ML20091N774
| ML20091N774 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/23/1995 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20091N777 | List: |
| References | |
| NUDOCS 9508310268 | |
| Download: ML20091N774 (23) | |
Text
..
- UNITED STATES y
- NUCLEAR REGULATORY COMMISSION :
"*g WASHINGTON, D.C. 20seH001 GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA
.I CITY OF DALTON. GEORGIA DOCKET NO. 50-366..
EDWIN 1. HATCH NUCLEAR PLANT. UNIT 2
'I AMiNDMENT TO FACILITY OPERATING LICENSE-
-Amendment No.
'137-License No. NPF-5 1.
The Nuclear Regulatory Commission (the Commission).has found that:
A.
The application for _ amendment to the Edwin I. Hatch Nuclear Plant, Unit 2-(the facility) Facility Operating License No.:NPF-5 filed.
by the. Georgia Power Company, acting for itself, Oglethorpe Power.
Corporation, Municipal Electric-Authority..of Georgia,.and City.of.
Dalton, Georgia (the licensees), dated April 14, 1995, as supplemented by letters dated June 22 and July 18, 1995, complies with the standards and. requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and:
regulations as set forth in 10 CFR Chapter I; 4
B.
The facility will operate in conformity with the' application, the provisions' of the Act, and the rules and regulations of the Commission, 4
i C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted.without endangering the health and safety of the public, and -(11) that such activities will.be conducted in compliance with the Commission's regulations set i
forth in 10 CFR Chapter I-
..~
'1 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.
9508310268 950823 PDR ADOCK 05000366 P
PDR n.
,, n.. a. _._ -.
t i
- 2; Accordinglyi the license is hereby amended by page' 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-5
.is.hereby amended'to read as follows:
Technical Soecifications
- The Technical Specifications contained in Appendices A and B, as-revised.through-Amendment No. '137,' are hereby incorporated ire the license.. The licensee shall operate the-facility in accordance with the Technical Specifications.
3.-
This license amendment:is effective as of its date of issuance' and shall be implemented within 60 days from the dateLof issuance.
FOR THE NUCLEAR REGULATORY COMMISSISN--
i r
rbert-N. Berkow, Director Project Directorate'11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor.P.egulation
Attachment:
Technical Specification
.i Changes LDate of Issuance: August 23, 1995 e
ATTACMENT TO LICENSE AMENDMENT NO.137 FACILITY OPERATING LICENSE NO. NPF DOCKET NO. 50-366 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines-indicating the areas of change.
Remove Paaes Insert Paaes 3.3-6.
3.3-6 3.3-41 3.3-41 3.3-42 3.3-42 3.3-43 3.3-43 3.3-44 3.3-44 3.3-55 3.3-55 3.5-6 3.5-6 3.5-6a 3.5-6b B 3.3-31 8 3.3-31 B 3.3-31a B 3.3-31b B 3.3-32 B 3.3-32 B 3.3-105 B 3.3-105 B 3.3-133 8 3.3-133 B 3.3-134 8 3.3-134 B 3.3-174 8-3.3-174 8 3.5-16 B 3.5-16 B 3.5-16a B 3.5-16b I
RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.1.1.16
NOTES------------------
1.
Neutron detectors are excluded.
2.
For Functions 3 and 4, channel i
sensors are excluded.
I 3.
For Function 5, "n" equals 4 channels for the purpose of determining the STAGGERED TEST BASIS Frequency.
Verify the RPS RESPONSE TIME is within 18 months on a limits.
STAGGERED TEST BASIS HATCH UNIT 2 3.3-6 Amendment No.137 I
1
ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS
NOTES------------------------------------
1.
Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.
2.
When a channel.is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 3.c and 3.f; and (b) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions other than 3.c.and 3.f provided the associated Function or the redundant Function maintains initiation capability.
SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST.
92 days SR 3.3.5.1.3 Perform CHANNEL CALIBRATION.
92 days SR 3.3.5.1.4 Perform CHANNEL CALIBRATION.
18 months SR 3.3.5.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST.
18 months I
i l
I l
1 I
HATCH UNIT 2 3.3-41 Amendment No.137
~
ECCS Instrumentation
.3.3.5.1-
+
Table 3.3.5.1 1 (pege 1 of 6)~
Emergency Core Cooling system Instrumentation APPLICAgLE-CouclTIONS MODES REQUIRED REFERENCE 0 0E OtMER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWASLE FUNCTION CON 0lfl0Ns FUNCTION ACTION A.1 REeulREMENTS VALUE 1.
Core sprey system e.
Reector vesset Wetec 1,2,3, 4(b)
B SR 3.3.5.1.1 m 113 inches Level - Low Low Low, SR 3.3.5.1.2
. (*I,$(83 sa 3.3.5.1.4 Level 1 4
st 3.3.5.1.5 I:
b.
Drywell 1,2,3 4(b) 8 sa 3.3.5.1.1 s 1.92 pelg Pre 6sure - Migh sa 3.3.5.1.2 SA 3.3.5.1.4
. SR 3.3.5.1.5 I
~
c.
Reactor steen Dome 1,2,3 4
C
$4 3.3.5.1.1 4.390 psis Pressure - Low sa 3.3.5.1.2 and (Injection Peralasive) st 3.3.5.1.4 s 4;'6 pets
$4 3.3.5.1.5 1
4(a), 5(*)
4 s
sa 3.3.5.1.1-t 390 pelg SR 3.3.5.1.2 and SR 3.3.5.1.4 s 476 pels-sa -3.3.5.1.5 l
d.
Core spray Pusp 1,2,3, 1 per E
sa 3.3.5.1.1 t 570 spa Discharge F Low - Low subsystem SA 3.3.5.1.2 and l
(sypese) 4(s), $(s).
$4 3.3.5.1.4
.s 745 som i
st 3.3.5.1.5 2.
Low Pressure Coolant injection (LPCI) system a.
Reactor vesset Water 1,2,3, 4(b) e SR 3.3.5.1.1 t 113 inches Level - Low Low Low,
$2 3.3.5.1.2 Level 1-4(83, 5(*I sa 3.3.5.1.4 a
st.3.3.5.1.5
. g (continued)
(at When associated s esystem(s) are required to be OPERAELE.
(b) Also required to initiate the associated diesel generator (DG) and isolate the associated plant service wat2r (PsW) turbine building (T/s) Isolation valves.
+
a
'l HATCH UNIT 2 3.3-42 Amendment No. 137 w
6 e
.w w-a,,m.
m
ECCC Instrunntation 3.3.5.1 l
Table 3.3.5.1 1 (page 2 of 6)
Emergency Core Cooling i stem Instrumentation f
APPLICA8LE CONDITIONS NODES REQUIRED REFERENCED OR OtHCR CHANNELS FRON SPECIFIED PER REQUIRED SURVEILLANCE ALLOWASLE-FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIRENENTS VALUE 2.
LPCI system (continued) 1,2,3 4(b) s SR 3.3.5.1.1 s 1.92 pois b.
Drywett SR 3.3.5.1.2 Pressure - High SR 3.3.5.1.4 SR 3.3.5.1.5 I
c.
Reactor steam Dome 1,2,3 4
C st 3.3.5.1.1 a 390 pois Pressure - Low st 3.3.5.1.2-and (Injection Permissive) st 3.3.5.1.4 s 476 pels st 3.3.5.1.5 1
4(a),5(a) 4 s
SR 3.3.5.1.1 2 390 psig sR 3.3.5.1.2 and SR 3.3.5.1.4 5 476 pelg i
d.
Reactor steam Ocme II8) 2, ICI, 4
C
$4 3.3.5.1.1 2 335 pois Pressure - Low SR 3.3.5.1.2' (Recirculation 3(C)
SR 3.3.5.i.4 Discharge Valve SR 3.3.5.1.5 Permissive) e.
Reactor vesset throud 1,2,3 2
a sa 3.3.5.1.1 2 202 inches Level - Level 0 st 3.3.5.1.2 SR 3.3.5.1.4 st 3.3.5.1.5 f.
Low Pressure Coolant 1,2,3, 1 per C
SR 3.3.5.1.4 Injection Puip pulp SR 3.3.5.1.5 start - Time Delay 4(*3, 5(*)
Relay Puupe A,B,D t 9 seconds and s 11 seconds Pusp C 5 1 second (continued) 1 (a) When associated stbsystem(s) are required to be OPERA 8LL.
(b) Also required to initiate the associated DG and Isolate the associated PsV T/I isolation valves.
(c) With associated recirculation pump discharge valve open.
i i
i HATCH UNIT 2 3.3-43 Amendment No. 137 i
l I
ECCS Instrumentation
-3.3.5.1 Table 3.3.5.1 1 (page 3 of 6)
Emergency Core Cooling System Instrumentation APPLICABLE CON 0!TIONs M00Es OR REQUIRED REFERENCED OtNER CHANNELS FROM
$PECIFIED PER REQUIRED SURVE!LLANCJ ALLOWABLE FUNCTION CONolT10NJ FUNCTION ACTION A.1 REQUIREMENTS VALUE 2.
LPCI system (continued)
.s.
Low Pressure 1,2,3, 1 per E
sa 3.3.5.1.1 a 1475 som Cootent injection Pw p subsystem SR 3.3.5.1.2 and Olscharge Flow - Low 4(a), $ e) sa 3.3.5.1.4 s 2215 spa t
(8ypese) sa 3.3.5.1.5 3.
High Pressure Cootent Injection (NPCI) System e.
Reactor Vessel Water 1,
4 8
SR 3.3.5.1.1 t 47 inches Level - Low Low, SR 3.3.5.1.2 tevel 2 2(d), 3(d)
SR 3.3.5.1.4 SR 3.3.5.1.5 I
b.
DryweLL 1,
4 8
SR 3.3.5.1.1 s 1.92 pels Pressure - High SR 3.3.5.1.2 2(d) 3(d)
SR 3.3.5.1.4 SR 3.3.5.1.5 I
c.
Reactor vessel Water 1,
2 C
$R 3.3.5.1.1 s 56.5 inches Level - High, level 8 SR 3.3.5.1.2 2(d), 3(d) sa 3.3.5.1.4 sa 3.3.5.1.5 1
d.
Condensate Storage 1,
2 0
SR 3.3.5.1.3 a 2.61 ft Tank Level - Low SR 3.3.5.1.5 e.
Suppression Pool Water 1,
2 0
SR 3.3.5.1.1 s 154 inches Level - High SR 3.3.5.1.2 2(d), 3(d) sa 3.3.5.1.4 sa 3.3.5.1.5 (continued)
(a) When the associated stboystem(s) are required to be OPERABLE.
(d) With reactor steem dome pressure > 150 pels.
w I
HATCH UNIT 2 3.3-44 Amendment No.137
Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS
NOTES------------------------------------
1.
Refer.to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.
2.
When a channel is placed in an inoperable status solely for performance of required Surve111ances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains isolation capability.
SURVEILLANCE FREQUENCY
[
SR 3.3.6.1.1 Perform CHANNEL CHECK.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST.
92 days SR 3.3.6.1.3 Perform CHANNEL CALIBRATION.
92 days SR 3.3.6.1.4 Perform CHANNEL FUNCTIONAL TEST.
184 days SR 3.3.6.1.5 Perform CHANNEL CALIBRATION.
18 months SR 3.3.6.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.
18 months SR 3.3.6.1.7
NOTE-------------------
Channel sensors are excluded.
l Verify the ISOLATION SYSTEM RESPONSE TIME 18 months on a is within limits.
STAGGERED TEST BASIS c
HATCH UNIT 2 3.3-55 Amendment No. 137
ECCS--Operating 3.5.1 SURVEILLANCE P.EQUIREMENTS (continued)
SURVEILLANCE FREQUENCY l.'
NOTE--------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are y
l adequate to perform the test.
__________________m________________________
Verify, with reactor pressure s 165 psig, 18 months the HPCI pump can develop a flow rate 2: 4250 gpm against a system head corresponding to reactor pressure.
SR 3.5.1.10
NOTE--------------------
Vessel injection / spray may be excluded.
Verify each ECCS injection / spray subsystem 18 months actuates on an actual or simulated automatic initiation signal.
SR 3.5.1.11
NOTE--------------------
Valve actuation may be excluded.
Verify the ADS actuates on an actual or 18 months simulated automatic initiation signal.
SR 3.5.1.12
NOTE--------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.
Verify each ADS valve opens when manually 18 months
- actuated, j
i (continued)
HATCH UNIT 2 3.5-6 Amendment No. 137
ECCS-Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY l
l SR 3.5.1.13
NOTE--------------------
ECCS injection / spray initiation instrumentation response time may be assumed from established limits.
Verify each ECCS injection / spray subsystem 18 months ECCS RESPONSE TIME is within limits.
b l
l l
I HATCH UNIT 2 3.5-6a Amendment No. 137 l
L_
c_,
1
~
ECCS-Operating 3.5.1 This page intentionally left blank.
i-h I
3 HATCH UNIT 2-3.5-6b Amendment No.137 l
i k
t RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE ~
SR 3.3.1.1.14 REQUIREMENTS (continued)
The Average Power Range Monitor Flow Biased Simulated Thermal Power -- High Function uses an electronic filter circuit to generate a signal proportional to the core THERMAL POWER from the APRM neutron flux signal.
This filter circuit is representative of the fuel heat transfer dynamics that produce the relationship between the neutron flux and the core THERMAL POWER. The time constant is specified in the COLR and must be verified to ensure that the channel is accurately reflecting the desired parameter.
The Frequency of 18 months is based on engineering judgment considering the reliability of the components.
SR 3.3.1.1.15 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required trip logic for a specific channel. The functional testing of control rods (LCO 3.1.3), and SDV vent and drain valves (LCO 3.1.8),
overlaps this Surveillance'to provide complete testing of the assumed safety function.
The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.
)
Operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency, t
t SR 3.3.1.1.16 This SR ensures that the individual channel response times E
are less than or equal to the maximum values assumed in the accident analysis. This test may be performed in one measurement or in overlapping segments, with verification j
v that all components are tested.
The RPS RESPONSE TIME acceptance' criteria are included in Reference 10.
Note 1 allows neutron detectors to be excluded from RPS.
l RESPONSE TIME testing because the principles of detector I
operation virtually ensure 01 instantaneous response time.
(continued)
HATCH UNIT 2 B 3.3-31 Amendment No. 137
RPS Instrumentation B 3.3.1.1 BASES-
' SURVEILLANCE SR 3.3'l.1.16 (continued)
REQUIREMENTS Note 2 allows channel sensors for Reactor Vessel Steam Dome Pressure - High and Reactor Vessel Water Level:- Low, Level 3 (Functions 3 and 4) to be excluded from RPS RESPONSE TIME testing. -This~ allowance is supported by Reference 12 which concludes that 'any significant degradation of the channel sensor response time can be detected during the performance of other Technical Specifications SRs.
P (continued)
HATCH UNIT 2' 8 3.3-31a Amendment No. 137
RPS Instrumentation 8 3.3.1.1 i
i l
This page intentionally left blank.
l i
i HATCH UNIT 2 B 3.3-31b Amendment No. 137
F.PS Instrumentation B 3.3.1.1
~
BASES'
~
SURVEILLANCE SR 3.3.1.1.16 (continued)
REQUIREMENTS RPS' RESPONSE TIME tests are conducted on an 18 month STAGGERED TEST BASIS. Note 3 requires STAGGERED TEST BASIS l-Frequency to be determined based on four channels per trip i
system, in lieu of the eight channels specified in Table 3.3.1.1-1 for the Main Steam Line Isolation Valve-Closure Function. This Frequency is based on the logic interrelationships of the various channels required to produce an RPS scram signal. This Frequency is consistent with the typical industry refueling cycle and is based upon plant operating experience, which shows that random failures of instrumentation components causing serious response time degradation, but not channel failure, are infrequent occurrences.
REFERENCES 1.
FSAR, Section 7.2.
i 2.
FSAR,. Chapter 15.
]
3.
FSAR, Section 6.3.3.
4.
l 5.
FSAR, Section 15.1.12.
6.
NEDO-23842, " Continuous Control Rod Withdrawal in'the Startup Range," April 18, 1978.
7.
FSAR, Section 15.1.38.
8.
P. Check (NRC) letter to G. Lainas (NRC), "BWR Scram Discharge System Safety Evaluation," December 1, 1980.
9.
NED0-30851-P-A, " Technical Specification Improvement Analyses for BWR Reactor Protection System,"
March 1988.
10.
Technical Requirements Manual.
11.
NRC No.93-102, " Final Policy Statement on Technical Specification Improvements," July 23, 1993.
12.
NED0-32291, " System Analyses for Elimination of Selected Response Time Testing Requirements,"
January 1994.
1 HATCH UNIT 2 8 3.3-32 Amendment No. 137
ECCS Instrurentation 6 3.3.5.1 BASES APPLICABLE ECCS instrumentation satisfies Criterion 3 of the NRC Policy SAFETY ANALYSES, Statement (Ref. 6). Certain instrumentation Functions are l
LCO, and retained for other reasons and are described below in the APPLICABILITY individual Functions discussion.
(continued)
The OPERABILITY of the ECCS instrumentation is dependent upon the OPERABILITY of the individual instrumentation channel Functions specified in Table 3.3.5.1-1.
Each Function must have a required number of OPERABLE channels, with their setpoints within the specified Allowable Values, where appropriate. The setpoint is calibrated consistent with applicable setpoint methodology assumptions (nominal ~
trip setpoint). Table 3.3.5.1-1, footnote (b), is added to l
show that certain ECCS instrumentation Functions are also required to be OPERABLE to perform DG initiation and actuation of the PSW T/B isolation.
Allowable Values are specified for each ECCS Function specified in the table. Nominal trip setpoints are specified in the setpoint calculations.
The nominal setpoints are selected to ensure that the setpoints do not exceed the Allowable Value between CHANNEL CALIBRATIONS.
Operation with a trip setpoint less conservative than the nominal trip setpoint, but within its Allowable Value, is acceptable. A channel is inoperable if its actual trip setpoint is not within its required Allowable Value.
Trip-setpoints are those predetermined values of output at which an action should take place.. The setpoints are compared to the actual process parameter (e.g., reactor vessel water level),.and when the measured output value of the process parameter exceeds the setpoint, the associated device (e.g., trip unit) changes state. The analytic limits are derived from the limiting values of the process parameters obtained from the safety analysis, where applicable.
The Allowable Values are derived from the analytic limits,
. corrected for calibration, process, and some of the instrument errors. The trip setpoints are then determined, accounting for the remaining instrument errors (e.g., drift). The trip setpoints derived in this manner provide adequate protection because instrumentation uncertainties, process effects, calibration tolerances, instrument drift, and severe environmental effects (for channels that must function in harsh environments as defined by 10 CFR 50'.49) are accounted for.
(continued)
HATCH UNIT 2 B 3.3-105 Amendment No. 137
ECCS Instrumentatien B 3.3.5.1 BASES SURVEILLANCE SR 3.3.5.1.5 REQUIREMENTS
-(continued)
The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the i
OPERABILITY of the required initiation logic for a specific channel. The system functional testing performed in-LCO 3.5.1, LCO 3.5.2, LCO 3.7.2, LCO 3.8.1, and LC0 3.8.2 overlaps this Surveillance to complete testing of the -
assumed safety function.
The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant l
outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.
Operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency.
r v
(continued)
HATCH UNIT 2 B 3.3-133 Amendment No. 137
h ECCS Instrumentation B 3.3.5.1 BASES- (continued)
REFERENCES 1.
FSAR, Section 5.2.
2.
FSAR, Section 6.3.
3.
FSAR, Chapter 15.
4.
NEDC-31376-P, "Edwin I. Hatch Nuclear Power
- Plant, SAFER /GESTR-LOCA, Loss-of-Coolant Accident Analysis,"
December 1986.
5.
NEDC-30936-P-A, "BWR Owners' Group Technical Specification Improvement Analyses for ECCS' Actuation Instrumentation, Part 2," December 1988.
I-6.
NRC No.93-102, " Final Policy Statement on Technical Specification Improvements," July 23, 1993.
l HATCH UNIT 2' B 3.3-134 Amendment No. 137
)
i 0
Primary Containment Isolation Instrumentation B 3.3.6.1 BASES
]
SURVEILLANCE SR 3.3.6.1.7 (continued)
REQUIREMENTS ISOLATION SYSTEM RESPONSE. TIME acceptance criteria are included in Reference 6.
This test may be performed in one measurement, or_ in overlapping segments, with verification that all components are tested.
A Note to the Surveillance states that the channsi sensors are excluded from ISOLATION ' SYSTEM RESPONSE TIME testing.
The exclusion of the channel sensors is supported by Reference 8 which indicates that the sensors' response' times are a small fraction of the total response time.
Even if the sensors experienced response time degradation, they would be expected to respond in the microsecond to millisecond range until complete failure.
ISOLATION SYSTEM RESPONSE TIME tests are conducted on an 18 month STAGGERED TEST BASIS. This Frequency is consistent l
with the typical industry refueling cycle ~and is based upon plant operating experience that shows that random failures of instrumentation components causing serious response time degradation, but not channel failure, are infrequent occurrences.
REFERENCES 1.
FSAR, Section 6.3.
2.-
FSAR, Chapter 15, 3.
FSAR, Section 4.2.3.4.2.
4.
NEDC-31677P-A, " Technical Specification Improvement Analysis for BWR Isolation Actuation Instrumentation,"
July 1990.
5.
NEDC-30851P-A Supplement 2, " Technical Specifications Improvement Analysis for BWR Isolation Instrumentation Common to RPS and ECCS Instrumentation," March 1909.
6.
Technical Requirements Manual.
7.
NRC No.93-102, " Final Policy Statement on Technical Specification Improvements," July 23, 1993.
8.
NE00-32291, " System Analyses for Elimination of -
Selected Response Time Testing Requirements,"
January 1994.
HATCH UNIT 2 B'3.3-174 Amendment No. 137
-m 93.(b ECCS. - Operating' 4:
B 3.5.1 -
_. BASES H
SURVEILLANCE SR'3.5.1.12 (continued)
REQUIREMENTS-SR when performed at the 18' month Frequency, which is' based.
on the refueling cycle. Therefore, the Frequency _was concluded to be acceptable'from a reliability standpoint..
SR 3.5.1.13 This SR ensures that the ECCS RESPONSE TIMES are less-than or equal to the maximum values assumed in'the accident analysis. Response time testing acceptance criteria are.
)
included in Reference 14. A Note to the Surveillance states that the instrumentation portion of the response time may be.
assumed from established limits. The exclusion of the instrumentation from the response time' surveillance is supported by Reference 15, which concludes that-instrumentation will continue to respond in the microsecond to millisecond range prior to complete failure.
The 18 month Frequency is based on the need to perform the Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.
Operating experience has'shown that these components usually i
pass the SR when performed at the~18 month Frequency, which 1
is based on the refueling cycle. Therefore, the Frequency i
was concluded to be acceptable from a reliability standpoint.
REFERENCES 1.
FSAR, Section 6.3.2.2.3.
2.
FSAR, Section 6.3.2.2.4.
3.
FSAR, Section 6.3.2.2.1.
4.
FSAR,'Section 6.3.2.2.2.
5.
FSAR, Section 15.1.39.
6.
FSAR, Section 15.1.40.
7.
FSAR, Section 15.1.33.
(continued)
' HATCH UNIT 2 8 3.5-16 Amendment No. 137
-m,..
,---,,.-e.
..m r-e
.,w r -,
c-
,--m- - -
, - ~,
n
ECCS Operating-B 3.5.1 BASES REFERENCES-8.
(continued) 9.
FSAR, Section 6.3.3.
- 10. NEDC-31376P,'"E.I. Hatch Nuclear Plant-Units 1 and 2 SAFER /GESTR-LOCA Loss-of-Coolant Analysis,"
December 1986.
- 11. :10 CFR 50.46.
- 12. Memorandum from R.L. Baer (NRC) to V. Stello, Jr.
(NRC), " Recommended Interim Revisions to LCOs for ECCS Components," December 1, 1975,
- 13. NRC No.93-102, " Final Policy Statement on Technical Specification Improvements," July 23, 1993.
- 14. Technical Requirements Manual.
- 15. NED0-32291, " System Analyses for Elimination of Selected Response Time Testing Requirements,"
January 1994.
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