ML20094C139
| ML20094C139 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 10/30/1995 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Philadelphia Electric Co |
| Shared Package | |
| ML20094C144 | List: |
| References | |
| NPF-39-A-103, NPF-85-A-067 NUDOCS 9511020061 | |
| Download: ML20094C139 (12) | |
Text
._. _ _ _
~
p rerg j,
i UNITED STATES a
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20086-4 N1 PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-352 LIMERICK GENERATING STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.103 License No. NPF-39 1
1.
The Nuclear Regulatory Commission (the Commission) has found that:
l A.
The application for amendment by Philadelphia Electric Company (the-licensee) dated January 27, 1995, as supplemented October 10, 1995, complies with the standards and requirements of the Atomic Energy Act l
of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR l
Chapter I; B.
The facility will operate in conformity with the application, the l
provisions of the Act, and the rules and regulations of the l
Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and l
safety of the public, and (ii) that such activities will be conducted in compliance with the Commission'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 E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been l
satisfied.
l l
l l
9511020061 951030 '
i PDR ADOCK 05000352 l
P PDR-
.7-..----.-
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-39 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.
103, are hereby incorporated into this license.
Philadelphia Electric Company 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, to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION 4
J n
. Stolz, Director P
ect Directorate I-Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October'30, 1995
ATTACHMENT TO LICENSE AMENDMENT NO.103 FACILITY OPERATING LICENSE NO. NPF-39 DOCKET NO. 50-352 1
Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 3/4 6-24 3/4 6-24 3/4 6-25 3/4 6-25 3/4 6-43 3/4 6-43 4
~
i TABLE 3.6.3-1 (Continued)
PART A - PRIMARY CONTAIMENT ISOLATION VALVES I
C
~
x 9
INBOARD OUTBOARD ISOL.
y PENETRATION FUNCTION ISOLATION ISOLATION MAX.ISOL.
SIGNAL (S), NOTES P&ID
)
NUMBER BARRIER BARRIER TINE.IF APP.
IF APP.
(SEC)(26)
(20) c*i l
.w 040G-1 ILRT DATA ACQUISITION 60-1057 NA 11 60
{
60-1058 NA 11
)
i 040G-2 ILRT DATA ACQUISITION 60-1071 NA 11 60 60-1070 NA 11 040H-1 CONTAlletENT INSTRtMENT 59-1005A(CK)
NA 59 GAS SUPPLY - HEADER
'A' HV59-129A 7
C,H,S i
STAND 8Y LIQUID CONTROL 48-lF007(CK)
NA 48 042 (X-Il6)
HV48-IF006A 60 29 i
(
s*
043B MAIN STEAM SAMPLE HV41-lFG84 10 8
41
[
HV41-lF085 10 8
044 RWCU ALTERNATE 41-1017 NA 5,31 41 RETURN 41-1016(X-9A, NA L
X-98) i PSV41-ll2 NA l
2 045A(B,C,D) LPCI INJECTION *A*(8,C.D) HV51-IF041A(8,C, NA 9,22 51 R
D)(CK) i 2
HV51-142A(8,C, 7
9,22 i
A D)
HV51-lF017A 38 2
(8,C,D) 050A-1 DRYWELL PRESSURE HV42-1478 45 10 42 O
INSTRLMENTATION 5
053 DRYWELL CHILLED WATER HV87-128 60 C,H 11 87 SUPPLY - LOOP
'A' HV87-120A 60 C,H 11 HV87-125A NA 34 l
I
- l
TABLE 3.6.3-1 (Continued) i PART A - PRINARY CONTAIMENT ISOLATION VALVES C
l a
r' 5
Q INBOARD OUTBOARD ISOL.
i PENETRATION FUNCTION ISOLATION ISOLATION NAX.ISOL.
SIGNAL (S),
NOTES P&ID NUMER BARRIER BARRIER TINE.IF APP. IF APP.
c (SEC)(26)
(20) 5 i
i 054 DRYWELL CHILLED WATER HV87-129 60 C,H 11 87 i
~
RETURN - LOOP 'A' HV87-121A 60 C,H 11 l
l HV87-124A NA 34 055 DRYWELL CHILLED WATER HV87-122 60 C,H 11 87 SUPPLY - LOOP 'B' HV87-1208-60 C,H 11 HV87-1258 NA 34 f
i 056 DRYWELL CHILLED WATER HV87-123 60 C,H 11 87 i
RETURN - LOOP 'B' HV87-1218 60 C,H 11 w
2 HV87-124B NA 34 l
[
061-1 RECIRC PUMP 'A' SEAL 43-1004A(CK)
NA 15 43 8
PURGE (XV43-103A -
NA 1
I SEE PART B, THIS TABLE) 061-2 RECIRC PLMP
'B' SEAL 43-1004B(CK)
NA 15 43 PURGE (XV43-1038 -
NA 1
i SEE PART 8, THIS TABLE) k 062 DRYWELL H2/02 SAMPLE SV57-150(X-220A) 5 8,H,R,5 11 57 g
RETURN, N2 MAKE-UP SV57-159 5
B,H,R,S 11 g
(X-220A)
HV57-116 30**
B,H,R,S 11 2
P (X-220A) t i
SV57-190 5
B,H,R,5 11 y
(X-220A) n I
d O
h 4
j i
4
TAE
. : 1.6.3-1 PRIMARY CONTAI NP EP ISOLATION VALVES NOTA" ION (Continued Automatic ?ssolation signal causes TIP to retract; ball valve closes when probe is fully retracted.
22.
Isolation barrier remains water filled or a water seal remains in the line post-LOCA.
Isolation valve may be tested with water.
Isolation valve leakage is not included in 0.60 La total Type B & C tests.
23.
Valve does not receive an isolation signal. Valves will be open during Type A test. Type C test not required.
24.
Both isolation signals required for valve closure.
25.
Deleted 26.
Valve stroke times listed are maximum times verified by testing per Speci-fication 4.0.5 acceptance criteria. The closure times for isolation valves in lines in which high-energy line breaks could occur are identified with a single asterisk.
The closure times for isolation valves in lines which provide an open path from the containment to the environs are identified with a double asterisk.
27.
The reactor vessel head seal leak detection line (penetration 29A) excess flow check valve is not subject to OPERABILITY testing. This valve will not be exposed to primary system pressure except under the unlikely con-ditions of a seal failure where it could be partially )ressurized to reactor pressure. Any leakage path is restricted at tie source; therefore, this valve need not be OPERABILITY tested.
28.
(DELETED) 29.
Valve may be open during normal operation; capable of manual isolation i
from control room.
Position will be controlled procedurally.
30.
Valve normally open, closes on scram signal.
31.
Valve 41-1016 is an outboard isolation barrier fcr penetrations X-9A, B and X-44.
Leakage through valve 41-1016 is included in the total for penetration X-44 only.
32.
Feedwater long-path recirculation valves are sealed closed whenever the reactor is critical and reactor pressure is < greater than 600 psig.
The valves are expected to be opened only in the following instances:
a.
Flushing of the condensate and feedwater systems during plant startup, 4
b.
Reactor pressure vessel hydrostatic testing, which is conducted follow-ing each refueling outage prior to commencing plant startup.
Therefore, d. valve stroke timing in accordance with Specification 4.0.5 is not require 33.
Valve also constitutes a Unit 2 Reactor Enclosure Secondary Containment AutomaticIsolationValveandaRefuelir$leArea Secondary Containment Automatic Isolation Valve as shown in Ta 3.6.5.2.1-1 and Table 3.6.5.7.2-1 respectively.
34.
Auto isolation signals have been removed from HV-0$7-124 A/B and 125 A/B.
Valves to be closed with associated circuit breakers locked open during OPCONs 1, 2, and 3.
LIMERICK - tJNIT 1 3/4 6-43 Amend.nent No. 23,103
7 -. _ _ _..-_._ -__
40u g
UNITED STATE 8 i
s j
NUCLEAR REGULATORY COMMIS810N
- %.....}
WASHINGTON, D.C. 30806 4001 1
PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-353 LIMERICK GENERATING STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 67 License No. NPF-85 1.
The Nuclear Regulatory Comission (the Commission) has found that:
3 A.
The application for amendment by Philadelphia: Electric Company (the licensee) dated January 27, 1995, as supplemented October 10, 1995,,
complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and i
regulations 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 Commission; 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 Commission'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 E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
i i
i
--,.,e...
-,.., - - - ~ _
... - -.. -. ~
l 1 2.
Accordingly, the license is amended by changes te the Technical Specifications as indicated in the attacanent to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-85 is hereby amended to read as follows:
Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.
67, are hereby incorporated into this license.
Philadelphia Electric Company 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, to be implemented within 30 days.
j FOR THE NUCLEAR REGULATORY COMISSION l
s 1
J nF.Stolz,Directd P
ect Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 30, 1995 l
i L
i l
e e
ATTACHMENT TO LICENSE AMENDMENT NO. 67 FACILITY OPERATING LICENSE NO. NPF-85 DOCKET NO. 50-353 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 3/4 6-24 3/4 6-24 3/4 6-25 3/4 6-25 3/4 6-43 3/4 6-43 i
i
l l
~
l TABLE 3.6.3-1 (Continued)-
l l
PART A - PRIMARY CONTAIMENT ISOLATION VALVES i
g M
m M
INBOARD OUTBOARD ISOL.
PENETRATION FUNCTION ISOLATION ISOLATION MAX.ISOL.
SIGNAL (S),
NOTES P&ID NUMBER BARRIER BARRIER TINE.IF APP.
IF APP.
l E
(SEC)(26)
(20) q ro 040G-1 ILRT DATA ACQUISITION 60-2057 NA 11 60 60-2058 NA 11 040G-2 ILRT DATA ACQUISITION 60-2071 NA 11 60
+
60-2070 NA 11 040H-1 CONTAINMENT INSTRUMENT 59-2005A(r..X)
NA 59 GAS SUPPLY - HEADER
'A' HV59-229A 7
C,H,S -
042 STANDBY LIQUID CONTROL 48-2F00T(CK)
NA 48
{
(X-116)
HV48-2F006A 60 29 i
0438 MAIN STEAM SAMPLE HV41-2F084 10 B
41 HV41-2F085 10 8
044 RWCU ALTERNATE 41-2017 NA 5,31 41 RETURN 41-2016(X-9A, NA X-98)
PSV41-212 NA 045A(B,C,D) LPCI INJECTION 'A'(B,C,D) HV51-2F041A(B,C, NA 9,22 51 y
D)(CK) 8 HV51-242A(B,C, 7
9,22 D)
HV51-2F017A 38 (B,C,D) 050A-1 DRYWELL PRESSURE HV42-2478 45 10 42 M
INSTRUMENTATION 053 DRYWELL CHILLED WATER HV87-228 60 C,H 11 87 f
SUPPLY - LOOP 'A' HV87-220A 60 C,H 11 l
HY87-225A NA 35 l
i TABLE 3.6.3-1 (Continued)
PART A - PRIMARY CONTAIMENT ISOLATION VALVES c
1 2
i 3
INBOARD OUTBOARD ISOL.
p PENETRATION FUNCTION ISOLATION ISOLATION MAX.ISOL.
SIGNAL (S),
NOTES P&ID NUMBER BARRIER BARRIER INE.IF APP.
IF APP.
(SEC)(26)
(20) c z
U 054 DRYWELL CHILLED WATER HV87-229 60 C,H 11 87 i
m RETURN - LOOP 't.'
HV87-221A 60 C,H 11 i
HV87-224A NA 35 055 DRYWELL CHILLED WATER HV87-222 60 C,H 11 87
'l SUPPLY - LOOP 'B' HV87-2208 60 C,H -
11
(
HV87-2258 NA 35 056 DRYWELL CHILLED WATER HV87-223 60 C,H 11 87 RETURN - LOOP 'B' HV87-221B 60 C,H 11 l
l HV87-224B NA 35 f
061-1 RECIRC PUMP 'A' SEAL 43-2004A(CK)
NA 15 43 a
PURGE (XV43-203A -
NA 1
5 SEE PART B, j
THIS TABLE) 061-2 RECIRC PUMP
'B' SEAL 43-2004B(CK)
NA 15 43 PUR"aE (XV43-2038 -
NA 1
i SEE PART B, THIS TABLE) 062 DRYWELL H2/02 SAMPLE SV57-250(X-220A) 5 S,H,R,S 11 57 Y
RETURN, N2 MAKE-UP SV57-2S9 5
U,H,R,5 11 (X-220A)
E HV57-216 30**
B,H,R,5 11 (X-220A)
SV57-290 5
B,H,R,S 11 l
f (X-220A)
~
f
. i ~ ~ ~ "~ ~ ~ "
~ ~ ' ~ ~
' ~~ TAB L f 3. 6. 3-1 PRIMARY CONTAINF EN" ISOLATION VALVES NOTA" ION Au(Continued) lation signal causes TIP to retract; ball valve closes when RQIES tomatic iso 21.
i probe is fully retracted.
22.
Isolation barrier remains water filled or a water seal remains in the line post-LOCA.
Isolation valve may be tested with water.
Isolation valve leakage is not included in 0.60 La total Type B & C tests.
23.
Valve does not receive an isolation signal. Valves will be open during Type A test. Type C test not required 2 4 '.
Both isolation signals required for valve closure.
25.
Deleted 26.
Valve ' stroke times listed are maximum times verified by testing per Speci-fication 4.0.5 acceptance criteria.
The closure times for isolation valves in lines in which high-energy line breaks could occur are identified with a single asterisk.
The closure times for isolation valves in lines which provide an open path from the containment to the environs are identified J
with a double asterisk.
27.
The reactor vessel head seal leak detection line (penetration 29A) excess I
flow check valve is not subject to OPERABILITY testing. This valve will not be exposed to primary systam pressure except under the unlikely con-ditions of a seal failure where it could be partially pressurized to reactor pressure. Any leakage path is restricted at the source; therefore, this valve need not be OPERABILITY tested.
28.
(DELETED) 29.
Valve may be open during normal operation; capable of manual isolation from control room.
Position will be controlled procedurally.
30.
Valve normally open, closes on scram signal.
31.
Valve 41-2016 is an outboard isolation barrier for penetrations X-9A, B and X-44.
Leakaae through valve 41-2016 is' included in the total for penetration X-44'only.
32.
Feedwater long-path recirculation valves are sealed closed whenever the reactor is critical and reactor pressure is greater than 600 psig. The valves are expected to be opened only in the following instances:
a.
Flushing of the condensate and feedwater systems during plant startup, b.
Reactor pressure vessel hydrostatic testing, which is conducted follow-ing each refueling outage prior to commencing plant startup.
Therefore, d. valve' stroke timing in accordance with Specification 4.0.5 is not require 33.
Valve also constitutes a Unit 1 Reactor Enclosure Secondary Containment Automatic Isolation Valve and a Refueling Area Secondary Containment Automatic Isolation Valve as shown in Table 3.6.5.2.1-1 and Table 3.6.5.2.2-1, respectively.
34.
Isolation signal causes recombiner to trip; valve closes when recombiner is not operating.
35.
Auto isolation signals have been removed from HV-087-224 A/B and 225 A/B.
Valves to be closed with associated circuit breakers locked open during OPCONs 1, 2, and 3.
LIMERICK - UNIT 2
?/4 6-43 Amendment No. 67
.