ML17156A171
| ML17156A171 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/23/1985 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17156A172 | List: |
| References | |
| NUDOCS 8504300046 | |
| Download: ML17156A171 (16) | |
Text
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/yn UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 PENNSYLVANIA POWER 8( LIGHT COMPANY A
N C
N UUE UEHAUUAE~TIUIE UIIIT I MNDMN F CIL Y
P R TING L GENS Amendment No.
38 License No. NPF-14 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having
-found that:
A.
The application for the amendment filed by the Pennsylvania Power.
5 Light Company, dated October 31, 1984, complies with the
- standards and requirements of the Atomic Energy Act of 1954, as amended (the Act). and the Commission's regulations set forth in 10 CFR Chapter I; B.
, C..
0.
E.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission;
.. There is teasonable
.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 set forth in 10 CFR Chapter I; 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 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 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 the Facility Operating License No. NPF-14 is hereby amended to read as follows:
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
38 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license..
The licensee shall operate the facilities in accordance with the Technical Specifications and the Environmental Protection Plan.
8504300046 PDR ADOCK P
e504ZS}
i 05000387'DR I
- i
3.
This amendment is.affective upon startup following the first refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Changes to the Technical Specifications Date of Issuance:
APR 8 8 595 A. Schwencer, Chief Licensing Branch No.
2 Division of Licensing
~
~ 1
\\
ATTACHMENT TO LICENSE AMENDMENT NO.
38 LI Y
P N
N.N
-1 DOCKET NO. 50-387 Replace the following pages of the Appendix "A" Technical Specifications with enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT 3/4 3-11 3/4 3-11 3/4 3-12 3/4 3-12 3/4 3-17 3/4 3-18 3/4 3-21 3/4 3-22 3/4 3-23 3/4 3-24 3/4 6-19 3/4 6-20
.B 3/4 3-7 B 3/4 3-.8 3/4 3-17 3/4 3-18 3/4 3-21 3/4 3-22 3/4 3-23 3/4 3-24 3/4 6-19
'3/4 6-20 B 3/4 3-7 B 3/4 3-8
TABLE 3.3.2-l ISOLATION ACTUATION INSTRUMENTATION TRIP FUNCTION 1.
PRIMARY CONTAINMENT ISOLATION a.
Low, Level 3
2)
Low Low, Level 2
3)
Low Low Low, Level 1
ISOLATION( )
SIGNAL s B
X MINIMUM APPLICABLE OPERABLE CHANNELS OPERATIONAL PER TRIP SYSTEM b
CONDITION 1,2,3 1', 2, 3
l, 2, 3
ACTION 20 20 20 b.
Drywell Pressure - High Y,Z,X c.
Manual Initiation 1,2,3 1.2 3
20 24 d.
SGTS Exhaust Radiation-High R
e.
Main Steam Line Radiation"High C
2.
SECONDARY CONTAINMENT ISOLATION 1
2 3
20 1
2 3 4am+ 5xxx 20 b.
C.
Reactor Vessel Water Level-Low Low, Level 2
Drywell Pressure - High Refuel Floor High Exhaust Duct Radiation - High 1,2,3 and*
1 $ 2 j 3 1, 2, 3 and "
25 25 25 d.
Railroad Access Shaft Exhaust Duct Radiation - High AA',2, 3 and "
25 e.
Refuel Floor Wall Exhaust Duct Radiation - High f.
Manual Initiation NA 1,2,3and" 1,,2, 3 and" 25 24
CA Cil AD
'C:
CTl TRIP FUNCTION TABLE 3.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION
. MINIMUM ISOLATION OPERABLE CHANNELS SIGNAL s PER TRIP SYSTEM b
APPLICABLE OPERATIONAL CONDITION ACTION 0
00 3.
. MAIN ao b.
C.
e.
h.
STEAM LINE ISOLATION eactor esse ater Level "
X Low, Low, Low, Level 1 Main Steam Line Radiation -
C High Main Steam Line Pressure - Low P
Main Steam Line Flow - High D
Condenser Vacuum - Low UA Reactor Building Main Steam Line E
Tunnel Temperature - High Reactor Building Main Steam Line E
Tunnel 4 Temperature - High Manual Initiation NA RWCU h Flow - High J
RWCU Area Temperature - High W
RWCU Area Ventilation 6 Temp. -
W High SLCS Initiation Reactor Vessel Water 8
Level - Low Low, Level 2 RWCU Flow - High ao C,
d.
e.
J NA g.
Manual Initiation Turbine Building Main Steam E
Line Tunnel Temperature-High 4.
REACTOR WATER CLEANUP SYSTEM ISOLATION 2
2 2/line 2
2 1, 2, 3
I 1
2 3
1, 2, 3
1, 2, 3
1, 2, 3
1,2,3 1,2,3 1, 2, 3 l,2,3 l,g,3 1,2,3 l, 2, 3
1 2
3 1
2 3
1,2,3 21 22
~
20 21 21 21 23 23 23 23 23 23 24
Vl AD I
TRIP FUNCTION PRIMARY CONTAINMENT ISDLATION TRIP SETPDINT TABLE 3.3.2-2 ISOLATION ACTUATION INSTRUMENT TION SETPDINTS ALLOMABLE VALUE 2.
a.
Reactor Vessel Mater Level 1)
Low, Level 3
2)
Low Low, Level 2 3)
Low Low Low, Level 1 b.
Drywell Pressure - High c.
Manual Initiation d.
SGTS Exhaust Radiation " High e.
Hain Steam Line Radiation - High SECONDARY CONTAINMENT ISOLATIDN
> 13.0 inches*
> -38.D inches"
> -129-inch'es*
< 1.72 psig NA
<23.D mR/hr
< 3 x full power background
> 11.5 inches
>.-45.0 inches
>,'-136 inches c 1.88 psig NA
<31.0 mR/Hr
<3. 6 x full power background ao b.
C.
d.
e.
Reactor Vessel Water Level-Low Low, Level 2
Drywell Pressure
- High Refuel Floor High Exhaust Duct Radiation - High Railroad Access Shaft Exhaust Duct Radiation - High Refuel Floor Mall Exhaust, Duct.
Radiation - High Hanual Initiation
> -38.D inches"
< 1.72 psig
< 2.5 mR/hr."*
< 2.5 mR/hr.""
< 2.5 mR/hr.""
HA
> -45.0 inches
< 1.88 psig
< 4.0 mR/hr.""
< 4.0 mR/hr."~
< 4.D mR/hr.""
HA 3.
HAIN STEAH LINE ISOLATION O
CD b:
c d.
Reactor Vessel Water Level - Low, Low Low, Level 1 Hain Steam Line Radiation - High Hain Steam Line Pressure - Low Hain Steam Line Flow - High
> -129 inches~
< 3 X full power Background' 861 psig
< 107 psid
> -136 inches
< 3.6 X full power
Background
> 841 psig
< 110 psid
C/l C:
C/l AD m
I M
. TRIP FUNCTION TRIP SETPOXNT HAIN STEAN LINE ISOLATION (Continued) e.
Condenser Vacuum - Low
> 9.0 inches Hg vacuum TABLE 3.3.2-2 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS
'LLOWABLE VALUE
> 8.8 inches Hg vacuum g.
Reactor Building Hain Steam Line Tunnel Temperature - High Reactor Building Hain Steam Line Tunnel 6 Temperature - High Hanual Initiation Turbine Building Hain Steam Line Tunnel Temperature-High
<177F
< 99'F NA
<177 F
< 184'F
< 108 F
NA
<184 F
II 4.
REACTOR WATER CLEANUP SYSTEM. ISOLATION a.
b.
C.
d.
RWCU h Flow - High RMCU Area Temperature - High RMCU/Area Ventilation h Temperature - High SLCS Initiation
< 60 gpm 147oF or 118 3oF
< 69 F or 35.3 F0 NA
< 80 gpm
< 154 F or 125.3 F8
< 78'F or 44.3'FO NA e.
Reactor Vessel Mater Level-Low Low, Level 2
f.
RWCU Flow - High g.
Manual Initiation
> -38 inches"
< 426 gpm NA
> -45 inches
< 436 gpm NA 5.
REACTOR CORE ISOLATION COOLING SYSTEH ISOLATION O
Ch a.
b.
C.
RCIC Steam Line h Pressure
- High RCIC Steam Supply Pressure - Low RCIC Turbine Exhaust Diaphragm Pressure - High
< 177" H 0*"
> 60 psig
< 10.0 psig 189u H OA*
> 53 psig
< 20.0 psig
TABLE 3.6.3"1 PRIMARY CONTAINMENT ISOLATION VALVES VALVE FUNCTION AND NUMBER a.
Automatic Isolation Valves MSIV HV-141F022 A,B,C,D HV-141F028 A,B,C,D
.MSL Drain HV"141F016 HV-141F019 RCIC Steam Su 1
HV-149F007 HV-149F008 HV-149F088 HPCI Steam Su l
HV-155F002 HV'-155F003 HV-155F100 RHR - Shutdown Coolin Suction HV"151F008 HV-151F009 RWCU Suction HV"144F001 HV-144F004 RHR - Reactor Vessel Head S ra HV-151F022 HV-151F023 MAXIMUM ISOLATION TIME Seconds 10 10 20 20 3
50 50 3
52 52 30 30 30 20 ISOLATION( )
SIGNAL s X,C,D,E,P,UA X,C,D,E,P,UA K,KB K,KB K,KB L,LB L,LB L,LB A,M,UB A,M,UB B,J,W A,M,UB,Z SUS(UEHANNA - UNIT 1 3/4 6-19 Amendment No. 38
TABLE 3.6.3-1 (Continued)
PRIMARY CONTAINMENT ISOLATION VALVES VALVE FUNCTION AND NUMBER MAXIMUM ISOLATION TIME Seconds ISOLATION( )
SIGNAL s Automatic Isolation Valves (Continued)
Containment Instrument Gas HV-12603 SV-12605 SV-12651 SV-12661 SV-12671 RBCCM HV-11313 HV-11314 HV"11345 HV-11346 Containment Pur e
HV-15703 HV-15704 HV"1570)
HV"15711 HV-15713 HV-15714 HV"15721 HV-15722 HV"15723 HV-15724 HV-15725 RHR - Or ell S ra HV-151F016 A,B RB Chi1'ted Mater 20 N/A N/A N/A N/A 30'0 30 30 15 15 15 15 15 15 15 15 15 15 15 90 X,Z X,Z X,Z Y,B Y,B X,Z X,Z X,Z X,Z B,Y,R B,Y,R B,Y,R B,Y,R B,Y,R B,Y,R B,Y,R B,Y,R B,Y,R B,Y,R B,Y,R X,Z HV-18781 HV-18782 HV"18791 HV-18792 Al,A2,B1,B2 Al,A2,Bl,B2 Al,A2,B1,B2
~Al,A2,Bl,B2 40 15 X,Z X,Z Y,B Y,B SUSQUEHANNA - UNIT 1 3/4 6"20 Amendment No:
36
TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATIDN RESPONSE TIME TRIP FUNCTION 1.
PRIMARY CONTAINMENT ISOLATION a.
Low, Level 3
2)
Low Low, Level 2
3)
Low Low Low, Level,1 b.
Drywell Pressure - High c.'anual Initiation d.
SGTS Exhaust Radiation - High e.
Main Steam Line Radiation - High(
RESPONSE
TIME Seconds)¹
<1P(')
<1.P r<1P(')-
<,j(m
-io~
HA'
<1p(a)
<1p(a) 2.
S ECON a@
b".
C.
d.
e.f.
3.
MAIN a 0 b.
C, d.
e.f.
h.
DARY CONTAINMENT ISOLATION Reactor Vessel Water Level-Low Low, Level Drywell Pressure - High Refuel Floor High Exhaust Duct, Radiation Railroad Access Shg) Exhausi Duct Radiation - High Refuel Floor Wall Exhaust Duct Radiation Manual Initiation STEAM LINE = ISOLATION Reactor Vesse1 Water Leva'I-Low )8'~ Low, Main Steam Line Radiation - High Main Steam Line Pressure - Low Main Steam Line Flow-High Condenser Vacuum - Low Reactor Building Main Steam Line Tunnel Temperature - High Reartor Building Main Steam Line Tunnel 6, Temperature - High Manual Initiation Turbine Building Main Steam Line Tunnel Temperature - High 2
- High(')
-High(b)
Level 1
<1P(')
<1p(a.)
<1P( )
<1p(a)
<1O(a)'A
<Xo')
I
- 1. PlR,/<1P (a) >lit
<1 Plit/<M(ah*
<p Slit/<yp(a)
NA NA.
NA NA NA 4.
REACTOR WATER CLEANUP SYSTEM ISOLATION 5.
a.
RWCU h Flow - High b.
RWCU Area Temperature - High c.
RWCU Area Ventilation Temperature bT - High d.
SLCS Initiation e.
Low Low, Level 2
f.
RWCU Flow " High g.
Manual Initiation REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION 1O(a)¹¹ NA NA NA
~
HA NA ae b.
C.
d.
RCIC Steam Line b, Pressure - High RCIC Steam Supply Pressure - Low RCIC Turbine Exhaust Diaphragm Pressure - High RCIC Equipment Room Temperature - High
<ip(a)¹¹¹
<1p(a HA NA SUS(UEHANNA - UNIT 1 3/4 3-21 Amendment No. 38
TRIP FUNCTION TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME
RESPONSE
TIME (Seconds ¹ 3/4 3-22 e.
RCIC Equipment Room b, Temperature - High NA f.
RCIC Pipe Routing Area Temperature - High NA g.
RCIC Pipe Routing Area 6 Temperature - High NA h.
RCIC Emergency Area Cooler Temperature - High NA i.
Manual Initiation NA j.
Drywell Pressure -High'~p(a) 6.
HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION a.
HPCI Steam Flow - High
<~O(a)¹¹¹¹ b.
HPCI Steam Supply Pressure - Low
<10( )
c.
HPCI Turbine Exhaust Diaphragm Pressure - High HA d.
HPCI Equipment Room Temperature - High NA e.
HPCI Equipment Room 6 Temperature - High NA f.
HPCI Emergency Area Cooler Temperature - High NA g.
HPCI Pipe Routing Area Temperature - High NA h.
HPCI Pipe Routing Area 6 Temperature. - High NA Manual Initiation NA j.
Drywell Pressure - High t<io(')
7.
RHR SYSTEM SHUTDOWN COOLING/HEAD SPRAY MODE ISOLATION t
a.
Reactor Vessel Water Level - Low, Level 3
<10 Reactor Vessel (RHR'Cut-in Permissive)
Pressure - High NA c.
RHR Equipment Area 6 Temperature - High'A d.
RHR Equipment Area Temperature - High NA I
e.
RHR Flow - High NA f.
Manual Initiation NA g.
Dryeell Pressure
- High (lg~ l a
e >so ation system instrumentation response time shall be measured and recorded as a part of the ISOLATION SYSTEM RESPONSE TIME.'Isolation system instrumentation response time specified includes the delay for diesel generator starting assumed in the accident analysis.
(b) Radiation detectors are exempt from response time testing.
Response
time shall be measured from detector output or the input of the first electronic component in the channel.
"Isolation system instrumentation response time for MSIVs only.
No diesel generator delays assumed for MSIV Valves.
""Isolation system instrumentation response time for associated valves except MSIVs.
¹Isolation system instrumentation response time specified for the Trip Function actuating each valve group shall be added to isolation time shown in Table 3.6.3-1 and 3.6.5.2-1 for valves in each valve group to obtain ISOLATION SYSTEM RESPONSE TIME for each valve.
¹¹With time delay of 45 seconds.
¹¹¹With time delay of 3 seconds.
¹¹¹¹With time delay of 3 seconds.
SUS(UEHANNA - UNIT 1 Amendment No'. 36
TABLE 4.3.2.1-1 ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP FUNCTION 1.
PRIMARY CONTAINMENT ISOLATION CHANNEL CHECK CHANNEL FUNCTIONAL TEST CHANNEL CALIBRATION OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE VIREO a.
b.
C.
d.
e.
Reactor Vessel Water Level-1)
Low, Level 3
S 2)
Low Low, Level 2
S 3)
Low Low Low, Level 1
S Drywell Pressure - High NA Manual Initiation NA SGTS Exhaust Radiation - High S
Main Steam Line Radiation - High S M
M M
M R
M M
R R
R R
NA R
R 1, 2, 1 j 2 $
1 7 2 j 1, 2, 1
2 1
2 1, 2, 3
3 3, 4, 5, 3
2.
SECONDARY CONTAINMENT ISOLATION ao b.
C.
d.
e.
Reactor Vessel Water Level-Low Low, Level 2
Drywell Pressure - High Refuel Floor High Exhaust Duct Radiation - High Railroad Access Shaft Exhaust Duct Radiation - High Refuel Floor Wall Exhaust Duct Radiation - High Manual Initiation
-NA S
NA M.
M R
NA 1,2,3and*
1,2,3 1,2,3and" 1, 2, 3 and
~
1, 2, 3 and "
1, 2, 3 and
- TABLE 4.3.2.1-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS AD f
RECHANNEL CHECK TRIP FUNCTION 3.
a%
b.
MAIN STEAM LINE ISOLATION Reactor Vessel Mater Level-Low, Low Low, Level 1 S
Main Steam Line Radiation - High S
Main Steam Line Pressure - Low HA Main Steam Line Flow - High S
Condenser Vacuum - Low.
HA Reactor Building Main Steam Line Tunnel Temperature - High NA Reactor, Building Main Steam Line Tunnel h Temperature - High NA Manual Initiation HA Turbine Building Main Steam Line NA Tunnel Temperatu) e - High C.
e.
h.
4.
REACTOR WATER CLEANUP SYSTEM ISOLATION CHANNEL FUNCTIONAL
. TEST CHANNEL CALIBRATION Q
HA OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE UIRED 1, 2, 3
I 2~
3 1, 2 3
24 3k*
1, 2, 3
1,2,3 1
2 3
O a.
C.
d.
e.
g.
RWCU h Flow - High RWCU Area Temperature - High RMCU Area Ventilation h Temperature - High SLCS Initiation Reactor Vessel Mater Level - Low Low, Level 2 RWCU Flow - High Manual Initiation NA NA S
S NA R
R NA 1,2,3 1,2,3 1, 2, 3
,1,2,3
1,2,3 1, 2, 3
1,2,3
INSTRUMENTATION BASES 3/4. 3.8 TURBINE OVERSPEED PROTECTION SYSTEM This specification is provided to ensure that the turbine over speed protection system instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed.
Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety related components, equipment or structures.
3/4. 3. 9 FEEDWATER/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION'The feedwater/main turbine trip system actuation instrumentation is provided to initiate action of the feedwater system/main turbine trip system in the event of failure of feedwater controller under maximum demand.
SUS(UEHANNA - UNIT 1 B 3/4 3-7
WATER LEVEI NOMENCLATURE HEIGHT ABOVE NO.
VESSEL ZERO READING (in.)
G VESSEL F LANGE l8)
(7)
(4)
(3)
(2)(ll 581.5 566.5 5578 540.5 39BD
+39
+30
+13 38 129 660 MAIN 58 Gl STEAM LINE WIOG i
NARROW IIANG RANGE
+60 BOTTOM OF STEAM DRYER SKIRT FE D
4985~
WATnR 450 581$ (8),
566.5 (7) 557.5 (4) 540.5 (3) 527 5 INSTRUMENT ZERO 489.5 (2)
SPRAY 0
0 (7)
HnCI 5
'f4l RCIC TRIPS (2)
INITIATERCIC, HPCI TRIP RECWC PUMPS 39 HI ALARM 30 LO aLARM (3) 13 0
REACiOR SCRAh1 CONTR I8U I-TO ADS 350.
398$ ('l l
~ 150 129 (1) INITIATERHR, C.S.
START DIESEL CONTRIBUTE TO A.D.S.
QJ7SE lBIV 5 IVE EL ACT FU RECIRC OUTLET 161.
NOZZLE 150 216 RECIRC 181.0~
INLET'OZZLE 100 NOTE: SCALE IN INCHES ABOVE VESSEL ZERO I
BASES FIGURE B 3/4 3-1 REACTOR VESSEL MATER LEVEL'US(UEHANNA
- UNIT 1 B 3/4 3-8 Amendment No. 38