ML18093A546
| ML18093A546 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/24/1987 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18093A545 | List: |
| References | |
| NUDOCS 8712300196 | |
| Download: ML18093A546 (11) | |
Text
ENCLOSURE 2 SALEM UNIT 2 REVISIONS TO TURBINE VALVE TEST FREQUENCY TECHNICAL SPECIFICATION REVISIONS
--9~,-12300 i 96 ___ 871224 ____ - - -
1 PDR ADOCK 05000272 P
. PDR
INSTRLMENTAT ION 3/4.3.4 TURBINE OVERSPEE D PROTECTION LIMITING CONDITION FOR OPERATION 3.3.4.
At least one turbine overspeed protection system shall be OPERABLE.
APPLICABILITY:
MO!ES 1, 2 and 3.
ACTION:
- a.
With one stop valve or one control valve per high pressure turbine steam lead inoperable and/or with one reheat stop valve or one reheat intercept valve per low pressure turbine steam lead inoperable, restore the inoperable valve(s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or close at least one valve in the affected steam lead; otherwise, isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- b.
With the above required turbine overspeed protection system otherwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either restore the system to OPERABLE status or isolate the turbine from the steam supply.
SURVEILLANCE REQUIREMENTS 4.3.4.1 The provisions of Specification 4.0.4 are not applicable.
4.3.4.2 The above required turbine overspeed protection system shall be demonstrated OPERABLE; (1) prior to admitting steam to the turbine during each startup unless performed within the past 7 days, (2) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of attaining greater than or equal to 85% of RATED THERMAL POWER, and (3) at a frequency not to exceed one year* by direct observation of the movement of each of the following valves through at least one complete cycle from the running position.
- a. Four high pressure turbine stop valves.
- b.
Four high pressure turbine control valves.
- c. Six low pressure hot reheat stop valves.
- d. Six low pressure hot reheat intercept valves.
- The above valves are to be tested at a frequency consistent with the methodology presented in WCAP-11525, 11Probabilistic Evaluation of Reduction in Turbine Valve Test Frequency 11, and in accordance with the established NRC acceptance criteria for the probability of a missile ejection incident of 1.0 X 10-5 per year, in no case shall the test interval for the above valves exceed one year.
SA LEM -
UN IT 2 3/4 3-65
INSTR Uv1ENTAT ION SURVEILLANCE REQUIREMENTS (Continued) 4.3.4.3 The above referenced turbine overspeed protection system shall be demon st rated OPERABLE:
- a.
At least once per 18 months by performance of a CHANNEL CALIBRATION on the turbine overspeed protection systems.
- b.
At least once per 40 months by disassembly at least one of each of the above valves and performing a visual and surface inspection of valve seats, disks and steams and verifying no unacceptable flaws or corrosion.
4.3.4.4 Verify the test frequency maintains the probability of a missile ejection incident within NRC guidelines by reviewing the methodology presented in WCAP-11525:
- a.
At least once every two refueling outages.
- b. After modifications to the main turbine or turbine overspeed protection valves.
SALEM - UNIT 2 3/4 3-66
INSTR LMENTAT ION BASES 3.4. 3.3. 8 RADIOACTIVE LIQUID EFFLUENT MON !TOR ING INSTRlJv1ENTAT ION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the procedures in the O!:IM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.
The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50. The purpose of tank level indicating devices is to assure the detection and control of leaks that if not controlled could potentially result in the transport of radioactive materials to UNRESTRICTED AREAS.
3/4.3.3.9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRlJv1ENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the procedures in the O!:IM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures.in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
3/4.3.4 TURBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed.
Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety-related components, equipment or structures.
To prevent double shocking the turbine, valve testing is not required when steam is being admitted to the turbine and THERMAL POWER is less than 85% of RATED THERMAL POWER, provided the valves are tested prior to startup and within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of attaining 85% of RATED THERMAL POWER.
SA LEM -
UN IT 2 B3/4 3-3
During normal power operation, turbine valve testing is performed at a frequency consistent with the methodology presented in WCAP-11525, 11Probabilistic Evaluation of Reduction in Turbine Valve Test Frequency.
11 This report evaluates the contribution of failure or unavailability of the turbine valve safety function to the probability that the turbine will overspeed and eject a missile.
It concludes that extended intervals between turbine valve functional tests can be achieved without exceeding the NRC acceptance criteria for the probability of a turbine missile ejection incident. Factors which affect the selected valve test interval include low pressure turbine rotor type and inspection interval; turbine valve type, arrangement and overspeed controls; and secondary side water chemistry.
SA LEM -
UN IT 2 B3/4 3-3a
ENCLOSURE 3 SALEM UNIT 1 ADDITION OF TURBINE VALVE TEST FREQUENCY TECHNICAL SPECIFICATIONS
I,
\\
INII:X LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION 3/4.2 3/4.2.1 3/4.2.2 3/4.2.3 3/4.2.4 3/4.2.5 3/4.3 3/4.3.1 3/4.3.2 3/4.3.3 3/4.3.4 SA LEM - UNIT 1 POWER DISTRIBUTION LIM ITS AXIAL FLUX HOT CHANNEL FACTOR HEAT F LUX HOT CHANNEL FACTOR ***********************
NUCLEAR ENTHALPY HOT CHANNEL FACTOR ****************
QUAffiANT POWER TILT RATIO **************************
008 PARAMETERS *************************************
INSTRUMENTATION REACTOR TRIP SYSTEM INSTRLMENTATION ****************
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM PAGE 3/4 2-1 3/4 2-5*
3/4 2-9 3/4 2-11 3/4 2-13 3/4 3-1 INSTRLMENTATION ************************************
3/4 3-14 MONITORING INSTRLMENTATION Radiation Monitoring Instrumentation ****************
Movable Incore Detectors ****************************
Seismic Instrumentation *****************************
Meteorological **************************************
Remote Shutdown Instrumentation *********************
Fire Detection Instrumentation **********************
Accident Monitoring Instrumentation *****************
Radioactive Liquid Effluent Monitoring Instrumentation Radioactive Gaseous Effluent Monitoring Instrumentation 3/4 3-35 3/4 3-39 3/4 3-40 3/4 3-43 3/4 3-46 3/4 3-49 3/4 3-53 3/4 3-58 3/4 3-64 TURBINE OVERSPEED PROTECTION ************************
3/4 3-70 IV
INDEX BASES SECTION PAGE 3/4.3 INSTRUMENTATIOO 3/4.3.1 PROTECTIVE INSTRI.MENTATICN......................... B 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEA'IURES (ESF)
INSTRlJ.1.ENTATICN *********************************** B 3/4 3-F 3/4.3.3 MONI'IDRING INSTRlNENTATICN ************************* B 3/4 3-1'.
3/4.3.4
'!URBINE OVERSPEED PRYI'ECTICN *********************** B 3/4 3-4 3/4.4.4 REAC'IDR COOIANT SYSTEM 3/4.4.1 REACIOR COOLANT IOOPS AND COOLANT CIRCUIATIOO...... B 3/4 4-1 3/4.4.2 SAFETY VALVES...................................... B 3/4 4-la 3/4.4.3 RELIEF VALVES...................................... B 3/4 4-la 3/4.4.4 PRESSURIZER****************************************
B 3/4 4-2 3/4.4.5 STE.AM GENERA'IDRS
~ ********************************** B 3/4 4-2 3/4.4.6 REACIOR COOLANT SYS'fEM LEAKAGE ********************* B 3/4 4-3 3/4.4.7 CHEMISTRY.......................................... B 3/4 4-4 3/4.4.8 SPECIFIC ACTIVITY.................................. B 3/4 4-5 3/4.4.9 PRESSURE/I'EMPERA'IURE LIMI'IS........................ B 3/4 4-6 3/4.4.10 STRUCWRAL INTEGRITY............................... B 3/4 4-12 SALEM - UNIT 1 XII
INSTR LMENTAT ION 3/4.3.4 TURBINE OVERSPEE D PROTECTION LIMITING CONDITION FOR OPERATION 3.3.4 At least one turbine overspeed protection system shall be OPERABLE.
APPLICABILITY:
MO !ES 1, 2 and 3.
ACTION:
- a.
With one stop valve or one control valve per high pressure turbine steam lead inoperable and/or with one reheat stop valve or one reheat intercept valve per low pressure turbine steam lead inoperable, restore the inoperable valve(s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or close at least one valve in the affected steam lead; otherwise, isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- b.
With the above required turbine overspeed protection system otherwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either restore the system to OPERABLE status or isolate the turbine from the steam supply.
SURVEILLANCE REQUIREMENTS 4.3.4.1 The provisions of Specification 4.0.4 are not applicable.
4.3.4.2 The above required turbine overspeed protection system shall be demonstrated OPERABLE; (1) prior to admitting steam to the turbine during each startup unless performed within the past 7 days, (2) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of attaining greater than or equal to 85% of RATED THERMAL POWER, and (3) at a frequency not to exceed one year* by direct observation of the movement of each of the following valves through at least one complete cycle from the running position.
- a.
Four high pressure turbine stop valves.
- b.
Four high pressure turbine control valves.
- c. Six low pressure hot reheat stop valves.
- d.
Six low pressure hot reheat intercept valves.
- The above valves are to be tested at a frequency consistent with the methodology presented in WCAP-11525, "Probabilistic Evaluation of Reduction in Turbine Valve Test Frequency 11
, and in accordance with the established NRC acceptance criteria for the probability of a missile ejection incident of 1.0 X 10-5 per year, in no case shall the test interval for the above valves exceed one year.
SA LEM -
UN IT 1 3/4 3-70 1
INSTR UvlENTAT ION SURVEILLANCE REQUIREMENTS (Continued) 4.3.4.3 The above referenced turbine overspeed protection system shall be demon st rated OPERABLE:
- a.
At least once per 18 months by performance of a CHANNEL CA LIB RAT ION on the turbine overs peed protection systems.
- b.
At least once per 40 months by disassembly at least one of each of the above valves and performing a visual and surface inspection of valve seats, disks and steams and verifying no unacceptable flaws or corrosion.
4.3.4.4 Verify the test frequency maintains the probability of a missile ejection incident within NRC guidelines by reviewing the methodology presented in WCAP-11525:
- a.
At least once every two refueling outages.
- b.
After modifications to the main turbine or turbine overspeed protection valves.
SALEM - UNIT 1 3/4 3-71
INSTR LMENTAT ION BASES 3/4.3.4 TURBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed. Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety-related components, equipment or structures.
To prevent double shocking the turbine, valve testing is not required when steam is being admitted to the turbine and THERMAL POWER is less than 85% of RATED THERMAL POWER, provided the valves are tested prior to startup and within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of attaining 85% of RATED THERMAL POWER.
C:Uring normal power operation, turbine valve testing is performed at a frequency consistent with the methodology presented in WCAP-11525, 11Probabilistic Evaluation of Reduction in Turbine Valve Test Frequency.
11 This report evaluates the contribution of failure or unavailability of the turbine valve safety function to the probability that the turbine will overspeed and eject a missile.
It concludes that extended intervals between turbine valve functional tests can be achieved without exceeding the NRC acceptance criteria for the probability of a turbine missile ejection incident. Factors which affect the selected valve test interval include low pressure turbine rotor type and inspection interval; turbine valve type, arrangement and overspeed controls; and secondary side water chemistry.
SA LEM -
UN IT 1 B3/4 3-4