ML20207S444
| ML20207S444 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 03/13/1987 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20207S443 | List: |
| References | |
| NLS-86-225, NUDOCS 8703190462 | |
| Download: ML20207S444 (8) | |
Text
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0 ENCLOSURE 1 TO NLS-86-225 PROPOSED TECHNICAL SPECIFICATION PAGES BRUNSWICK-1 JET PUMP SURVEILLANCE REQUIREMENTS (84TSB32) t 8703190462 870313 (3976 MAT /bac)
PDR ADOCK 05000324 P
SUMMARY
LIST OF REVISIONS BRUNSWICK-1 PAGE NO.
DESCRIPTION 3/44-2 Item 4.4.1.2 - Reword to read "Each of the above required jet pumps shall be demonstrated Operable af ter entering Operational Condition I but prior to thermal power exceeding 25% of Rated Thermal Power and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter by verifying the at least 2 of the following conditions do not occur:".
Item 4.4.1.2.a - Change "10%" to "5%".
Item 4.4.1.2.b - Replaced with "The jet pump loop flow differs by more than 5% from the established speed-flow characteristics."
Item 4.4.1.2.c - Change "... from the mean of all jet pump differential pressure, in that loop, by more than 10%." to "... by more than 10%
from that jet pump's established operating characteristics.
Change CONDITIONS to OPERATIONAL CONDITIONS.
B 3/4 4-1 Bases - Add paragraph to describe the method used to establish the acceptance criteria for the proposed surveillances.
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1 (BSEP-1-47)
REACTOR COOLANT SYSTEM JET PUMPS LIMITING CONDITION FOR OPERATION 3.4.1.2 All jet pumps shall be OPERABLE.
APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2 ACTION:
With less than 20 jet pumps OPERABLE, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.1.2 Each of the above required jet pumps shall be demonstrated OPERABLE after entering OPERATIONAL CONDITION 1 but prior to THERMAL POWER exceeding 25% of RATED THERMAL POWER and at least once'per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, thereafter, by verifying that at least 2 of the following conditions do not occur:
The recirculation pump flow differs by more than 5% from the a.
established speed-flow characteristics.
b.
The jet pump loop flow differs by more than 5% from the established speed-flow characteristics.
The diffuser-to-lower plenum differential pressure reading on any c.
individual jet pump varies by more than 10% from that jet pump's established operating characteristics.
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l BRUNSWICK - UNIT 1 3/4 4-2 Amendment No.
.(BSEP-1-47) 3/4.4 REACTOR COOLANT SYSTEM BASES 3/4.4.1 RECIRCULATION SYSTEM Operation for longer than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with a reactor core coolant recirculation loop inoperable is prohibited until an evaluation of the performance of the ECCS during one loop operation has been performed, evaluated, and determined to be acceptable.
An inoperable jet pump is not, in itself, a sufficient reason to declare a recirculation loop inoperable, but it does present a hazard in case of a design basis accident by increasing the blowdown area and eliminating the capability of reflooding the core--thus, the requirement for shutdown of the facility with a jet pump inoperable.
The established characteristics for the criteria of 4.4.1.2 are bands of values that encompass the normal scatter of the data. The scatter in the data can be attributed primarily to monitoring inaccuracies and instrumentation tolerances. An evaluation of these factors will be used to determine the widths of the bands. The bands will be centered about the expected values determined from operating data. The acceptance criteria will be these bands plus the appropriate percentage of the expected values at any point. The acceptance criteria will be updated as required to reflect any changes in the recirculation system that would affect the monitored variables.
In order to prevent undue stress on the vessel nozzles and bottom head region, the recirculation loop temperatures should be within 50 F of each other prior to start-up of an idle loop.
l Since the coolant in the bottom of the vessel is at a lower temperature than the water in the upper regions of the core, undue stress on the vessel would result if the temperature difference were greater than 145 F.
3/4.4.2 SAFETY / RELIEF VALVES The reactor coolant system safety. valve. function.of the. safety relief valves operates to prevent the system from being pressurized.above the Safety Limit of 1325 psig. The system is. designed to meet the requirements of the ASME Boiler and Pressure Vessel Code Section III for the pressure vessel and ANSI B31.1, 1975 Code for the reactor coolant system piping.
3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.3.1 LEAKAGE DETECTION SYSTEMS I
The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the Reactor Coolant Pressure Boundary. These detection systems are consistent with the recommendations of Regulatory Cuide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection I
Systems."
BRUNSWICK - UNIT 1 B 3/4 4-1 Amendment No.
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ENCLOSURE 2 TO NLS-86-225 PROPOSED TECHNICAL SPECIFICATION PAGES BRUNSWICK-2 JET PUMP SURVEILLANCE REQUIREMENTS (84TSB32) l l
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SUMMARY
LIST OF REVISIONS BRUNSWICK-2 PAGE NO.
DESCRIPTION 3/44-2 Item 4.4.1.2 - Reword to read "Each of the above required jet pumps shall be demonstrated Operable af ter entering Operational Condition 1 but prior to thermal power exceeding 25% of Rated Thermal Power and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter by verifying the at least 2 of the following conditions do not occur:".
Item 4.4.1.2.a - Change "10%" to "5%"
Item 4.4.1.2.b - Replaced with "The jet pump loop flow differs by more than 5% from the established speed-flow characteristics."
Item 4.4.1.2.c - Change "... from the mean of all jet pump differential pressures, in that loop, by more than 10%." to "... by more than 10%
from that jet pump's established operating characteristics with respect to loop flow."
Change CONDITIONS to OPERATIONAL CONDITIONS.
B 3/4 4-1 Bases - Add paragraph to describe the method used to establish the acceptance criteria for the proposed surveillances.
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(BSEP-2-42)
REACTOR COOLANT SYSTEM JET PUMPS LIMITING CONDITION FOR OPERATION 3.4.1.2 All jet pumps shall be OPERABLE.
APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2 ACTION:
With less than 20 jet pumps OPERABLE, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.1.2 Each of the above required jet pumps shall be demonstrated OPERABLE after entering OPERATIONAL CONDITION 1 but prior to THERMAL POWER exceeding 25% of RATED THERMAL POWER and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, thereafter, by verifying that at least 2 of the following conditions do not occur:
The recirculation pump flow differs by more than 5% from the a.
established speed-flow characteristics.
b.
The jet pump loop flow differs by more than 5% from the established speed-flow characteristics.
The diffuser-to-lower plenum differential pressure reading on any c.
individual jet pump varies by more than 10% from that jet pump's established operating characteristics.
BRUNSWICK - UNIT 2 3/4 4-2 Amendment No.
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b (BSEP-2-42) 3/4.4 REACTOR COOLANT SYSTEM BASES 3/4.4.1 RECIRCULATION SYSTEM Operation with a reactor core coolant recirculation loop inoperable is prohibited until an evaluation of the performance of the ECCS during one loop operation has been performed, evaluated, and determined to be acceptable.
An inoperable jet pump is not, in itself, a sufficient reason to declare a recirculation loop inoperable, but it does present a hazard in case of a design basis accident by increasing the blowdown area and eliminating the capability of reflooding the core. Thus, the requirement for shutdown of the facility with a jet pump inoperable.
4 The established characteristics for the criteria of 4.4.1.2 are bands of values that encompass the normal scatter of the data. The scatter in the data can be attributed primarily to monitoring inaccuracies and instrumentation tolerances. An evaluation of these factors will be used to determine the widths of the bands. The bands will be centered about the expected values determined from operating data. The acceptance criteria will be these bands plus the appropriate percentage of the expected values at any point. The acceptance criteria will be updated as required to reflect any changes in the recirculation system that would affect the monitored variables.
In order to prevent undue stress on the vessel nozzles and bottom head region, the recirculation loop temperatures should be within 50 F of each 0
other prior to start-up of an idle loop.
Since the coolant in the bottom of the vessel is at a lower temperature than the water in the upper regions of the core, undue stress on the vessel would result if the temperature difference were greater than 145 F.
3/4.4.2 SAFETY / RELIEF VALVES The reactor coolant system safety valve function of the safety-relief valves operate to prevent the system from being p'ressurized above the Safety Limit of 1325 psig. The system is designed to meet the requirements of the ASME Boiler and Pressure Vessel Code Section III for the pressure vessel and 3
ANSI B31.1, 1967, Code for the reactor coolant system piping.
3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE c
3/4.4.3.1 LEAKAGE DETECTION SYSTEMS l
l The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the Reactor Coolant Pressure Boundary. These detection systems are consistrnt with the recommendations of Regulatory cuide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems."
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i BRUNSWICK - UNIT 2 B 3/4 4-1 Amendment No.
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