automatic valve in the flow path is in the fully open position whenever the Auxiliary Feedwater System is placed in automatic control or when above 10% RATED THERMAL POWER; and 5)
Verifying.that the isolation valves in the~ auxiliary feedwater pump suction: lines 'are open and that power is' removed from the valve operators on Valves CA-2, CA-7A, CA-98, and CA-11A and that the respective circuit breakers are padlocked.
- b.
At least once per 18 months during shutdown by:
1)
Verifying that each automatic valve. in the flow path actuates to-its correct position upon receipt of an Auxiliary Feedwater Actuation test signal, 2)
Verifying that each motor-driven auxiliary feedwater pump starts as designed automatically upon receipt of'an Auxiliary Feedwater Actuation-test signal, 3)
Verifying that the turbine-driven auxiliary feedwater pump steam supply valves open upon receipt of an Auxiliary Feedwater Actua-tion test signal,** and 4)
Verifying that the valve in the suction line of each auxiliary feedwater pump from the Nuclear Service Water System automatically actuates to its full open position within less than or equal to 16 seconds
- on a Loss-of-Suction test signal.
l 4.7.1.2.2 An auxiliary feedwater flow path to each steam generator shall be
- demonstrated OPERABLE following each COLD SHUTDOWN of greater than 30 days prior to entering MODE 2 by verifying normal flow to each steam generator.
- Includes a time delay of up to 6 seconds.
l
- This surveillance need not be performed on Unit 2 until prior to entering HOT STANDBY following the Unit 2 first refueling.
CATAWBA - UNITS 1 & 2 3/4 7-5 Amendment No. 60(Unit 1)
Amendment No. 54 (Unit 2)
_ _ - _ _- _ _ _ _ _.