ML18059A977

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Proposed Tech Specs Re Shutdown Cooling
ML18059A977
Person / Time
Site: Palisades Entergy icon.png
Issue date: 05/05/1994
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18059A976 List:
References
NUDOCS 9405110259
Download: ML18059A977 (12)
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Text

  • ATTACHMENT 1 Consumers Power Company Palisades Plant Docket 50-255 SHUTDOWN COOLING TECHNICAL SPECIFICATIONS CHANGE REQUEST Revised Proposed Pages May 5, 1994

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9405110259 940505 11 Pages PD R ADOCK 05000255 ,

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PA~ADES PLANT TECHNICAL SPECIFICA~NS TABLE OF CONTENTS SECTION DESCRIPTION PAGE NO 1.0 DEFINITIONS 1-1 1.1 REACTOR OPERATING CONDITIONS 1-1 1.2 PROTECTIVE SYSTEMS 1-3 1.3 INSTRUMENTATION SURVEILLANCE 1-3 1.4 MISCELLANEOUS DEFINITIONS 1-4 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2-1 2.1 SAFETY LIMITS - REACTOR CORE 2-1 2.2 SAFETY LIMITS - PRIMARY COOLANT SYSTEM PRESSURE 2-1 2.3 LIMITING SAFETY SYSTEM SETTINGS - RPS 2-1 Table 2.3.l Reactor Protective System Trip Setting Limits 2-2 B2.l Basis - Reactor Core Safety Limit B2-l B2.2 Basis - Primary Coolant System Safety Limit B2-2 B2.3 Basis - Limiting Safety System Settings B2-3

3. 0 LIMITING CONDITIONS FOR OPERATION 3-1 3.0 APPLICABILITY 3-1
3. I PRIMARY COOLANT SYSTEM 3-1 b
3. I. I Operable Components 3-1 b Figure 3-0 ASI Limit for Tinlet function 3-3a 3 .1. 2 Heatup and Cooldown Rates 3-4 Figure 3-1 Pressure - Temperature Limits for Heatup 3-9 Figure 3-2 Pressure - Temperature Limits for Cooldown 3-10 Figure 3-3 Pressure - Temperature Limits for Hydro 3-11 3.1.3 Minimum Conditions for Criticality 3-12 3.1.4 Maximum Primary Coolant Radioactivity 3-17 3.1.5 Primary Coolant System Leakage Limits 3-20 3.1.6 Maximum PCS Oxygen and Halogen Concentration 3-23 3.1. 7 Primary and Secondary Safety Valves 3-25 3.1.8 Overpressure Protection Systems 3-25a 3.1.9 Shutdown Cooling 3-25h 3.2 CHEMICAL AND VOLUME CONTROL SYSTEM 3-26 3.3 EMERGENCY CORE COOLING SYSTEM 3-29 3.4 CONTAINMENT COOLING 3-34 3.. 5 STEAM AND FEEDWATER SYSTEMS 3-38 3.6 CONTAINMENT SYSTEM 3-40 Table 3.6.1 Containment Penetrations and Valves 3-40b 3.7 ELECTRICAL SYSTEMS 3-41 3.8 REFUELING OPERATIONS 3-46 3.9 Deleted 3-50 i

Amendment No.

3. l . 9 s.HUTOOWN COOL I NG!oc)

Specification 3.1.9.1 One PCS loop or SOC train shall be in operation providing ~2810 gpm flow through the reactor core, and at least two of the means of decay heat removal listed below shall be OPERABLE:

1. SOC train A consisting of an OPERABLE SOC pump and an OPERABLE heat flow path to Lake Michigan.
2. SOC train B consisting of an OPERABLE SOC pump and an OPERABLE heat flow path to Lake Michigan.
3. PCS loop 1 consisting of an OPERABLE Primary Coolant Pump and an OPERABLE Steam Generator and secondary water level ~-84%.
4. PCS loop 2 consisting of an OPERABLE Primary Coolant Pump and an OPERABLE Steam Generator and secondary water level ~-84%.

Applicability Specification 3.1.9.1 applies when there is fuel in the reactor, with PCS Temperature is >200°F and ~300°F.

Exception

1. All flow through the reactor core may be intentionally stopped for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided:
a. No operations are permitted that would cause reduction of the PCS boron concentration, and
b. Core outlet temperature stays ~l0°F below saturation temperature.

Action

1. With fewer OPERABLE means of decay heat removal than required:
a. Immediately initiate corrective action to return a second loop or train to OPERABLE status, and
b. Maintain PCS temperature as low as practical with available equipment.
c. If a SDC train is available, be <200°F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2. With less flow through the core than required:
a. Immediately suspend all operations involving a reduction in PCS boron concentration, and
b. Immediately initiate corrective action to return a loop or train to operation providing flow through the core.

3-25h Amendment No.

3.'1.9 SHUTDOWN COOLING-Cl 3.1.9.2 Specification One SOC train shall be in operation providing ~2810 gpm flow through the reactor core, and at least two of the means of decay heat removal listed below shall be OPERABLE:

1. SOC train A consisting of an OPERABLE SOC pump and an OPERABLE heat flow path to Lake Michigan.
2. SOC train B consisting of an OPERABLE SOC pump and an OPERABLE heat flow path to Lake Michigan.
3. PCS loops 1 and 2, each with an OPERABLE steam generator and secondary level ~-84%.

Applicability Specification 3.1.9.2 applies when there is fuel in the reactor, with PCS Temperature is <200°F and the PCS loops filled.

Exceptions

1. All flow through the reactor core may be intentionally stopped for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided:
a. No operations are permitted that would cause reduction of the PCS boron concentration or PCS inventory, and
b. Core outlet temperature stays ~200°F, and
c. Two SOC trains are OPERABLE.
2. One or both SOC trains may be intentionally rendered inoperable for testing or maintenance provided:
a. One PCS loop or SOC train is providing flow through the reactor core, and
b. Core outlet temperature stays ~200°F, and
c. Each steam generator secondary water level is ~-84%.

Action

1. With fewer OPERABLE means of decay heat removal than required:
a. Immediately initiate corrective action to return a second loop or train to OPERABLE status, and
b. Maintain PCS temperature as low as practical with available equipment.
2. With less flow through the core than required:
a. Immediately suspend all operations involving a reduction in PCS boron concentration, and
b. Immediately initiate corrective action to return a loop or train to operation providing flow through the core.

3-25i Amendment No.

3 . *l . 9 SHUTDOWN COOL I NG'°C) 3.1.9.3 Speci fi cat ion One SDC train shall be in operation providing ~1000 gpm flow through the reactor core, and at least two of the means of decay heat removal listed below shall be OPERABLE:

1. SDC train A consisting of an OPERABLE SDC pump and an OPERABLE heat flow path to Lake Michigan.
2. SDC train B consisting of an OPERABLE SDC pump and an OPERABLE heat flow path to Lake Michigan.

Appl icabil itv Specification 3.1.9.3 applies when there is fuel in the reactor, with PCS Temperature is <200°F and the PCS loops NOT filled.

Exceptions

1. All flow through the reactor core may be intentionally stopped for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided:
a. No operations are permitted that would cause reduction of the PCS boron concentration or PCS inventory, and
b. Core outlet temperature stays ~200°F, and
c. Two SDC trains are OPERABLE.
2. One or both SDC trains may be intentionally rendered inoperable for testing or maintenance provided:
a. One SDC train is providing flow through the reactor core, and
b. Core outlet temperature stays ~200°F, and
c. The refueling cavity water level is ~647'.

Action

1. With fewer OPERABLE means of decay heat removal than required:
a. Immediately initiate corrective action to return a second train to OPERABLE status, and
b. Maintain PCS temperature as low as practical with available equipment.
2. With less flow through the core than required:
a. Immediately suspend all operations involving a reduction in PCS boron concentration, and
b. Immediately initiate corrective action to return a train to operation providing flow through the core.

3-25j Amendment No.

3.1 PRIMARY COOLANT 3:1.9 SHUTDOWN COOLING

~TEM (PCS)

  • BASIS The Shutdown Cooling (SOC) specifications require a minimum flow be maintained through the reactor core and two methods of decay heat removal to be OPERABLE, in each of three situations, PCS temperature 200°F to 300°F, PCS temperature below 200°F with the loops filled, and PCS temperature below 200°F with the loops not filled. "Loops Filled" means the PCS loops are intact, not blocked by dams, and totally filled with coolant.

The requirement to maintain 2810 gpm flow through the reactor core when the PCS loops are filled is based on an analysis of potential dilution events. Maintenance of this flow assures that indication of increasing count rate will be available to warn the operator and allow compensating action. The requirement to maintain 1000 gpm flow through the reactor core when the loops are not filled assures mixing of the PCS while allowing flow to be reduced to avoid vortexing in the SOC suction piping.

The 1000 gpm is based on operating experience, rather on analysis. With flow less than 2810 gpm, Specification 3.10.1 imposes additional requirements for Shutdown Margin and limits charging pump operability.

Maintaining flow through the reactor core also allows use of the SOC temperature indication to determine core outl~t temperature when the core outlet thermocouples are not in service.

Natural circulation is adequate for decay heat removal, however it may not provide adequate mixing of the PCS coolant during PCS boron concentration changes or inadvertent dilution events. Therefore, forced circulation is required except during short intervals when the required loops or trains may be intentionally stopped provided additional constraints are followed.

An OPERABLE steam generator, for the purposes of this specification, must have both its primary and secondary sides intact, its tubes filled with primary coolant, and a secondary water level of at least -84% on the wide range level channels. The specified steam generator secondary water level of -84% ensures that at least one-third of the effective steam generator heat transfer area is covered and is therefore sufficient to support natural circulation in the Pcs< 1* 2'. In addition, there must be available a method of feedwater addition and a controllable path for steam release.

A heat flow path to the lake may vary in actual component configuration, method of operation and control, but it shall always accomplish the objective of transferring decay heat from the reactor to Lake Michigan.

As a minimum, a heat flow path requires: a shutdown cooling pump, a shutdown cooling heat exchanger, a component cooling water pump, a component cooling heat exchanger, a service water pump, and appropriate piping, valves and controls for the equipment to perform its function.

All of this equipment must be OPERABLE and must have adequate, but not necessarily redundant, electrical power.

3-25k Amendment No.

3.1 PRIMARY COOLANT 3:1.9 SHUTDOWN COOLING

~TEM (PCS)

(Continued)

The shutdown cooling trains at Palisades are not totally independent since they share common suction and discharge piping including valves M0-3015, M0-3016, CV-3006, CV-3025 and CV-3055. Similarly, the Service Water and Component Cooling Water systems are each comprised of two trains which are electrically independent, but not mechanically independent. The arrangement of each of these systems is illustrated in the associated chapters of the FSAR.

Operation of the shutdown cooling trains is limited to when the PCS temperature is below 300°F because, although the original design of the system was for 325°F, the maximum temperature used in the stress analysis of the shutdown cooling system piping was 300°F.

With the PCS temperature >200°F and ~300°F, a single primary coolant loop or a single shutdown cooling train provides sufficient heat removal capability for removing decay heat. Requiring a second means of decay heat removal to be operable provides an back up in the event of a component failure.

With the PCS temperature ~200°F the SOC trains are the normal means of decay heat removal. If both PCS loops are filled and intact, use of the PCS is permitted as a back up means of decay heat removal to permit maintenance or testing of SOC components. If a failure of the operating SOC train required use of the PCS for decay heat removal, temperatures could rise above 200°F but boiling in the steam generators would then provide a method of decay heat removal.

With the PCS temperature ~200°F with the loops not filled, the PCS cannot be used as a method of decay heat removal. Therefore, two SOC trains are required. The loops are considered "not filled" if it has been drained so air has entered the loops and has not yet been removed. Once the PCS loops have been drained to any extent (to install steam generator nozzle dams for example) there could be sufficient air trapped in the steam generator u-tubes to prevent natural circulation.

The balance of equipment which comprises a heat flow path, (shutdown cooling heat exchanger, component cooling flow path, service water pump, and etc.) must be operated as necessary so as to maintain the PCS temperature and heatup rate within limits. This equipment is manually operated, and has no provision or requirement for automatic actuation during shutdown conditions. During periods when this equipment is required to be OPERABLE, but when PCS temperature and heat load do not require it to be in operation, required components may be temporarily isolated from the cooling flow path in order to perform testing, provided the components themselves are not disabled or rendered inoperable.

3-251 Amendment No.

3 :1 PRIMARY COOLANT 3;1.9 SHUTDOWN COOLING

~TEM (PCS)

(Continued)

An exception to the requirement for continuous circulation through the reactor core is provided. Both SOC and PCS circulation may be stopped for up to one hour provided actions are taken to prevent dilution or draining of the PCS and to avoid situations that could produce steam in the reactor vessel. During periods without forced circulation, admission of water with less Boron concentration than currently in the PCS could collect in a localized pocket and present a potential reactivity addition upon restart of forced circulation. Maintaining the temperature well below boiling ensures that availability of single phase natural circulation. The one hour time limit is not based on analysis. It was chosen to allow testing (such as test closure of containment isolation or shutdown cooling suction valves which require or result in stopping shutdown cooling flow) or minor maintenance, but to restrict the time without mixing and circulation of the PCS.

An exception to the requirement to have heat flow paths to the lake operable has also been provided, when below 200°F. Both heat flow paths may be made inoperable provided that adequate means are provided to assure that decay heat removal is available. In addition, core outlet temperature must be maintained below 200°F, PCS heatup rate must remain within Technical Specification limits, and circulation must be maintained through the reactor core.

In the condition where the PCS loops are filled and both steam generators have sufficient secondary water level, the PCS may be relied upon as the means of decay heat removal allowing maintenance or testing of SOC, Component Cooling or Service water components.

In the condition where the reactor vessel head has been removed and the refueling cavity has been filled for refueling, the mass of water in the pool provides a passive means of decay heat removal. When the cavity is filled to ~647' elevation, this passive heat sink may be relied upon as the means of decay heat removal allowing maintenance or testing of SOC, Component Cooling, or Service water components.

During the exercising of these exceptions, operations which could drain the PCS and thereby cause a loss of, or a failure to regain, shutdown cooling are not allowed. This restriction against reducing PCS inventory does not apply to operations, such as pump flow testing, which may cause relatively minor changes in PCS inventory. The restriction is intended to apply to operations which might actually drain water from the PCS such that inventory could not be quickly regained.

References (1) ABB/CE Letter OPS-91-0496, "Minimum S/G Level Required to Support Natural Circulation Decay Heat Removal."

(2) Consumers Power Company Engineering Analysis EA-GFP-90-03, Revision 0, "Technical Review of ABB/CE Letter OPS-91-046."

3-25m Amendment No.

3:7 3:7.3 ELECTRICAL ~TEMS (Continued)

SHUTDOWN COOLING ELECTRICAL REQUIREMENTS With the primary coolant system at :c;;300°F, and with fuel in the reactor, the shutdown cooling train(s) shall be electrically powered as follows:

a. If one train of shutdown cooling is required to meet specification 3.I.9:

I. The appropriate engineered safeguards bus (IC or ID) shall be operable and capable of being supplied by offsite power and an operable diesel generator.

2. Have two trains of shutdown cooling operable, and meet all the requirements of 3.7.3.b below.
b. If two trains of shutdown cooling are required to meet specification 3.I.9, one engineered safeguards bus (IC or ID) shall be operable and supplied by offsite power while the other engineered safeguards bus (ID or IC) is operable and capable of being supplied by offsite power and an operable diesel generator.

ACTION With less than the required electrical sources operable:

A. Immediately initiate action to suspend REFUELING OPERATIONS, B. Immediately initiate action to suspend movement of irradiated fuel, C. Immediately suspend crane operations over irradiated fuel, D. Immediately suspend operations with a potential for draining the PCS or fuel pool, E. Immediately initiate action to restore the required electrical sources to operable status.

3-45a Amendment No.

No Functional Unit

  • Table 3.17.4 Minimum O~erable C annels (continued)

Minimum Degree of Redundancy Permissible Bypass Conditions

8. Pressurizer Wide 2 (m,n,o) None Not required in Range Water Level Cold or Indication Refueling Shutdown
9. Pressurizer Code 1 ver None Not Required I Safety Relief Valves Position Indication Va ve below 300°F fAcoustic Monitor or emperature Indication)
10. Power Operated Relief 1 ver None Not required when Valves (Acoustic Va ve PORV isolation Monitor or Temperature valve is closed Indication) and its indication system is operable
11. PORV Isolation Valves 1 ~er None Not required when Position Indication Va ve reactor is depressurized and vented in accordance with Specification 3.1.8
12. Subcooling Margin 1 None Not required Monitor below 300°F
13. Auxiliary Feed Flow 1 pefi None Not required Rate Indication fl ow h) below 300°F Control Valve
14. Auxiliary Feedwater 2 per 1 Not required Actuation System steam below 300°F Sensor Channels generator<e>
15. Auxiliary Feedwater 2<f> 1 Not required I Actuation S~stem Actuation C annels below 300°F
16. Excore Detector l(g) None Not Required Deviation Alarms Below 25% of Rated Power
17. Axial Shape Index 2 1 Not Required Alarm Below 25% of Rated Power
18. Reactor Vessel 2cj,k,L,m> None Not Required Water Level Below 300°F
19. Core Exit 4/core None Not required Thermocouples ~uadrart I q, r below 300°F 3-8la Amendment No. e:!-, 68, %, H.§., -H-8, H-9, H-7-, &G,

12.

  • Table 4.2.2 (continued}

Minimum Frequencies for Equipment Tests Iodine Removal System The Iodine Removal System shall be demonstrated operable:

a. At least once per 31 days by verifying that each valve (manual, power operated or automatic} in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position.
b. At least once per 6 months by:
1. Verifying the volume of sodium hydroxide in tank T-103.
2. Verifying the concentration of sodium hydroxide in T-103.
13. Containment Purge and Ventilation Isolation Valves The Containment Purge and Ventilation Isolation Valves shall be determined closed:
a. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by checking the valve position indicator in the control room;
b. At least once every 6 months by performing a leak rate test between the valves.
14. Shutdown Cooling To meet the shutdown cooling requirements of Section 3.1.9:
a. The required reactor coolant pump(s}, if not in operation should be determined to be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.
b. The required steam generator(s} shall be determined OPERABLE by verifying the secondary water level to be ~-84% at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
c. At least one coolant loop or train 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 />.

4-15b Amendment 8-l, -9{), -l-68,

TABLE 4.21.1 (Continued)

ALTERNATE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Surveillance Channel Description Function frequency Surveillance Method

7. Source Range Neutron Monitor a. Test Prior to a. Internal test signal (performed under Table 4.1.3)

CNI-1/3C) startup'41

8. Auxiliary Feedwater Low Suction a. Calibrate Refueling a. Apply known pressure to pressure sensor Pressure switch Cycle CPS-0741D)
9. SIRW Tank Level Indication a. Check'11 Quarterly a. Compare independent level readings CLI-03328)
b. Calibrate Refueling b. Apply known differential pressure to level sensor Cycle
10. Auxiliary Feedwater Flow Rate'21 a. Calibrate Refueling a. Apply known differential pressure to sensor(s)

Indication Cycle CFI-07278)

CFI-07498)

11. Auxiliary Feedwater Flow Control'31 a. Check Refueling a. Verify Control Valves (CV-0727 & CV-0749) Cycle
12. Auxiliary Feedwater Pump Inlet Steam Valve (CV-05228)
a. Check Refueling Cycle
a. Verify Control (1) Quarterly check are not required when the plant is less than 300°F.

(2) Satisfies Table 4.1.3-15 Requirement.

(3) See Specification 4.9b.

(4) Prior to each startup, if not done previous week.

4-88 Amendment No. 3§., ~. m,

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