ML17139B177
| ML17139B177 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 10/22/1982 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17139B178 | List: |
| References | |
| NUDOCS 8211090116 | |
| Download: ML17139B177 (11) | |
Text
PENNSYLVANIA POllER 5 LIGHT COMPANY A LE HE E
C ERA N
0 N
SUSQUEHANNA S 0
L S
TIOH, UNIT 1 NDNENT TO FA ILITY OPERATING LICENSE I.icense No. HPF-14 Amendment Ho. 4 1.
The Nuclear Regulatory Commission (the Commission or the HRC) having found that:
A.
The applications for amendment filed by the Pennsylvania Power 8 Light
- Company, dated October 6, 1982 (PLA-1329), October 15, 1982 (PLA-1349) and October 20, 1982 (PLA-1356) comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission' 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 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.
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 Ho. HPF-14 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan OFRCEP SURNAME/
DATEf
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The Technical Specifications contained in Appendix A, as revised through Amendment Ho. 4, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PP8L shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
8211090116 82i022PDR
'ADQCH, 05000387 P
NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1881~960
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3.
This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COM1/IISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
0<< > > lgsp B. J. Youngblood, Chief Licensing Branch No. I Division of Licensing OFFICE%
SURNAME/
10/g+82 DATE5 DL:L 01
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MRush o :ci DL g2 ABournia 10/yV/82 OELD 10/~~/82 DL:
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NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USG PO: 1981 335-960 1
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ATTACHtKNT TO LICENSE AMENDMENT NO. 4 N
DOCKET 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.
RENOVE 3/4 3-11 3/4 3-17 3/4 3-21 3/4 3-23 3/4 6-20 INSERT 3/4 3-11 3/4 3-17 3/4 3-21 3/4 3-23 3/4 6-20 OFFICE/
SURNAME/
DATEf
,NRG FORM 318 (10-80) NRCM 0240
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OFFlCIAL. RECORD COPY USePO: 1081-33. M0
TABLE 3. 3. 2-1 ISOLATION ACTUATION INSTRUMENTATION
-TRIP FUNCTION 1.'RIMARY CONTAINMENT ISOLATION
,a.
Low, Level 3
MINIMUtl APPLICABLE ISOLATION OPERABLE CHANNELS OPERATIONAL
)')
1, 2, 3
ACTION 20 2)
Low Low, Level 2
3)
Low Low Low, Level 1
b.
Drywel1 Pressure
- High I
c.
Manual Initiation Y,Z,X 1, 2, 3
1 1, 2, 3
1 2
3 1
2 3
20 20 20 2.
SECONDARY CONTAINMENT ISOLATION I
a.
Rbactor Vessel Water Level-L'ow Low, Level 2
b.'rywell Pressure High c.
Refuel Floor High Exhaust Duct Radiat'ion - High Y (c)
Y Z <c) 2 1, 2, 3 and
- 1 2
3 1, 2, 3 and
~
25 25 25 d.
e.
Railroad Access Shaft Exhaust Duct Radiation High Refuel Floor Wall Exhaust Duct Radiation - High manual Initiation
'2 1, 2, 3and*
1,'2, 3 and "
1, 2, 3 and
- 25 25 24
TABLE 3.3.2-2'SOLATION ACTUATION INSTRUMENTATION SETPOINTS TRIP FUNCTION 1.
PRIMARY CONTAINMENT ISOLATION TRIP SETPOINT ALLOWABLE VALUE a.
b.
C.
Low, Level 3
2)
Low Low, Level 2
3)
Low Low Low, Level 1
Drywell Pressure
- High Manual Initiation
> 13.0 inches"
> -38.0 inches~
> -129 inches"
< 1.72 psig NA
> 11.5 inches
> -45.0 inches
> -136 inches
< 1.88 psig NA 2.
SECONDARY CONTAINMENT ISOLATION 3.
a.
C.
dl MAIN a.'.
d.
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
'adiation
- High Manual, Initiation STEAM LINE ISOLATION Reactor Vessel Water Level: Low Low, Level 2
Main Steam Line Radiation - High Main Steam Line Pressure Low Main Steam Line Flow - High
> -38.0 inches~
< 1.72 psig
< 2.5 mR/hr."~
< 2.,5 mR/hr.~"
< 2.5 R/hr.""
NA
> -38 inches~
< 3 X full power background
> 861 psig
< 107 psid
> -45.0 inches
< 1.88 psig
< 4.0 mR/hr.~"
< 4.0 mR/hr.~"
< 4.0 mR/hr."*
NA I
> -45.0 inches
< 3.6 X full power background
> 841 psig
< 110 psid
TRIP FUNCTION TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME
RESPONSE
TIME (Seconds ¹ PRIMARY CONTAINMENT ISOLATION a ~
b.
C.
Low, Level 3
2)
Low Low, Level 2
3)
Low Low Low, Level 1
Drywell Pressure
- High Manual Initiation
<yO(a)
- i. O ~I.O(')-
-,'2 )
NA 2 ~
3.
SECONDARY CONTAINMENT ISOLATION a ~
b.
C.
d.
MAIN STEAM LINE ISOLATION Reactor Vessel Water Level-Low Low, Level 2
Drywell Pressure High Refuel Floor High Exhaust Duct Radiation - High Railroad Access Sh~P Exhaust lluct Radiation - High e.
Refuel Floor Wall Exhaust Duct Radiation -High f.
Manual Initiation
<yO(a)
<yO(a)
<io(a)
<IO(a)
.<IO(a)
NA a 0 b.
C.
d.
e.f.
g.
h.
Reactor Vessel Water Level-Low )gy~h)evel 2
t1ain Steam Line Radi ati on - High Main Steam Line Pressure Low Main Steam Line Flow-High Condenser Vacuum -
Low Main Steam Line Tunnel Temperature - High Main Steam Line Tunnel IA Temperature - High Manual Initiation
<io(a)
O*/<yO(a)*lit
<g'OlR:/<jO(
)SL*
<O'5~/<gO(a)~~
NA
-NA NA NA REACTOR WATER CLEANUP SYSTEM ISOLATION a.
RWCS 6 Flow - High b.
RWCS Area Temperature - High c.
RWCS Area Ventilation Temperature bT - High d.
SLCS Initiation e.
Low Low, Level 2
f.
RWCS b, Pressure
- High g.
Manual Initiation REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION a.
RCIC Steam Line 6 Pressure
- High b.
RCIC Steam Supply Pressure Low c.
RCIC Turbine Exhaust Diaphragm Pressure
- High d.
RCIC Equipment Room Temperatur'e; High e.
RCIC Equipment Room 6 Temperature
- High f.
RCIC Pipe Routing Area Temperature High g.
RCIC Pipe Routing Area b; Temperature
- High h.
RCIC Emergency Area Cooler Temperature
- High.
i.
Manual Initiation
'O(a)¹¹ NA NA NA
<I.O(a)
NA NA O(')¹¹¹
<IO(a)
NA NA.,
NA NA NA NA NA C
SUSQUEHANNA - UNIT 1 3/0 3-2Z Amendment No.
4
TABLE 4.3.2.1-1'SOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP FUNCTION 1..
PRIMARY CONTAINMENT ISOLATION a.
Reactor Vessel Water Level CHANNEL CHECK CHANNEL FUNCTIONAL TEST CHANNEL CALIBRATION OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE UIRED b.
C.
1)
Low, Level'3 2)
Low Low, Level 2
3)
Low Low Low, Level 1
Drywell Pressure
- High Manual Initiation NA NA M
R R
R NA 1
2 3
1.2 3
1 2
3 1
2 3
1, 2, 3
2.
SECONDARY CONTAINMENT ISOLATION a.
'eactor Vessel Water Level-Low Low, Level 2
1 b.
Drywell Pressure - High c.
Refuel Floor High Exhaust Duct, Radiation - High d:
Railrqad Access Shaft Exhaust Diect Radiation - High e.
Refuel. Floor Wall Exhaust Duct Radiation High f.
Manual Initiation S
NA S
NA M
M R
R NA 1,2,3and" 1, 2, 3
1, 2, 3 and" 1, 2, 3 and "
1, 2, 3 and
- 1, 2,3and*
TABLE 3. 6. 3-1 (Continued)
PRIMARY CONTAINMENT ISOLATION VALVES MAXIMUM ISOLATION TIME Automatic Isolation Valves (Continued)
Containment Instrument Gas ISOLATION( )
SIGNAL s 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-15705 HV-15?11 HV-15713 HV-15714 HV-15721 HV-15722 HV-15723 HV.-15724 HV-15725 RHR - Dr ell S ra (<)
HV-151F016 A, B RB Chilled Mater HV-18781 Al,A2,Bl, B2 HV-18782 Al,A2,Bl,B2 HV-18791 Al,A2,Bl;B2 HV-18792 Al,A2,Bl,B2 20 N/A N/A N/A N/A 30 30 30 30 19 19 5
5 30 30 6
30 30 19 19 90 40
~
6 15 4
X X
X Y
Y Y,R Y,R Y,R Y,R Y,R Y,R Y,R Y,R Y,R Y,R Y,R X
X Y
Y SUS(UEHANNA - UNIT 1 3/4 6-20 Amendment No.
4
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