ML021410288
| ML021410288 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 05/17/2002 |
| From: | NRC/NRR/DLPM |
| To: | |
| References | |
| TAC MB2007 | |
| Download: ML021410288 (5) | |
Text
RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.1.1.11 Verify Turbine Stop Valve - Closure and 18 months Turbine Control Valve Fast Closure, Trip Oil Pressure - Low Functions are not bypassed when THERMAL POWER is > 28% RTP.
SR 3.3.1.1.12 Perform CHANNEL FUNCTIONAL TEST.
18 months SR 3.3.1.1.13
NOTES--------------
- 1.
Neutron detectors are excluded.
- 2.
For Function 1, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2.
Perform CHANNEL CALIBRATION.
18 months SR 3.3.1.1.14 (Not used.)
SR 3.3.1.1.15 Perform LOGIC SYSTEM FUNCTIONAL TEST.
18 months SR 3.3.1.1.16
NOTES
- 1.
Neutron detectors are excluded.
- 2.
(Not used.)
- 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 limits.
18 months on a STAGGERED TEST BASIS (continued)
AMMENT NO. 173 HATCH UNIT 2 I
3.3-5
RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 2 of 3)
Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE
- 2.
Average Power Range Monitor (continued)
- e.
Two-out-of-Four Voter
- f.
OPRM Upscale
- 3.
Reactor Vessel Steam Dome Pressure - High
- 4.
Reactor Vessel Water Level Low, Level 3
- 5.
Main Steam Isolation Valve Closure
- 6.
Drywell Pressure - High
- 7.
Scram Discharge Volume Water Level - High
- a.
Resistance Temperature Detector
- b.
Float Switch 1,2 1
1,2 1,2 1
1,2 1,2 5(a) 1,2 5(a) 2 3(c) 2 2
8 2
2 2
2 2
G SR 3.3.1.1.1 SR 3.3.1.1.10 SR 3.3.1.1.15 SR 3.3.1.1.16 1
SR 3.3.1.1.1 SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.13 SR 3.3.1.1.17 G
SR 3.3.1.1.1 SR 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.15 G
SR 3.3.1.1.1 SR 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.15 F
SR 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.16 G
SR 3.3.1.1.1 SR 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.15 G
SR 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.15 H
SR 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.15 G
SR 3.3.1.1.13 SR 3.3.1.1.15 H
SR 3.3.1.1.13 SR 3.3.1.1.15 (continued)
(a)
With any control rod withdrawn from a core cell containing one or more fuel assemblies.
(c)
Each APRM channel provides inputs to both trip systems.
AXETDNT-,-ii NO.
173 HATCH UNIT 2 NA NA
- 1085 psig
> 0 inches
< 10% closed 5 1.92 psig
< 57.15 gallons 5 57.15 gallons
- 57.15 gallons
< 57.15 gallons 3.3-8
RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.16 (continued)
REQUIREMENTS overlapping segments, with verification that all components are tested. The RPS RESPONSE TIME acceptance criteria are included in Reference 10.
RPS RESPONSE TIME for APRM two-out-of-four Voter Function 2.e includes the output relays of the voter and the associated RPS relays and contactors. (The digital portions of the APRM and two-out-of-four voter channels are excluded from RPS RESPONSE TIME testing because self-testing and calibration check the time base of the digital electronics.) Confirmation of the time base is adequate to assure required response times are met. Neutron detectors are excluded from RPS RESPONSE TIME testing because the principles of detector operation virtually ensure an instantaneous response time.
Note 1 allows neutron detectors to be excluded from RPS RESPONSE TIME testing because the principles of detector operation virtually ensure an instantaneous response time.
RPS RESPONSE TIME tests are conducted on an 18 month STAGGERED TEST BASIS. Note 3 requires STAGGERED TEST BASIS Frequency to be determined based on four channels per trip 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.
Note: SR 3.3.1.1.16 for Function 2.e confirms the response time of that function, and also confirms the response time of loop components common to APRM - Two Out Of Four Voter logic and other RPS loops.
SR 3.3.1.1.17 This SR ensures that scrams initiated from OPRM Upscale Function 2.f will not be inadvertently bypassed when THERMAL POWER, as indicated by APRM Simulated Thermal Power, is
> 25% RTP and core flow, as indicated by recirculation drive flow, is
< 60% rated core flow. This normally involves confirming the bypass setpoints. Adequate margins for the instrument setpoint methodologies are incorporated into the actual setpoint. The actual (continued)
REVISION 34 HATCH UNIT 2 B 3.3-30
RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.17 (continued)
REQUIREMENTS Surveillance ensures that the OPRM Upscale Function is enabled (not bypassed) for the correct values of APRM Simulated Thermal Power and recirculation drive flow. Other Surveillances ensure that the APRM Simulated Thermal Power and recirculation flow properly correlate with THERMAL POWER and core flow, respectively.
If any bypass setpoint is nonconservative (i.e., the OPRM Upscale Function is bypassed when APRM Simulated Thermal Power is > 25%
and recirculation drive flow is < 60% rated), then the affected channel is considered inoperable for the OPRM Upscale Function.
Alternatively, the bypass setpoint may be adjusted to place the channel in a conservative condition (unbypass). If placed in the unbypass condition, this SR is met and the channel is considered OPERABLE.
The 18 month Frequency is based on engineering judgment and component reliability.
REFERENCES
- 1.
FSAR, Section 7.2.
- 2.
FSAR, Chapter 15.
- 3.
FSAR, Section 6.3.3.
- 4.
FSAR, Supplement 5A.
- 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.
NEDO-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.
(continued)
REVISION 34 HATCH UNIT 2 B 3.3-31
RPS Instrumentation B 3.3.1.1 BASES REFERENCES
- 12.
NEDO-32291, "System Analyses for Elimination of Selected (continued)
Response Time Testing Requirements," January 1994.
- 13.
NEDC-3241OP-A, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM) Retrofit Plus Option III Stability Trip Function," October 1995.
- 14.
NEDO-31960-A, "BWR Owners' Group Long-Term Stability Solutions Licensing Methodology," November 1995.
- 15.
NEDO-31960-A, Supplement 1, "BWR Owners' Group Long-Term Stability Solutions Licensing Methodology,"
November 1995.
- 16.
NEDO-32465-A, "BWR Owners' Group Long-Term Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications," March 1996.
- 17.
NEDO-32410P-A, Supplement 1, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM) Retrofit Plus Option III Stability Trip Function,"
November 1997.
- 18.
Letter, L.A. England (BWROG) to M.J. Virgilio, "BWR Owners' Group Guidelines for Stability Interim Corrective Action,"
June 6, 1994.
- 19.
NEDO-32291 -A, Supplement 1, "System Analyses for the Elimination of Selected Response Time Testing Requirements," October 1999.
HATCH UNIT 2 B 3.3-32 REVISION 34