ML17157C231
| ML17157C231 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 03/02/1993 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17157C232 | List: |
| References | |
| NUDOCS 9303100333 | |
| Download: ML17157C231 (13) | |
Text
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UNITED STATES
-NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555 PENNSYLVANIA POWER 5 LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-388 SUS UEHANNA STEAM ELECTRIC STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 93 License No. NPF-22 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 November 30,
- 1992, 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.
.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 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 Commission's regulations and all applicable requirements have been satisfied.
9303100333'30302 PDR ADOCK 05000388
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Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-22 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. 93 and the Environmental Protection Plan con-tained in Appendix B, are hereby incorporated in the license.
PP&L shall operate the facility in accordance with the Technical Specifica-tions and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
Attachment:
Changes to the Technical Specifications Date of Issuance: ~<<g 2 l993 FOR THE NUCLEAR REGULATORY COHHISSION c/~ 2 @i54 Charles L. Hiller, Director Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
1 I
4
ATTACHMENT TO LICENS AM NDMENT NO.
ACILITY OPERATING LICENSE NO.
NPF-22 DOCKET NO. 50-388 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.
The overleaf pages are provided to maintain document completeness.*
REMOVE 3/4 3-11 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 INSERT 3/4 3-11*
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
TABLE 3.3.2-1 ISO!AIION ACTUATION INSTRUHfNTATION TRIP FUNCTION 1.
PRIHARY CONTAINHENT ISOLAT ION 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.
Hanual l'nitiation l SOLA710N SlGNAl(S)(a Y,2 NA HI NIHIL JH APPLICABLE OPERABLE CHANNELS OPERATIONAL
~E 1; 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
ACTION 20 20 20 20 24 2.
d.
SGTS Exhaust Radiation-High e.
Hain Steaa line Radiation-High SECONDARY CONTAINHENT ISOLATION 3
4AAA 5AAA 1, 2, 3
20 CD
~
Q Pp 0
a.
b."
C.
d.
e.
Reactor Vessel Mater level-Low low, Le'vel 2
Drywell Pressure High'efuel Floor High Exhaust Duct Radiation - High Railroad Access Shaft Exhaust Duct Radiation - High Refuel Floor Wall Exhaust Duct Radiation - High Hanual Init iat ion NA 1, 2, 3 and
~
1, 2, 3
1, 2, 3 and
~
25 25 25 25 25
TABLE 3.3.2-1 {Continued)
ISOLATIONACTUATIONINSTRUMENTATION
,tn q agC z
zz I
z co t4 O
TRIP FUNCTION MAINSTEAM LINE ISOLATION a.
Reactor Vessel Water Level-Low Low Low, Level 1
b.
Main Steam Une Radiation - High c.
Main Steam Line Pressure - Low d.
Main Steam Line Flow - High e.
Condenser Vacuum - Low f.
Reactor Building Main Steam Line Tunnel Temperature
- High g.
Reactor Building Main Steam Line Tunnel d Temperature - High h.
Manual Initiation i.
Turbine Building Main Steam Line Tunnel Temperature
- High REACTOR WATER CLEANUP SYS I EM ISOLATION a.
RWCU d Flow - High b.
RWCU Area Temperature
- High c.
RWCU Area Ventilation d Temperature
- High d.
SLCS Initiation e.
Reactor Vessel Water Level-Low Low, Level 2 f.l.
RWCU Flow - High f.2.
Non-Regenerative Heat Exchanger Discharge Temperature
- High g.
Manual Initiation ISOLATION SIGNALIS)Ia)
UA NA W
W MINIMUMOPERABLE CHANNELS PER TRIP SYSTEM Ib) 2/line 1¹ 1¹ APPLICABLE OPERATIONAL CONOFRON 1,2,3
- 1. 2. 3 1.2 3
- 1. 2. 3 1,2,3 1,2,3 1,2,3 1,2,3
- 1. 2, 3
- 1. 2. 3 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 ACTION 21 21 22 20 21 21 21 24 21 23 23 23 23 23 23 23 24 These trip functions need not be OPERABLE from October 19, 1989 to January 1,;1990.:,
¹ For Unit 2 Cycle 6 operation, the Non-Regenerative Heat Exchanger Discharge Temperature - High Channel shall be OPERABLE.in place of RWCU Flow-High Channel 'B'.
TA8LE 3.3.2-2 ISOIAIION ACIUAIIOH INSIRINENIAIIOHSEIPOIHIS IRIP fQK)ION l.
tNINANE CONIAINKNl ISOlAI ION IRIP Sf IPOINI Al I OMAH1f VAIUI'.
b.
Co 4.
eo Reecter Vessel Mater level l)
Lat, level 3 2)
Lar Lar, lewl 2 3) kev tao Lee, Level l S~ll tresswe - Nigh Naael laitietlea SGTS fxheast Re4ietiea - Nigh iiela Steaa Liae Ne4letiea - Nigh
>l3.0 inches~
> -38.0 Inches~
> -)2$ laches~
< l.72 ysig NA
< 23. ~ aN/hr 7 4 X full power
> ll.5 inches
> -IS.O inciw.s-
> -l36 Inches
< I.bb psig NA
< 3l.O ak/hr bachgrourxI 8.I X full paar teckground 2.
SECOIOIIY GNlAINKNl ISOLAIION C.
4.
Neacter Vessel Mater level-Lar Lear, level 2 Orywell tressure - Nigh Refuel Flwr Nigh fxhaust Duct Re4ietiea - Nigh Neilree4 Access Shrift Exhaust
~uct Re4letlea - Nigh Refuel Flwr Mall fxheust Suet Re4latiea - Nigh Ileriual laitlatiea
> -38.0 inches~
< l.l2 psiy
< 2-5 aN/hr
< 2.5 aN/hr
< 2.5 aN/hr IA
+ -I5.0 incIM.s l.88 psig
~.0 aR/hr
~. ii aR/lir
< I.O aR/hr NA 3.
INlllSlfNI II% SOLI'I e.
Reecter Vessel Mater Level - Lee Lew La(, Level l b.
Naia Stem Liae Nedietiea - High c.
Naia Stem Liae tressure - Low d.
Naia Stem Line Flow - High
> -uS I~h s~
< 7.0 X full power
> 86l psiy
< I07 psid
> -l36 iacles background
< 8.I X gull ~r bwiiground
> 8II psig
< llO psid
V) co
~0:
C x
zz I
Cz hJ TRIP FUNCTION MAINSTEAM LINE ISOLATION IContinued) e.
Condenser Vacuum - Low f.
Reactor Building Main Steam Line Tunnel Temperature
- High g.
Reactor Building Main Steam Line Tunnel h Temperature
- High TRIP SETPOINT
~ 9.0 inches Hg vacuum 6 177'F 99oF TABLE3.3.2-2 (Continued)
ISOLATIONACTUATIONINSTRUMENTATIONSETPOINTS ALLOWABLEVALUE 2 8.8 inches Hg vacuum 1840F 108OF h.
Manual Initiation i.
Turbine Building Main Steam Line Tunnel Temperature
- High 4.
REACTOR WATER CLEANUP SYSTEM ISOLATION NA S 197oF NA s 2004F 4l co co a.
RWCU h Flow - High b.
RWCU Area Temperature
- High c.
RWCU/Area Ventilation 6 Temperature
- High d.
SLCS Initiation e.
Reactor Vessel Water Level - Low Low, Level 2 f1.
RWCU Flow - High f2.
Non-Regenerative Heat Exchanger Discharge Temperature-High g.
Manual Initiation 5.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION 6 60 gpm 6 147' or 131 F¹
~ 69'F or 40.54F¹ NA h -38 inches
~ 426 gpm 144oF 6 80 gpm
~ 154'F or 137'F 72oF or 43 50F¹ NA 2 -45 inches 6 436 gpm 150oF NA 3
0 a.
RCIC Steam Line h Pressure
- High b.
RCIC Steam Supply Pressure
- Low c.
RCIC Turbine Exhaust Diaphragm Pressure
- High 6 153" H~O h 60psig
~ 10.0 psig These trip functions need not be OPERABLE from October 19, 1989 to January 19, 1990.
S 165" H~O h 53psig 6 20.0 psig
TRIP FUNCTION PRIMA TABLE3.3,2N ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME RESPONSE TIME (Seconds)f LATI N a.
- 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.
Main Steam Line Radiation - High" s10" s1.0'Is10>>')
s10">
s10'>
NA s10" s10'I 2.
NDAR TAINME I
LATI N a.
b.
C.
d.
e.
f.
Reactor Vessel Water Level - Low Low, Level 2 Drywell Pressure
- High Refuel Floor High Exhaust Duct Radiation - High>> I Railroad Access Shaft Exhaust Duct Radiation - High (b)
Refuel Floor Wall Exhaust Duct Radiation - High Manual Initiation s1O'I s1O>>'I s10>>'10>>6) s10">
NA MAIN TEAM LINE I LATI N a.
Reactor Vessel Water Level - Low Low Low, Level 1
b.
Main Steam Line Radiation - High>>"I c.
Main Steam Line Pressure
- Low d.
Main Steam Line Flow - High e.
CondenserVacuum
- Low f.
Reactor Building'Main Steam Line Tunnel Temperature
- High g.
Reactor Building Main Steam Line Tunnel h Temperature
- High h.
Manual Initiation i.
Turbine Building Main Steam Line Tunnel Temperature
- High REA T RWATR N
P YTMI LATI N a.
RWCU h Flow - High b.
RWCU Area Temperature
- High c.
RWCU Area Ventilation Temperature hT - High d.
SLCS Initiation e.
Reactor Vessel Water Level - Low Low, Level 2 f1.
RWCU Flow - High f2. NorHhgenerative Heat Exchanger Discharge Temperature
- High g.
Manual Inithtlon REA R
LATI N LIN Y TEM IS LATI N a.
RCIC Steam Line h Pressure
- High b.
RCIC Steam Supply Pressure
- Low c.
RCIC Turbine Exhaust Diaphragm Pressure
- High d.
RCIC Equipment Room Temperature
- High e.
RCIC Equipment Room 6 Temperature
- High f.
RCIC Rpe Routing Area Temperature
- High g.
RCIC Rpe Routing Area 6 Temperature
- High h.
RCIC Emergency Area Cooler Temperature
- High i.
Manual Initiation j.
Drywell Pressure
- High s10" s1.0'I s10>>'I s1.0'I s10>>'I so.5'I s10>>~I NA NA NA NA NA s10>>a)¹¹ NA NA NA s1O'I NA NA NA 10>> )¹¹¹ s1O>>'I NA NA NA NA NA NA NA s10>>>>
SUSQUEHANNA - UNIT 2 3/4 3-21 Amendment No. 93.
TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION 6.
HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION
RESPONSE
TIME Seconds 0
aO b.
C.
d.
e.f.
go h.
3 ~
HPCI Steam Flow - High HPCI Steam Supply Pressure - Low HPCI Turbine Exhaust Diaphragm Pressure - High HPCI Equipment Room Temperature - High HPCI Equipment Room h Temperature - High HPCI Emergency Area Cooler Temperature - High HPCI Pipe Routing Area Temperature - High HPCI Pipe Routing Area h Temperature - High Manual Initiation Drywell Pressure - High 1O(')
<1O(')
ih NA NA NA NA NA NA
<1O(a) 7.
RHR SYSTEM SHUTDOWN COOLING/HEAD SPRAY MODE ISOLATION a 0 b.
C.
d.
e.f.
go Reactor Vessel Water Level - Low, Level 3 Reactor Vessel (RHR Cut-in Permissive)
Pressure - High RHR Equipment Area h Temperature - High RHR Equipment Area Temperature - High RHR Flow - High Manual Initiation Drywell Pressure - High
<1O(')
NA NA NA NA NA
<1O(a)
(a) The isolation 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 qf the first electronic component in the channel.
"Isolation system instrumentation response time for NSIVs only.
No diesel generator delays assumed for MSIV Valves.
- Isolation system instrumentation response time for associated valves except NSIVso SIsolation 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.
8%ith time delay of 45 seconds.
AANith time delay of 3 seconds.
&%With time delay of 3 seconds.
SUf+JEHANNA - UNIT 2 3/4 3-22
TABLE 4.3.2.1-1 ISOLATION ACTUATION INSTRUHENTATION SURVEILLANCE RE UIRENENTS Reactor Vessel Mater Level-1)
Low, Level 3 2)
Low Low, Level 2 3)
Low Low Low, Level 1
b.
Drywell Pressure - High c.
Hanual Initiation d.
SGTS Exhaust Radiation - High e.
Hain Steai Line Radiation-High SECONDARY CONZAINIENZ ISOLATION a.
TRIP FUNCTION 1.
PRIHARY CONTAINHENZ ISOLATION CIIANNEL CIIECK NA NA CIIANNEL FUNCTIONAL TEST H
H H
H R
H CIIANNEL
. CALIBRATION R
R R
R NA R
OPERATIONAL COND IT IONS FOR NICII SURVEILLANCE RE UIRED 1, 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
3 g*k*
51*A I
1, 2, 3
V)
Dl Q.
a.
Reactor Vessel Mater Level-Low Low, Level 2 b.
Drywell Pressure
- High c.
Refuel floor High Exhaust Duct.
Radiation - High d.
. Railroad Access Shaft Exhaust Duct Radiation - High e.
Refuel Floor Mall Exhaust Duct Radiation - High f.
Hanual Initiation H
H H
R 1, 2, 3 and ",
1, 2, 3
1, 2, 3 and ~
,:,;:,.TABf,64'.3,'2;1 I,;:tCOn'ttIWed),:;.-,,;-,
TRIP. FUNCTION
- ir>:.',,r.<(<~." ~:.<
. ':..- <<< "..:va'ed@'2<<~Cr<'X5".:~~.'a4rA...;,<.'~ &z<x.,"<'"4"
~. CHANNEL
,:: QffECK
'CHANNEL~";
"-.FUNCTIONAL;,
, 'CHANNEL<';:,
CALIBIIA<TION<':,,
O<PERATION'AL"CON'nImONS'F'OR,.;:-".',:~WHICH SURVEILLANCEREQUQQljj.,
3.
AI S
a.
Reactor Veaael Water Level-Low Low Low, Level 1 1,2,3 b.
Main Steam Une Radiation - High 1,2,3 c.
Main Steam Une Preaawe - Low d.
Main Steam Une Flow - High 1,2,3 e.
Condenser Vacuum - Low NA 1,2,3 f.
Reactor Building Main Steam Une Tunnel Temperature
- High g.
Reactor Building Main Steam Une Tunnel h Temperature
- High h.
Manual Initiation i.
Turbine Building Main Steam Line Tunnel Temperature
- High C 0 C
U S
a.
RWCU h Flow - High b.
RWCU Area Temperature
- High 0
0 NA NA NA S
NA 1,2,3 1,2,3 1,2,3 1,2,3 1, 2, 3 1,2,3 c.
RWCU Area Ventilation h Temperature - High NA 1,2,3 d.
SLCS Initiation e.
Reactor Veaael Water Level-Low Low, Level 2 f.1.
RWCU Flow - High f.2.
Non-Regenerative Heat Exchanger Discharge
. Temperature
- High g.
Manual Initiation S
S NA NA 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3