ML20133L107
| ML20133L107 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 01/13/1997 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20133L094 | List: |
| References | |
| NUDOCS 9701210487 | |
| Download: ML20133L107 (7) | |
Text
TABLE OF CONTENTS 12G.11QH Iillt
.P3a:
15 TECHNICAL SPECIFICATIONS AND BASES 15.1 Dermitions 15.2.1-1 15.2.0 Safety Limits and Limiting Safety System Settings 15.2.1-1 15.2.1 Safety Limit, Reactor Core 15.2.1-1 15.2.2 Safety Limit, Reactor Coolant System Pressare 15.2.2-1 15.2.3 Limiting Safety System Settings, Protective Instrumentation 15.2.3 1 15.3 Limiting Conditions for Operation 15.3.0 15.3.0 General Consideration 15.3.0-1 15.3.1 Reactor Coolant System 15.3.1-1 15.3.2 Chemical and Volume Control System 15.3.2-1 15.3.3 Emergency Core Cooling System, Auxiliary Coolmg Systems, Air Recirculation Fan Coolers, and Containment Spray 15.3.3-1 15.3.4 Steam and Power conversion System 15.3.4-1 15.3.5 Instrumentation System 15.3.5-1 15.3.6 Containment System 15.3.6-1 15.3.7 Auxiliary Electrical System 15.3.7 1 15.3.8 Refueling 15.3.8-1 15.3.9 Effluent Releases 15.3.9-1 15.3.10 Control Rod and Power Distribution Limits 15.3.10-1 15.3.11 Movable In. Core Instrumentation 15.3.11-1 15.3.12 Control Room Emergency Filtration 15.3.12-1 15.3.13 Shock Suppressor(Snubbers) 15.3.13-1 15.3.14 Fire Protection System 15.3.14-1 15.3.15 Low Temperature Overpressure Protection Msg-ateg-System 15.3.15-1 15.3.16 Reactor Coolant System Pressure Isolation Valve 15.3.16-1 15.4 Surveillance Requirement 15.4.1 15.4.1 Operational Safety Review 15.4.1-1 15.4.2 In-Service Inspection of Safety Class Components 15.4.2-1 15.4.3 Primary System Testing Following Opening 15.4.3-1 15.4.4 Containment Tests 15.4.4-1 15.4.5 Emergency Core Cooling System and Containment Cooling system Tests 15.4.5-1 15.4.6 Emergency Power System Periodic rem 15.4.6-1 15.4.7 Main Steam Stop Valves 15.4.7-1 15.4.8 Auxiliary Feedwater System 15.4.8-1 15.4.9 Reactivity Anomalies 15.4.9 1 15.4.10 Operational Environmental Monitoring 15.4.10-1 15.4.11 Control Room Emergency Filtration 15.4.11-1 15.4.12 Miscellaneous Radioactive Materials Sources 15.4.12-1 15.4.13 Shock Suppressors (Snubbers) 15.4.13-1 15.4.14 Surveillance of Auxiliary Building Crane Lifting Devices 15.4.14-1 15.4.15 Fire Protection System 15.4.15-1 15.4.16 Reactor Coolant System Pressure Isolation Valves Leakage Tests 15.4.16-1 Unit 1 Amendment No.-%
9701210487 970113 gyac m g.c PDR ADOCK 05000266 Unit 2 - Amendment No -M0 P
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5.
Pressurizer Power-Operated Relief Valves (PORV) and PORV Block Valves l
If a unit is placed in the HOT SHUTDOWN condition in accordance with the requirements of Specifications a(1) through a(5) below, then the reactor coolant system temperature should be l
maintained greater than th:
"m= p:=:=!=:!cn *:mperm: for : !=M:: pre== :=t =
1 Mi=d ! ri;;= !!J. ' ! 355'F If cooldown to less than this temperature is required in order to take action to restore the inoperable component (s) to service, then the requirements of Specification 15.3.15 apply.
Two PORVs and their associated block valves shall be operable.
a.
(1)
If one or both PORVs are INOPERABLE due to seat leakage in excess of that allowed in Specifications 153.1.D, within one hour either restore the PORVs to an operable status or close the associated block valves (s). If these conditions cannot be met, place the unit in a HOT SHUTDOWN condition within the next six hours.
(2)
If one PORV is INOPERABLE due to causes other than excessive seat leakage, within one hour either restore the PORV to OPERABLE status or close its associated block valve and remove power from the block valve, if the PORV cannot be restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, place the unit in a HOT SHUTDOWN condition within the next six hours.
(3)
If both PORVs are INOPERABLE due to causes other than excessive seat leakage, within one hour restore at least one PORV to OPERABLE status. If this condition cannot be met, close the associated block valves, remove power from the block valves and place the unit in a HOT SHUTDOWN condition within the next six hours.
(4)
If one block valve is inoperable, within one hour either restore the block valve to OPERABLE status or place the associated PORV in manual control. Restore the block valve to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. if these conditions cannot be met, place the unit in a HOT SHUTDOWN condition within the next six hours.
Unit 1 Amendment 464 15 3.1-3 Sep' ~'r 7 0. " '
Unit 2 - Amendment 4&O
0 15.3.15 OVER42RESs44R4411-T4 GATING-LOW TEMPERATURE OVERPRESSURE PROTECTIQ_N.
SYSTEM 4PERATIONS Appiicability Applies to operability of the low _Lemperatuttoserpressure protection (LTOP) minganag-system when the reactor coolant system temperature is-4wahan.4heessmmwempera4*e-foshe4aserv4egewurse,4 < 355'F.
Obiective To specify functional requirements and limiting conditions for operation on the use of the pressurizer power operated relief valves when used as part of the overpre
.re :;ingathy LTOP system and to specify further limiting conditions for operation when the reactor coolant system is operatedehout a pren. abwrlsig-voimne-*Hke geworker.atlow temperatures.
Specification A.
System Operability 1.
Except as specified in 15.3.15.A.2 below, the-evergewwkasm
- .c.' ng 1LQf system shall be operable whenever the reactor coolant system is not open to the atmosphere and the temperature is lew4h*Hhenknmem-pre **naanwaemperanay-fouhe-mservice pres :re :J, spa! Fed i F4gw: 15 4-4 < 355'F Operability requirements are:
Both pressurizer power operated relief valves operable at a setpoint of s4243 psig.
a.
b.
Both power operated relief valve block valves are open.
2.
The requirements of 15.3.15.A.1 may be modified as specified below:
With one PORV inoperable while reactor coolant system temperature is >200*F but '~
a.
^
nwassmamprewar4aanswemperauwe fo Se : c;erv4ce prezure tew < 355 F, either restore the inoperable PORV to operable status within 7 days, or depressurize and vent reactor coolant system within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
b.
With one PORV inoperable while reactor coolant system temperature is 5200 F, either restore the inoperable PORV to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or depressurize and vent the reactor coolant system within a total of 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />.
c.
With both power operated relief valves inoperable while the reactor coolant system temperature is fez :'- me : inianun pres n:!en tempera:ure for 'e
- er ce pra
- re se9 < 355*F. the reactor coolant system must be depressurized and sented within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
3.
If the reactor coolant system is s ented per Specification 15.3.15.A.2.a. b, or c, the pathway must be j
l verified at least once every 31 days when it is provided by a non isolable pathway or by a vake(s) that is locked, sealed, or otherwise secured in the open position; otherwise, s erify the pathw a) es ery 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Unit I - Amendment No.-444 15.3.15-1 N * *be' " ! OH t
Unit 2 Amendment No 454
4 11.
Additional Limitations I.
Wher 4he-r ewwredansy. ten kwt4+pev4*4heatmosphe e+mh he-4 emper atwe44+nd.th
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eem4*woianwy. tem +4 !:,,, c275"Ghen1TDP is requittitoir_cnabled by sprsificatina 11111Al no more than one high pressure safety injection pump shall be operable. The second high pressure safety injection pump shall be demonstrated-rendstriinoperable whenever the tempeestmenf+ns r-both4em4orer' *.y, tem-e4 !:gr, c275"E LTOP is. required.In_ht enableiby verifying that the motor circuit breakers have been removed from their electrical power supply circuits or by verifying that the discharge valves from the high pressure safety injection pumps to the reactor coolant system are shut and that power is removed hain_t,hricoperators.
i 2.
A reactor coolant pump shall not be staited when the reactor coolant system temperature is lew4han i
theninkmem4en peratwe4w4h : c ;e prn re4es. < 355'F unless There is a pressure absorbing volume in the presurizer or in the steam generator tubes or a.
b.
The secondary water temperature of each steam generator is less than 50 F above the temperature of the reactor coolant system.
Basis 1
The Owrprewmiration-Mkigating-Low Tempnature Os erpressure P.rnterhen_ System consists of a diver +e redundantmeans of relieving pressure during periods of water solid operation and when the tratter.snojanLsystem temperature is 5:!n :'; ak++pennhted4*-perform 4hepthwary :3". ' ':A4e,tg55'F This method of water relief o.ilizes the pressurizer power operated relief valves (PORV's). The PORV's are made operational for low pressure relief by utilizing a dual setpoint where the low pressure circuit is energized and de-energized by the operator with a keylock switch depending on plant conditions. The logic required for the low pressure setpoint is in addition to the existing PORV actuation logic and will not interfere with existing automatic or manual actuation of the PORV's. The OPERABILITY of the PORVs is determined on the basis of their being capable of automatically mitigating an overpressure event during low temperature operation. The LTOP setpoint of 440 nsig is valid throngb an insidclurface neutron Guence of the limiling reactor ventimaterial ofless than or equal to 105 x 10 n / cmi E
G > 1.031cy1 1
l During plant cooldown prior to reducing reactor coolant system temperature below th: ':- - N np - tme
- !! - ^!:faah : e
,e pr =re4est 355'F. the operator under administrative procedures shall place the ke,slock switch in the " Low Pressure" position. This action enables the Low Temocraturg_ Overpressure ErntcElion
"!!::gn:ing-System. The redundant PORV channels shall remain enabled and operable while the O. rpr:" :::
Mkigaten-l. TOP system is required to be in operation.
Umt 1 - Amendment No.-444 15.3.15-2 Septemke M "M !
Unit 2 - Amendment No.-440
' The reactor coolant system is defined as vented if there is an opening in the reactor coolant system pressure boundary to atmosphere or the pressurizer relief tank that has an equivalent system pressure relieving capability as a PORV. Some examples of such openings include an open or removed PORV, open steam generator or pressurizer manways, a removed pressurizer safety valve, and the top of the reactor vessel when the reactor vessel head has been unbolted or removed.
i The mass input transient used to determine the PORV serpoint assumeds a worse case transient of a single high pressure safety injection pump discharging to the reactor coolant system while the system is solid. Therefore, when theeassence!=: :y;: m i: !::: than-;MF LTOP is recuired to be enabled, only one high pressure safety injection pump shall be operable at any time except when the reactor coolant system is open to the atmosphere.
The heat input transient used to determine the PORV serpoint assumes a temperature difference between the reactor coolant system and the steam generator of 50 F. 'Iherefore, before starting a reactor coolant pump when the reactor coolant system is solid, the operator shall ignsure that the secondary temperature of each steam generator is less than 50 F above the temperature of the reactor coolant system unless a pressure absorbing volume has been verified to exist in the pressurizer or steam generator tubes.
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Unit 1 - Amendment No.4f4 15.3.15-3 cep: mb e ", '"" '
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15.6.9.2 Unique Reoorting Requirements The following written reports shall be submitted to the Director, Office of Nuclear Reactor Regulation, USNRC:
A.
Deleted i
B.
Poison Assembiv Removal From Soent Fuel Storage Racks Plans for removal of any poison assemblies from the spent fuel storage racks shall be reported and described at least 14 days prior to the planned j
activity. Such report shall describe neutron attenuation testing for any 1
replacement poison assemblies,if applicable, to confirm the presence of boron material.
C.
Low Tempestute Overnressure MitigathgProtection Svstem Onemtien In the esent the low temperature _ overpressure m%pteg-protection system (power operated relief valves in the low temperature overpressure protection mode) or residual heat removal system relief valves are operated to relieve a pressure transient which, by licensee's evaluation.
could have resulted in an overpressurization incident had the system not been operable, a special report shall be prepared and submitted to the Commission within 30 days. The report shall describe the circumstances initiating the transient, the effect of the system on the transient and any corrective action necessary to prevent recurrence.
Unit 1 - Amendment No.-M0 15.6.9-4 Ot4ober o ""M Unit 2 - Amendment No.M s