ML19336A630
| ML19336A630 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/17/1980 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML19336A628 | List: |
| References | |
| TAC-42112, NUDOCS 8010300365 | |
| Download: ML19336A630 (9) | |
Text
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DOCKET No. 50-336 ATTACHMENT 1 MILL NE NUCLEAR POWER STATION, UNIT NO. 2 PROPOSED REVISIONS TO TECHNICAL SPECIFICATIONC OCTOBER, 1980 8010s00395
t-l 3/4.4 REACTOR COOLANT SYSTEM t
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- 3/4.4.1 COOLANT LOOP 3 AND COOLANT CIRCULATION I
STARTUP AND POWER OPERATI_0N j
LIMITING CONDITION FOR OPERATION 3.4.1.1 Both reactor coolant loops and both reactor coolant pumps in each loop shall be in operation.
l A_PPLICABILITY : 1 and 2*.
i ACTION:
With less than the above required reactor coolant pumps in operation, be in at least HOT STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
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4 SURVEILLANCE REQUIREMENTS
- 4. 4.1.1 The Flow Dependent Selector Switch shall be determined to be in the 4 pump position within 15 minutes prior to making the reactor critical and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.
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- See Special Test Exception 3.10.4.
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HOT STANDBY L
LIMITING CONDITION FOR OPERATION 3.4.1.2 a, The ' react 6r c~oolant loops listed below shall-be ORERABLE:
1.
Reactor Coolant Loop (A) and at least one associated reactor coolant pump.
2.
Reactor Coolant Loop (B) and.at least one associated reactor coolant pump.
b.
At least one of the above' Reactor Coolant Loops shall be in operation *.
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APPLICABILITY:
MODE 3 1
ACTION:
i a.
With less than the above required reactor coolant loops operable, i
restore the required loops 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 be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
With no reactor coolant loop in operation, suspend all operations involving _a r.educ. tion in. boron concentration of the Reactor Coolant System and immediately initiate. corrective action to return the required loop to operati,on.
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-SURVEILLANCE REQUIREMENTS
- 4. 4.1. 2.1 At least the above required reactor coolant pumps, if not in operation, shall be determined to be OPERABLE once per 7 days by verify-ing correct breaker alignments and indicated power availability, s
4.4.1.2.2 At least one cooling loop shall be verified to be in operation and circulating rea'ctor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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- All reactor coolant punps may be de-energized for up to I hour provided (1) no operations are permitted that would cause dilution of the reactor coolant.
i system bgron concentration, and (2) core outlet tenperature is maintained at W
least 10 F below saturation temperature.
CE-STS 3/4 4-lb e
REACTOR COOLANT SYSTEM SHUTOOWN LIMITING CONDITION FOR OPERATION
- 3. 4.1. 3 a.
At least two of the coolant loops listed below shall be OPERABLE:
1.
Reactor Coolant Loop (A) and its associated steam generator and at least one associated reactor coolant pump, 2.
Reactor Coolant Loop (B) and its associated steam generator and at least one associated reactor coolant pump, 3.
Shutdown Cooling Loop (A)#,
4.
Shutdown Cooling Loop (B)#,
b.
At least one of the above coolant loops shall be in operation *,
APPLICABILITY: MODES 4** and 5**
ACTION:
a.
With less than the above required coolant loops OPERABLE, immediately initiate corrective action to return the required coolant loops to OPERABLE status as soon as possible; be in COLD SHUTDOWN within 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.
j b.
With no coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required coolant loop to operation.
SURVEILLANCE REQUIREMENTS 4.4.1.3.1 The required shutdown cooling loop (s), if not in operation, shall be determined OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability for pump and shutdown cooling loop valves.
4. 4.1. 3. 2 The required reactor coolant pump (s), if not in operation, shall be determined to be OPERABLE once per 7 days by verifying correct breaker aligmnents and indicated power availability.
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- 01 reactor coolant pumps and shutdown cooling pumps may be deenergized for up to I hour provided:
(1) no operations are pennitted,that would cause dilution of the reactor coolant system boron concentration, and (2) core outlet temperature is maintained at least 10 F below saturation tenperature.
- A reactor coolant pump shal~. not be started with one or more of the RCS cold leg temperatures less than or equal to 275cF unless:
(1) the pressurizer water volume is less than 600 cubic feet or (2) the secondary water temperature of each steam generator is less than 43'F (31F when measured by a surface contact instru-ment) above each of the RCS cold leg temperatures.
- The normal or emergency power source may be inoperable in MODE 5.
3/4 4-Ic
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-REACTOR COOLANT SYSTEM REACTOR COOLANT LOOPS AND COOLANT CIRCULATION
'intVI.IlI.AllCl. ItfqqlltEMErlT5 (Continued) i 4.4.1.3.3 The required steam generator (s) shall be determined OPERABLE by verifying the secondary side water level to be > 10% of span at least once i
per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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- 4. 4.1. 3.4 At least one coolant loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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REFUELING OPERATIONS O
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W 3/4.9.8 Sit 0TDOWN COOLING AND C00LAtlT CIRCULATION u J" h
ALL WATER LEVELS LIMI. TING. CONDITION ~FOR OPERATION.
3.9.8.1 At least one shutdown cooling loop shall be in operation.
APPLICABILITY:
MODE 6 ACTION:,
a.
With less than one shutdpwn cooling loop in operation, except as provided in b. below,' suspend all operations involving an increase in the reactor decay heat load er a reduction in boron concentration of the Reactor Coolant System.
Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, b.
The shutdown cooling loop may be removed from operation for up to I hour per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.
c.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.8.1 At least one shutdown cooling loop shall be verified to be in operation
.and circulating reactor coolant at.a flow rate of. greater than or equal to (3000)
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u.m.. x.. gpm at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
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CE-STS 3/4 9-8a
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_ REFUELING OPERATIONS it.0W WATl_l(1.1.VI L-j LIMITING CONDITION FOR OPERATION i
1 3.9.8.2 Two ind+ pendent shutdown cooling loops shall be OPERABLE *.
4 APPLICABILITY: MODE 6 when the water level above the top of the irradiated fuel assemblies seated within the reactor pressure vessel is less than 23 feet above the reactor pressure vessel flange.
ACTION:
With less than the required shutdown cooling loops OPERABLE, a.
immediately initiate corrective action to return loops to OPERABLE status as soon as possible, b.
The provisions of Specification 3.0.3 are not applicable.
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SURVEILLANCE REQUIREMENTS
- 4. 9.8. 2 The required shutdown cooling loops, if not in operation, shall be determined OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability for pump and shutdown cooling loop valves.
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4.
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- 'The normal or emergency power source may be inoperable for each shutdown
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cooling loop.
3/4 9-8b
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3/4.4 REACTOR C00LAN'T SYSTEM BASES
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3/ 4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION The plant is designed to operate with both reactor coolant loops and associated reactor coolant pumps in operation, and maintain DNBR above 1.30 during all normal operations and anticipated transients.
In MODE 3, a single reactor coolant loop provides sufficient heat removal capability for removing decay heat; however, single failure considerations require that two loops be OPERABLE.
In MODES 4 and 5, a single reactor coolant loop or shutdown cooling loop provides sufficient heat removal capability for removing decay heat; but single failure considerations require that at least two loops be OPERABLE. Thus, if the reactor coolant loops are not OPE ABLE, this specification requires two shutdown cooling loops to be OPERABLE The operation of one Reactor Coolant Pump or one shutdown cooling pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during boron concentration reductions in the Reactor Coolant System.
The reactivity change rate associated with boron reductions will, therefore, be within the capability of operator recognition and control.
The restrictions on starting a Reactor Coolant Pump during MODES 4 and 5 with one or more RCS cold. legs less than or equal to 275'F are provided to prevent RCS pressure transients, caused by energy additions from the secondary system, which could exceed the limits of Appendix G to 10CFR Part 50. The RCS will be protected against overpressure transients and will not exceed the limits of Appendix G by either:
(1) restricting the water volume in the pressurizer and thereby providing a volume for the primary coolant to expand into or (2) by restricting starting of the RCP's to when the secondary water temperature of '.ach steam generator is less than 43*F (3PF when measured by a surface contact istrument) above each of the RCS cold leg temperatures.
3/4.4.2 and 3/4.4.3 SAFETY VALVES The pressurizer code safety valves operate to prevent the' RCS from being pressurized above its Safety Limit of 2750 psia.
Each safety valve is designed to relieve 296,000 lbs per hour of saturated steam at the valve setpoint. The relief capacity of a single safety valve is adequate to relieve any' overpressure condition which could occur during shutdown.
In the event that no safety valves are OPERABLE, an operating shutdown cooling loop, connected to the RCS provides overpressure relief capa-bility and will prevent RCS overpressurization.
MILLSTONE - UNIT 2 B 3/4 4-1
' REFUELING OPERATIONS 0
l BASES 3/4.9.6 CRANE OPERABILITY - CONTAIMENT BUILDING The OPERABILITY requirments of the cranes used for movement of fuel assemblies ensures that: 1) each crane has sufficient load capacity to lift a fuel element, and 2) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.
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3/4.9.7 CRANETRAVEL-SPENTFUELSTORAGEBUILDD@,
The restriction on movement of loads in excess of the nominal weight of a fuel assembly and CEA over irradiated fuel assemblies ensures that i
no more than the contents of one fuel assembly will be ruptured in the event of a fuel handling accident. This assumption is consistent with 1
the activity release assumed in the accident analyses.
3/4.i.8~ C00tAdYCIRCOLATION The requirement that at least one shutdown cooling loop be in operation ensures that (!) sufficient cooling capacity is available to remove decay heat 0
,and maintain the water in the reactor pressure vessel below 140 F as required uuring the REFUELING MODE, and (2) sufficient ' coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification.
The requircaent to have two shutdown cooling loops OPERABLE when there is 1ess than 23 feet of water above the core, ensures that a single failure of the operating shutdown cooling loop will not result in a corr?lete loss of decay heat removal capability.
With the reactor vessel head removed and 23 feet of water above the core, a large heat sink is available for core cooling, thus in the event of a failure of the operating shutdown cooling loop, adequate time is provided to initiate emergency procedures to cool the core.
3/4.9.9 and 3/4.9.10 CONTAIMENT RADIATION MONITORING AND CONTAIMENT I
PURGE VALVE I5OLATION 5YSTEM The OPERABILITY of these systems ensure that the containment purge valves will be automatically isolated upon detection of high radidtion levels within the containment. The OPERABILITY of these systems are required to restrict the release of radioactive material from the I
containment atmosphere to the environment.
l 3/4.9.11 and 3/4.9.12 WATER LEVEL-REACTOR VESSEL AMD ST0EAGE POOL DATER LEVEL l
The restrictions on minimum unter level ensure that sufficient unter
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available to remove 99% of the assumed 101 iodine gap activity depth 1s,from the rupture of an irradiated fuel assembly.
released The minimum water depth is consistent with the assumptions of the accident analysis.
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