ML17157C527
| ML17157C527 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 10/19/1993 |
| From: | Larry Nicholson Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17157C528 | List: |
| References | |
| NUDOCS 9310280268 | |
| Download: ML17157C527 (11) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055~00I NSYLV IA POM R
GK COMPANY G
E TR C
COO RAT INC DOCKET NO. 50-387 SUS UEKANNA STEAM ELECTRIC STATION UNIT 1 AM NT 0
C 0 ERATI G
C S
Amendment No.
130 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 May 17,
- 1993, as supplemented by letter dated October 7, 1993, 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.
qS10280268 SOO0387 PDR PDOCN. o p
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2.
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-14 is hereby amended to read as follows:
(2) ica ec
'c t s
v et ot t The Technical Specifications contained in Appendix A, as revised through Amendment No.
130 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PPLL 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 and is to be implemented prior to startup in Cycle 8, currently scheduled to occur November 4, 1993.
FOR THE NUCLEAR REGULATGRY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 19.
1993 Larr
. Nicholson, Acting Director Pro ct Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
TTACHMEN TO LICENSE AMENOMENT NO. 130 CI IT OP T NG CE S
NO
-14 QODcK 0
5 -3 1 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.*
lEKHl 3/4 3-27 3/4 3-28 3/4 3-29 3/4 3-29a 3/4 5-5 3/4 5-5a 3/4 3-27*
3/4 3-28 3/4 3-29*
3/4 3-29a 3/4 5-5 3/4 5-Sa*
INSTRUMENTATION 3/4. 3. 3 MERGENCY CORE COOLING SYSTE ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3 The emergency core cooling system (ECCS) actuation instrumentation channels shown in Table 3.3.3-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.3-2 and with EMERGENCY CORE COOLING SYSTEM RESPONSE TIME as shown in Table 3.3.3-3.
APPLICABILITY:
As shown in Table 3.3.3-1.
ACTION:
a.
b.
With an ECCS actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.3-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Sqtpoint value.
With one or more ECCS actuation instrumentation channels inoperable, take the ACTION required by Table,',3.3.3-1.
SURVEILLANCE RE UIREMENTS 4.3.3. 1 Each ECCS actuation instrumentation channel shall be demonstra ed OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAl. TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the requencies shown in Table 4.3.3.1-1.
4.3.3.2 lOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.
4.3.3.3 The ECCS
RESPONSE
TIME of each ECCS trip function shown in Table 3.3.3-3 shall be demonstrated to be within the limit at least nrce per 18 months.
Each test shall include at least one channel per trip system such that all channels are tested at least once every N times 18 months whe~e N is the total number of redundant channels in a specific ECCS trip system.
SUSQUEHANNA - UNIT 1 3/4 3-2?
r/)C U)
QCmz zZ I
CZ TRIP FUNCTION MINIMUMOPERABLE Cl(ANNELS PER TRIP. SYSTEM APPUCABLE OPERATIONAL CONDITIONS 1.
CORE SPRAY SYSTEM a.
Reactor Vessel Water Level - Low Low Low, Level 1 2(a) 1,2,3,4,5 TABLE3.3.3-1 EMERGENCY CORE COOLING SYSTEM ACTUATIONINSTRUMENTATION ACTION 30 b.
Drywell Pressure
- High c.
Reactor Vessel Steam Dome Pressure - Low (Permissive) d.
Manual Initiation 2(a) 2(a) 1/subsystem 1,2,3 1,2,3, 4,5 1,2,3,4,5 30 31 32 33 Ca)
D Ca) co CL z0 2.
LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM a.
Reactor Vessel Water Level - Low Low Low, Level 1
b.
Drywell Pressure - High c.
Reactor Vessel Steam Dome Pressure - Low (Permissive)
- 1) System Initiation
- 2) Recirculation Discharge Valve Closure
- d. - Manual Initiation 3.
HIGH PRESSURE COOLANT INJECTION SYSTEM a.
Reactor Vessel Water Level - Low Low, Level 2 b.
Drywell Pressure - High c.
Condensate Storage Tank Level - Low
~ 0 ~
d.
Suppression Pool Water Level - High e.
Reactor Vessel Water Level - High, Level 8 t.
Manual Initiation 2(a) 2(a) 2(a) 2(a) 1/subsystem 2(a) 2(s) 2(a)(b) 2(a) 2(cl 1/system 1, 2, 3, 4
, 5 1,2,3
- 1. 2, 3 4,5 1,2,3 4,5 1,2,3,4,5 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 30 30 31 32 31 32 33 30 30 34 34 31 33
t/ICt/I0 ZZ Z
TSP FUNCTION MINIMUMOPERABLE CHANNELS PER TRIP SYSTEM APPLICABLE OPERATIONAL CONDITIONS 4.
AUTOMATICDEPRESSURIZATION SYSTEM ss a.
~ Low Low Low, Level I 2 ill I. 2. 3 TABLE3.3.3-1 (Continued)
EMERGENCY CORE COOLING SYSTEIN ACTUATIONINSTRUMENTATION ACTION 30 Ca)
Gl hJ tO b.
Drywell Pressure
~ High c.
ADS Timer d.
Core Spray Pump Discharge Pressure
- High IPermissive) e.
RHR LPCI Mode Pump Discharge Pressure
- High
)Permissive)
I.
~ Low. Level 3 )Permissive) g.
ADS Drywell Pressure Bypass Timer h.
Manual Inhibit i.
Manual Initiation 2Ill 2(dl(l) 2ldl(e)ill 2III 1/valve
- l. 2. 3 I, 2. 3 I. 2, 3 I. 2. 3
- l. 2. 3
- 1. 2, 3
- l. 2. 3
- 1. 2, 3 30 31 31 31 31
. 33 33 TOTAL NO.
OF CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE OPERATIONAL CONDITIONS ACTION 5.
LOSS OF POWER 3
CL 3
tV Z0 l~
a.
4.16 kv ESS Bus Under. voltage ILoss ol Voltage, < 20%)
b.
4.16 kv ESS Bus Under voltage
{Degraded Voltage, < 65%)
c.
4.16 kv ESS Bus Under voltage
)Degraded Voltage, < 93%)
d.
'480V ESS Bus 08565 Under voltage
)Degraded Voltage, < 65%) alt e.
480V ESS Bus 08565 Under voltage
)Degraded Voltage, < 92%)
See Iootnotes on next page.
1/bus 2/bus 2/bus 2/bus 2/bus I/bus 2/bus 2/bus I/bus 2/bus 1/bus 2/bus 2/bus 2/bus 2/bus 1.2.3.4
.5 1,2,3,4,5 I, 2. 3, 4, 5 1,2,3,4
.5
- 1. 2,3,4,5 35 36 36 36 3li
C DC zz I
Cz TABLE 3.3.3-t (Continued)
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION (a)
A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter.
(b)
One trip system.
Provides signal to HPCI pump suction valves only.
(c)
Two out of two logic.
(d)
Either 4d or 4e must be satisfied.
The ACTION is required to be taken only if neither is satisfied.
A channel is not OPERABLE unless its associated pump is OPERABLE per Specification 3.5.1.
Ca) td CO (e)
Within an ADS Trip System there are two logic subsystems, each of which contains an overall pump permissive.
At least one channel associated with each of these overall pump permissives shall be OPERABLE.
(f)
A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance testing provided that all channels in the other trip system are OPERABLE.
When the system is required to be OPERABLE per Specification 3.5.2 Not required to be OPERABLE when reactor steam dome pressure is less than or equal to 150 psig.
Required when ESF equipment is required to be OPERABLE.
¹¹ Not required to be OPERABLE when reactor steam dome pressure is less than or equal to 100 psig.
3 Q.
3 z0 Required to be OPERABLE only when Diesel Generator E is either aligned to the Class 1E system or not aligned to the Class 1E system but operating on the Test Facility.
The automatic transfer of HPCI pump suction from the condensate storage tank to suppression pool on high suppression pool water level occurs only when HPCI injection valve is open.
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS Continued 2.
For the HPCI system, verifying that the system develops a flow of at least 5000 gpm against a test line pressure of greater than or equal to 245 psig when steam is being supplied to the turbine at 150 ~ 15 psig 3.
Performing a CHANNELCALIBRATIONof the CSS header hP instrumentation and verifying the setpoint to be 6 1 psid.
4.
Verifying that the suction for the HPCI system is automatically transferred from the condensate storage tank to the suppression chamber either on a suppression chamber water level-high signal when HPCI injection valve is open, or on a condensate storage tank water level - low signal.
5.
Performing a CHANNEL CALIBRATION of the condensate transfer pump discharge low pressure alarm instrumentation and verifying the low pressure alarm setpoint to be ~ 113 psig.
d.
For the ADS:
- 1. At least once per 31 days, performing a CHANNEL FUNCTIONALTEST of the accumulator backup compressed gas system low pressure alarm system.
- 2. At least once per 18 months:
a)
Performing a system functional test which includes simulated automatic actuation of the system throughout its emergency operating sequence, but excluding actual valve actuation.
b)
Manually opening each ADS valve when the reactor steam dome pressure is greater than or equal to 100 psig and observing that either:
1)
The control valve or bypass valve position responds accordingly, or 2)
There is a corresponding change in the measured steam flow.')
Performing a
CHANNEL CALIBRATION of the accumulator backup compressed gas system low pressure alarm systems and verifying air alarm setpoint of 2070 k 35 psig on decreasing pressure.
- e. At least every 18 months the following shall be accomplished by any series of sequential, overlapping or total channel steps such that the entire channel is tested:
The provisions of Specification 4.0.4 are not applicable provided the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the test.
ADS solenoid energization shall be used alternating between ADS Division 1 and ADS Division 2.
SUSQUEHANNA - UNIT 1 3/4 5-5 Amendment No.
130
94ERGENCY CORE COOLING SYSTEMS SURVEILLANCE IRE%NTS Contf nued I.,
A funct)onal test of the )nterlocks assoc)ated ~th LPCI CS puap starts
$ n response to an aubmt$ c )nit)at1on s)gnal
$ n Unft I followed by a "False" autoaat$ c )nest)at)on s)gnal
$ n Unft 2.
2.
A functional test of the Interlocks associated with LPCI and CS puep starts
$ n response to an automat)c
)n$ t$ at$ on signal
$ n Un)t 2 followed by a "False" autoeatfc 3n$ tfatfon s)gnal
$ n Unkt 1.
3.
A functional test of the )nterlocks assoc)ated with LPCI and CS puap starts
$ n response to sfaultaneous occurrence of an autoaat$ c
$ n$ t$ at$ on s)gnal
$ n both Un)t 1 and Unit 2 and a Loss-of-Offs)te-Power condkt)on affect$ ng both Un)t 1 and Un)t 2.
UNIT 1 3/i 5-Sa Haunt No. 112 4NNt m