ML18057B303

Proposed Tech Specs,Consisting of Rev 2 Re Addition of Shutdown Cooling Sys Operability Requirements,Per Generic Ltr 88-17 Recommendations

ML18057B303
Person / Time
Site:	Palisades
Issue date:	09/26/1991
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18057B301	List: ML18057B300 ML18057B302 ML18057B303
References
GL-88-17, NUDOCS 9110080294
Download: ML18057B303 (48)

Text

ATTACHMENT 1 Consumers Power Company Palisades Plant Docket 50-255 TECHNICAL SPECIFICATIONS CHANGE REQUEST SHUTDOWN COOLING SYSTEM, REVISION 2 PROPOSED PAGES September 26, 1991 19 Pages

~

PALISADES PLANT TECHNICAL SPECIFICATIONS 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 2-3 2.3 LIMITING SAFETY SYSTEM SETTINGS - REACTOR PROTECTIVE SYSTEM 2-4 Table 2.3.l Reactor Protective System Trip Setting Limits 2-5 3.0 LIMITING CONDITIONS FOR OPERATION 3-1 3.0 APPLICABILITY 3-1 3.1 PRIMARY COOLANT SYSTEM 3-1 b 3.1.1 Operable Components 3-1 b Figure 3-0 Reactor Inlet Temperature vs Operating Pressure 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 Test 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 Primary Coolant Oxygen and Halogens Concentrations 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 3-25e I 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 EFFLUENT RELEASE (DELETED) 3-50 i

Amendment No. pJ, ~J, ~7, $~, J~$, JJ~, Ji$,

TSPR8902

l

• 3.1 PRIMARY COOLANT SYSTEM Applicability Applies to the operable status of the primary coolant system.

Objective To specify certain conditions of the primary coolant system which must be met to assure safe reactor operation.

Specifications 3.1.1 Operable Components

a. At least one primary coolant pump or one shutdown cooling pump with a flow rate greater than or equal to 2810 gpm shall be in operation whenever a change is being made in the boron concentration of the primary coolant and the plant is operating in cold shutdown or above, except during an emergency loss of coolant flow situation. Under these circumstances, the boron concentration may be increased with no primary coolant pumps or shutdown cooling pumps running.

• b. Four primary coolant pumps shall be in operation whenever the reactor is operated above hot shutdown, with the following exception:

Before removing a pump from service, thermal power shall be reduced as specified in Table 2.3.1 and appropriate corrective action implemented. With one pump out of service, return the pump to service within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (return to four-pump operation) or be in hot shutdown (or below) with the reactor tripped (from the C-06 panel, opening the 42-01 and 42-02 circuit breakers) within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Start-up (above hot shutdown) with less than four pumps is not permitted and power operation with less than three pumps is not permitted.

c. The measured four primary coolant pumps operating reactor vessel flow shall be 140.7 x 10 6 lb/hr or greater, when corrected to 532°F.

d. Both steam generators shall be capable of performing their heat transfer function whenever the average temperature of the primary coolant is above 300°F.

e. Deleted 3-lb Amendment No. ~J, $~, JJ$, JJ~, J$~, J$7,

• TSPR8902

3. I PRIMARY COOLANT SYSTEM (Cont'd)

3. I. I Operable Components (cont'd)

h. Forced circulation (starting the first primary coolant pump) shall not be initiated unless one of the following conditions is met:

Primary coolant cold leg temperature is > 430°F.

H~ PCS cold leg temperature is ~ 430°F and S/G secondary temperature is less than PCS cold leg temperature.

(3) Shutdown cooling is isolated from the PCS AND PCS cold leg temperature is > 2I0°F and S/G secondary temperature is less than I00°F higher than PCS temperature.

(4) Shutdown cooling is isolated from the PCS AND PCS cold leg temperature is ~ I70°F and ~ 2I0°F AND S/G secondary temperature is less than 20°F higher than PCS cold leg temperature.

(5) Shutdown cooling is isolated from the PCS AND PCS cold leg temperature is ~ I20°F and < I70°F AND S/G secondary temperature is less than I00°F higher than PCS cold leg temperature.

i. The PCS shall not be heated or maintained above 300°F unless a minimum of 375 kW of pressurizer heater capacity is available from both buses ID and IE. Should heater capacity from either bus ID and IE fall below 375 Kw, either restore the inoperable heaters to provide at least 375 Kw of heater capacity from both buses ID and IE 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 I2 hours.

Basis When primary coolant boron concentration is being changed, the process must be uniform throughout the primary coolant system volume to prevent stratification of primary coolant at lower boron concentration which could result in a reactivity insertion.

Sufficient mixing of the primary coolant is assured ~f one shutdown cooling or one primary coolant pump is in operation. > The shutdown cooling pump will circulate the primary system volume in less, than 60 minutes when operated at rated capacity. By imposing a minimum shutdown cooling pump flow rate of 28IO gpm, sufficient time is provided for the operator tp5 termi~ate the boron dilution under asymmetric flow conditions. > The pressurizer volume is relatively inactive, therefore will tend to have a boron concentration higher than rest of the primary coolant system during a dilution operation.

Administrative procedures will provide for use of pressurizer sprays to maintain a nominal spread between the boron concentration in tl\e pressurizer and the primary system during the addition of boron.

3-Id Amendment No ~7, ~~' JJJ, JJ~, 1~J, TSPR8902

3 .1 PRIMARY COOLANT SYSTEM (PCS) (Continued) 3.1.9 SHUTDOWN COOLING - This section only applies with fuel in the reactor.

a. PCS Temperature >200°F and ~300°F At least two of the loops or trains listed below shall be operable and at least one loop or train shall be in operation:

1. Primary Coolant System Loop 1 consisting of an operable Steam Generator and at least one operable Primary Coolant Pump (PCP).

2. Primary Coolant System Loop 2 consisting of an operable Steam Generator and at least one operable Primary Coolant Pump (PCP).

3. Shutdown Cooling Train A.

4. Shutdown Cooling Train B.

EXCEPTION All PCPs and Shutdown Cooling may be intentionally secured 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 D. Core outlet temperature stays at least l0°F below saturation temperature.

ACTION A. If only 1 PCS loop is operable and no SDC trains are operable:

1. Immediately initiate corrective action to return a second loop or train to operable status.

B. If only 1 SDC train is operable and no PCS loops are operable:

1. Immediately initiate corrective action to return a second loop or train to operable status, AND

2. If a second loop or train cannot be returned to operable status be less than 200°F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

C. If no PCS loops or Shutdown Cooling trains are in operation when required:

1. Immediately suspend all operations involving a reduction in PCS boron concentration, AND

2. Immediately initiate corrective action to return the required loops or trains to operation.

3-25e Amendment No.

TSPR8902

• 3 .1 3 .1.9 PRIMARY COOLANT SYSTEM (PCS) (Continued)

SHUTDOWN COOLING (Continued)

b. PCS Temperature ~200°F - Loops Filled At least one of the loops or trains listed below shall be operable and in operation and either one additional loop or train shall be operable or the secondary side water level of each steam generator shall belligher than the minus 84 percent level:

1. Primary Coolant System Loop 1 consisting of an operable Steam Generator and at least one operable Primary Coolant Pump (PCP).

2. Primary Coolant System Loop 2 consisting of an operable Steam Generator and at least one operable Primary Coolant Pump (PCP).

3. Shutdown Cooling Train A.

4. Shutdown Cooling Train B.

EXCEPTION All PCPs and Shutdown Cooling may be intentionally secured 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 0:- Core outlet temperature does not exceed 200°F.

ACTION A. If only one PCS loop or SDC train is operable when two are required:

1. Immediately initiate corrective action to return the required loops or trains to operable status.

B. If a required Steam Generator has less than the specified water level:

1. Immediately initiate corrective action to restore the required Steam Generator water level.

C. If no PCS loops or Shutdown Cooling trains are in operation when required:

1. Immediately suspend all operations involving a reduction in PCS boron concentration, AND

~, Immediately initiate corrective action to return the required loops or trains to operation.

3-25f Amendment No.

TSPR8902

• 3 .1 3.1.9 PRIMARY COOLANT SYSTEM (PCS) (Continued)

SHUTDOWN COOLING (Continued)

c. PCS Temperature ~200°F - Loops not filled Two Shutdown Cooling trains (SOC) shall be operable, and at least one train shall be in operation.

EXCEPTIONS:

1. One SOC train may be intentionally rendered inoperable for testing or maintenance provided:

a. The other SOC train is in operation.

2. All Shutdown Cooling may be intentionally secured 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 does not exceed 200°F.

ACTION A. If only one SOC train is operable when two are required:

1. Immediately initiate corrective action to return two trains to operable status.

B. If no SOC trains are in operation when required:

1. Immediately suspend all operations involving a reduction in PCS boron concentration, AND

2. Immediately initiate corrective action to return the required trains to operation.

3-25g Amendment No .

• TSPR8902

3 .1 PRIMARY COOLANT SYSTEM {PCS) (Continued) 3.1.9 SHUTDOWN COOLING (Continued)

BASIS Palisades' specific design does not include redundant shutdown cooling "trains." However, using the term "train" when discussing the shutdown cooling system facilitates understanding. A shutdown cooling train 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 the ultimate heat sink. As a minimum, a shutdown cooling train requires:

a shutdown cooling pump, one component cooling water pump, one service water pump, and appropriate piping, valves and controls for the equipment to perform its function. All of this equipment must also have adequate electrical power to be operable.

"Loops filled" means the Primary Coolant System (PCS) loops are intact, not blocked by dams and totally filled with coolant. This permits partial draining of the PCS provided air has not entered the PCS loops.

The loops are considered "not filled" after the PCS has been drained so air has entered the loops and air sweeps have not been completed to remove the air. Once the PCS loops have been drained to any extent (install steam generator nozzle dams for example) there could be sufficient air trapped in the upper portion of the steam generator u-tubes, even after the PCS water level is raised, to prevent natural circulation in the PCS. For this reason, the steam generators cannot be considered operable until the PCS loops are completely filled with coolant and the air sweeps completed.

With the PCS temperature >200°F and ~300°F a single primary coolant loop or shutdown cooling train provides sufficient heat removal capability for removing decay heat. Natural circulation is adequate for core heat removal, however it may not provide adequate mixing of the PCS coolant during PCS boron concentration changes. Therefore, forced circulation is required during these operating conditions, except during intervals when the required loops or trains can be intentionally rendered inoperable provided additional constraints are followed. Requiring a second loop or train be operable provides some assurance that major component failure will not result in a loss of decay heat removal capability. Operation of the shutdown cooling trains is limited to when the PCS temperature is ~300°F because 300°F is the maximum temperature used in the stress analysis of the shutdown cooling system piping.

When the PCS temperature <200°F and the loops filled, a single primary coolant loop or shutdown cooling train provides sufficient heat removal capability for removing decay heat. The steam generators remove heat by bulk heating of the secondary side water rather that creating steam. Natural circulation is adequate as a backup means for core heat removal, however it may not provide 3-25h Amendment No .

TSPR8902

3 .1 PRIMARY COOLANT SYSTEM (PCS} (Continued) 3.1.9 SHUTDOWN COOLING (Continued)

BASIS (Continued) adequate mixing of the PCS coolant during PCS boron concentration changes. In addition, it is difficult to maintain PCS temperature

<200°F, if the only method of core heat removal is natural circulation. Therefore, forced circulation is required during these operating conditions, except during intervals when the required loops or trains can be intentionally secured provided additional constraints are followed. A steam generator secondary water level of at least minus 84 percent covers at least one-third of the effective steam generator heat transfer r.f.~f and is sufficient to support natural circulation in the PCS * .

With the PCS temperature ~200°F and the loops not filled, a single shutdown cooling train provides sufficient heat removal capability for removing decay heat. Requiring a second loop or train be operable provides some assurance that major component failure will not result in a loss of decay heat removal capability.

Both SDC and PCS circulation may be terminated for up to one hour provided actions are taken to prevent dilution of the PCS and to avoid situations that could produce steam in the reactor vessel.

When the PCS temperature is >200°F and <300°F, maintaining ~l0°F subcooling ensures the availability of single phase natural circulation. Maintaining PCS temperature ~200°F also ensures the availability of single phase natural circulation.

A train of SDC may be intehtionally rendered inoperable for testing or maintenance for any ti~e interval provided the other SDC train is in operation. The two shutdown cooling trains 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. No time limit is specified because the time interval that is needed for each required evolution could vary. This method of operating equipment is consistent with the intent of Generic Letter 88-17, Loss of Decay Heat Removal. It is recommended that equipment be maintained and tested as appropriate to create an acceptable level of confidence that the systems will be able to perform their decay heat removal function. Therefore, appropriate testing or maintenance is considered prudent and justified, without any specific time limit related to equipment that may be inoperable to permit such evolutions. In all cases, the intent is to take reasonable actions to minimize the use of exception No. 1 of specification 3.1.9.c. If it is required to use exception No. 1 of specification 3.1.9.c, SDC will not be rendered inoperable in situations where PCS temperature is close to 200°F or the PCS heatup rate would result in the PCS temperature exceeding 200°F in a relatively short period of time.

(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 O "Technical Review of ABB/CE Letter OPS-91-046."

3-25i Amendment No.

TSPR8902

3.5 STEAM AND FEEDWATER SYSTEMS Applicability Applies to the operating status of the steam and feedwater systems.

Objective To define certain conditions of the steam and feedwater system necessary to assure adequate decay heat removal.

Specifications 3.5.1 The primary coolant shall not be heated above 300°F unless the following conditions are met:

a. Both electric driven Auxiliary Feedwater Pumps and one fire protection pump shall be operable. The steam driven pump shall be operable prior to making the reactor critical.

b. The Auxiliary Feedwater System Instrumentation shall meet the minimum operability requirements addressed in Technical

• Specification 3.17.

c. All flow control valves associated with the Auxiliary Feedwater System shall be operable.

d. All valves, interlocks and piping associated with the above components required to function during accident conditions shall be operable.

e. A minimum of 100,000 gallons of water in the condensate storage and primary coolant system makeup tanks combined.

f. The main steam stop valves shall be operable and capable of closing in five seconds or less under no-flow conditions.

3.5.2 With the Primary Coolant System at a temperature greater than 300°F, the requirements of Specification 3.5.1 may be modified to permit the following conditions to exist. If the system is not restored to meet the requirements of Specification 3.5.1 within the time period specified below, refer to Specification 3.5.3.

a. One auxiliary feedwater pump may be inoperable for a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

b. Two auxiliary feedwater pumps may be placed in manual, for testing, for a period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

3-38 Amendment No. ~$, ~~'

TSPR8902

3.5 STEAM AND FEEDWATER SYSTEMS (Cont'd) 3.5.2 (Continued)

c. The fire water makeup to the Auxiliary Feedwater Pump Suction (P-8A and P-88) may be inoperable for a period of 7 days provided the pump service water makeup to P-8C, pump P-8C, and its corresponding flow control valves are operable.

d. The service water makeup to the Auxiliary Feedwater Pump Suction (P-8C) may be inoperable for a period of 7 days provided the fire water makeup to P-8A & P-88, pumps P-8A and P-88 and their corresponding flow control valves are operable.

e. One flow control valve on each train may be inoperable for a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided the corresponding redundant flow control valve and a pump in the other pipe train are operable.

3.5.3 With the Primary Coolant System at a temperature greater than 300°F and if the system does not satisfy the requirements of Specification 3.5.1 or the conditions of Specification 3.5.2 except as noted in Specification 3.5.4, the reactor shall be placed in hot standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, hot shutdown within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.5.4 With all Auxiliary Feedwater.Pumps inoperable immediately initiate corrective action to restore at least one Auxiliary Feedwater Pump to OPERABLE status as soon as possible and reduce power within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the lowest stable power level consistent with reliable Main Feedwater System operation.

3-38a Amendment No. ~~'

TSPR8902

3.7 ELECTRICAL SYSTEMS Applicability

• Applies to the availability of electrical power for the -Operation of plant components.

Objective To define those conditions of electrical power availability necessary to provide for safe reactor operation and the continuing availability of engineered safety features.

3.7.I Specifications The primary coolant system shall not be heated or maintained at temperatures above 300°F if the following electrical systems are not operable:

a. Station power transformer I-2 {2400 V).

b. Start-up transformer I-2 {2400 V).

c. 2400 V engineered safeguards buses IC and ID.

d. 480 v* distribution buses 11 and 12.

e. MCC No 1, 2, 7 and 8.

f. 125 V d-c buses No 1 and 2.

g. Four preferred a-c buses.

h. Two station batteries and the d-c systems including at least one battery charger on each bus.

i. Both diesel generators, with a minimum of 2500 gallons of fuel in each day tank a minimum of 16,000 gallons of fuel in the underground storage tank.

j. Switchyard battery and the d-c system with one battery charger.

k. 240 V a-c power panels No 1 and 2, and their associated ACB breaker distribution systems.

1. 2400 V bus IE.

3.7.2 The requirements of Specification 3.7.1 may be modified to the extent that one of the following conditions will be allowed after the reactor has been made critical. If any of the provisions.of those exceptions are violated, the reactor shall be placed in a hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If the violation is not corrected within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the reactor shall be placed in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3-41 Amendment No.

TSPR8902

3.7 ELECTRICAL SYSTEMS (Continued) 3.7.3 SHUTDOWN COOLING ELECTRICAL REQUIREMENTS With the primary coolant system at ~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 an operable diesel generator.

ACTION With less than the required electrical sources operable:

A. Immediately initiate action to suspend core alterations, 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 .

• TSPR8902 3-45a Amendment No.

3.7 ELECTRICAL SYSTEM (Continued) 3.7.3 SHUTDOWN COOLING ELECTRICAL REQUIREMENTS (Continued)

BASIS The operability of the minimum specified power sources and associated distribution systems during shutdown and refueling ensures that:

1. The plant can be maintained in the shutdown or refueling operation condition for extended time periods, and

2. Sufficient control capability is available for.maintaining the plant status.

When a single train of shutdown cooling must be operable to meet the minimum equipment operability requirements to remove decay heat, the train must still function following the loss of one electric supply (offsite power or diesel generator).

When two trains of shutdown cooling must be operable to meet the minimum equipment operability requirements to remove decay heat, the loss of any single pump or the loss of one electrical supply (offsite power or diesel generator) must still leave a shutdown cooling train operable.

The action statements will minimize the occurrence of postulated events, however, they should not preclude the orderly completion of an activity, such as fuel movement or crane operation, in order to get into a safe and conservative position.

3-45b Amendment No.

TSPR8902

Table 3.17.4 (Cont'd)

Minimum Minimum Permissible Operable Degree of Bypass No Functional Unit Channels Redundancy Conditions

8. Pressurizer Wide 2 Cm, p, q) None Not required in Range Water Level Cold or Refueling Indication Shutdown

9. Pressurizer Code 1 per None Not Required Safety Relief Valves Valve below 300°F Position Indication (Acoustic Monitor or Temperature Indication)

10. Power Operated Relief 1 per None Not required when Valves (Acoustic Valve PORV isolation Monitor or Temperature valve is closed Indication) and its indication system is operable

11. PORV Isolation Valves 1 per None Not required when Position Indication Valve reactor is depressurized and vented through a vent ~1.3 sq.in.

12. Subcooling Margin 1 None Not required Monitor below 300°F

13. Auxiliary Feed Flow 1 per 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 Actuation System below 300°F Actuation Channels

16. Excore Detector 1<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 3-8la Amendment No.%7, %$, ~%, J1~, J1$, 1~~'

TSPR8902

I***

TABLE 3.24-2

... -* ...,.RADIOACTIVE. GASEOUS-EFFLUENT** MONITORING ... INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APP LI CAB IL ITV ACTION

1. WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor (RIA 1113)

Providing Alarm and Automatic Termi-nation of Release (1) At All Times 35

b. Effluent System Flow Rate Measuring Device (FI 1121) (1) At All Times 36

2. CONDENSER EVACUATION SYSTEM (RIA 0631)

a. Noble Gas Activity Monitor ( 1) Above 210°F 37

3. STACK GAS EFFLUENT SYSTEM

a. Noble Gas Activity Monitor (RIA 2326 or RIA 2318) ( 1) At All Times 37

b. Iodine/Particulate/Sampler/Monitor (RIA 2325) (1) At All Times 37

c. Sampler Flow Rate Monitor (1) At All Times 36

d. Hi Range Noble Gas (RIA 2327)** (1) Above 210°F 38

4. STEAM GENERATOR SLOWDOWN VENT SYSTEM

a. Noble Gas Activity Monitor (RIA 2320) (1) Above 210°F 37

5. MAIN STEAM SAFETY AND DUMP VALVE DISCHARGE LINE

a. Gross Gamma Activity Monitor** 1 per Above 300°F 38 (RIA 2323 and 2324) Main Steam Line

6. ENGINEERED SAFEGUARDS ROOM VENT SYSTEM

a. Noble Gas Activity Monitor** 1 per Above 210°F 38 (RIA 1810 and 1811) room

• • Setpoints for these instruments are exempted from Specification 3.24.5.1 limits.

Setpoints for these instruments are governed by Emergency Implementing Procedures or operating procedures .

• TSPR8902 3-118 Amendment No. ~%, ~7,

I 3.25 ALTERNATE SHUTDOWN SYSTEM LIMITING CONDITION FOR OPERATION 3.25.1 The Alternate Shutdown System instrumentation and components shown in Table 3.25.1 shall be OPERABLE. Operability shall be demonstrated by performing the surveillances in accordance with Section 4.21.

APPLICABILITY:

Reactor coolant temperature > 300°F.

ACTION:

a. With less than the "Minimum Equipment" in Table 3.25.1 Operable, restore the inoperable equipment to Operable within 7 days, or provide equivalent shutdown capability and restore the inoperable equipment to Operable within 60 days; 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 /> and Cold Shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. The provisions of Specification 3.0.3 and 3.0.4 do not apply.

The operability of the Alternate Shutdown System ensures that any fire will not preclude achieving safe shutdown. The Alternate Shutdown System components are independent of areas where a fire could damage systems normally used to shut down the reactor. This capability is consistent with Regulatory Guide 1.97 and Appendix R to 10CFR50.

3-134

• TSPR8902 Amendment No. Jii,

Table 4.2.2 (Contd}

Minimum Frequencies for Equipment Tests

12. 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 that tanks T-102 and T-103 contain the minimum required volumes.

2. Verifying the concentration of hydrazine in T-102 and sodium hydroxide in T-103.

c. At least once per refueling cycle, during shutdown, by verifying that each automatic valve in the flow path actuates to its correct position.

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

• • TSPR8902 Amendment No. ~J, ~~'

TABLE 4.21. ntinued)

ALTERNATE SHUTDOYN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Surveillance Channel Description Function Frequency Surveillance Method

7. Start-up Range Neutron Monitor a. Test Prior to a. Internal test signal CN-001A) startup141

8. Auxiliary Feedwater Low Suction a. Calibrate Refueling a. Apply known pressure to pressure sensor Pressure Switch Cycle (PS-07410)

9. SIRY Tank Level Indication a. Check 01 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 121 a. Calibrate Refueling a. Apply known differential pressure to sensor(s)

Indication Cycle

( FI-07278)

CFI-07498)

11. Auxiliary Feedwater Flow Control 131 a. Check Refueling a. Verify Control Valves (CV-0727 & CV-0749) Cycle

12. Auxiliary Feedwater Pump Inlet a. Check Refueling a. Verify Control Steam Valve (CV-05228) Cycle (1) Quarterly checks are not required when the PCS temperature is less than or equal to 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.

(Next Page is 4-90) 4-88 Amendment No. 87, 1ZZ, 1~~.

TSPR8902

TABLE 4. (cont)

CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED

5. MAIN STEAM SAFETY AND DUMP VALVE DISCHARGE LINE

a. Gross Gamma Activity Monitor D M Above 300°F

6. ENGINEERED SAFEGUARDS ROOM VENT SYSTEM

a. Noble Gas Activity Monitor D M Above 210°F TABLE NOTATION

{l) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway occurs if instrument indicates measured levels above the alarm/trip set point.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if either of the following conditions exists.

a. Instrument indicates measured levels above the alarm set point (not applicable for Item 3.d, Hi Range Noble Gas).

b. Circuit failure.

(3) a. The CHANNEL CALIBRATION shall be performed using one or more of the reference standards traceable to the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range.

b. For subsequent CHANNEL CALIBRATION, sources that have been related to the (a) calibration may be used.

(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECKS shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous or batch releases are made.

TABLE FREQUENCY NOTATION D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Q At least once per 92 days M At least once per 31 days R At least once per 18 months p Prior to radioactive batch release w At least once per week 4-94 Amendment No. ~~' ii~,

TSPR8902

ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 TECHNICAL SPECIFICATIONS CHANGE REQUEST SHUTDOWN COOLING SYSTEM, REVISION 2 EXISTING PAGES MARKED-UP WITH PROPOSED CHANGES September 26, 1991 19 Pages

? AL :sADc:s ?'....~:: :::c:-'.~::c ..u. s2::c :: :i:~::::*:~s TABLE OF CO~TENTS - APP::~m!x A

• SECT!.ON l.Q

l. l DEFINITIONS OESCR!?T!ON REACTOR OPERATING CONDITIONS

? AG::

L-l

~- l

~:()

l *2 PROTECTIVE SYSTEMS L- 3 1.3

• INSTRUMENTATION SURVEILLANCE L-3 L.4 MISCELLANEOUS DEFINITIONS L-4

2. 0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETIINGS 2- l

2. l SAFETY LIMITS - REACTOR CORE 2- l 2.2 SAFETY LIMITS - PRIMARY COOLANT SYSTEM PRESSURE 2-3 2.3 LIMITING SAFETY SYSTEM SETl'INGS - REACTOR PROTECTIVE SYSTEM 2-4 Table 2.3.l Reactor Protective System Trip Setting Limits 2-5 3.0 LIMITING CONDITIONS FOR OPERATION 3-1 3.0 APPLICABILITY 3-1

3. l PRIMARY COOLANT SYSTEM 3-lb

3. l. l Op*rabl* Component* 3-lb Figure 3-0 Reactor Inlet Temp1ratur* vs Operating Pressure. 3-3a

3. l. 2 H1atup and Cooldovn Rat11 3-4 Figure 3-1 Pr111ur* - Tellq)eratur* Limits for Reatup 3-9 Figure 3-2 Pressur* - Temp1ratur* Limits for Cooldovn 3-10 Figur* 3-3 Pressure - Temp1ratur* Limit* for Hydro Test 3-11

3. l. 3 MinilllWI Condition* for Criticality 3-12

3. l.4 MaxiDIWI Primary Coolant Radioactivity 3-17

3. l. 5 Primary Coolant Sy1t .. L1akage Limits 3-20

3. l. 6 Maximua Pri.Jlary Coolant Ozyg1n and Halog*n*

Concentrati0119 3-23

3. l. 7 Priaary and Sec01lda~ Safety Valve** 3-25

3. l. 8 Overpre*sure Protection Sy*t ... 3-25a

,..3, /. 9 s-h~_,.,c~"*<- .J-.2.sf e 1 3.2 CB!MICAL AND VOLOMI CONTROL SYSTEM 3-26 3.3 !MllGERCT COil! COOLING SYSTEM 3-29 3.4 COITADIMENT COOLING 3-34 3.5 STUM AMI> F!EDWAT!I SYSTEMS 3-38 3.6 COITADIMDT SYSTEM 3-40 Table 3.6.1 Containaant Penetration* and Valve* 3-40b ~

3.7 ELECTllICAL SYST!KS 3-41 3.8 RD'U!LING OPDATIOtfS 3-46 3.9 ElFLUDT RELF.AS! (D!L!T!D) 3-50 i

&epeeaH* S, 198,.

t*

Aaandmant No. Jl, Jl, J7, IJ, t I l ll 1 4-i-&-

• TSP0689-0136-N1.04

3. l ?RIMARY COOLANT SYSTEM Aopl icabil it't Applies to the operable status of the primary coolant system.

Objective To specify certain conditions of the primary coolant system which must be met to assure safe reactor operation.

Specifications 3.1.1 Ocerable Comoonents

a. At least one primary coolant pump or one shutdown cooling pump with a flow rate greater than or equal to 2810 gpm shall be in operation whenever a change is being made in the boron concentration of the primary coolant and the plant is operating in cold shutdown or above, except during an emergency loss of coolant flow situation. Under these circumstances, the boron concentration may be increased with no primary coolant pumps or shutdown cooling pumps running.

b. Four primary coolant pumps shall be in operation whenever the reactor i$ operated above hot shutdown, with the following exception:

Before removing a pu_, from service, thermal power shall be reduced as specified in Table 2.3.l and appropriate corrective action implemented. With one pump ont of service, return the pump to service within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (return to four-pump operation) or be in hot shutdown (or below) with the reactor tripped (from the C-06 panel, opening the 42-01 and 42-02 circuit breakers) within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Start-up (above hot shutdown) with less than four plJllPS is not penaitted and power operation with lass than three pumps is not permitted.

c. The ..asurtd four pri111ry coolant PUllPS operating reactor vessel flow shall be 140.7 x 10- lb/hr or greater, .tlen corrected to 53z*F.

d. Both st*.. generators shall be capable of perform1ncJ their heat transfer function whenever th* average t~erature of the primary cool ant 1s above W,1 F. *

-- .*. . 306

e. Dlletld 3-lb Amendment No. JJ, *** JJ*, JJ,, JJJ, F1IPW1Fy ~

ae, l!!l

_:: :'-'_:._:,*:*  :: ... ~;: ~*:* ;:::~ .. .. ...

~....

4

>:~:-3.':~~ '::~oor:e!'l.i:s r(Jl'!i:'~)

h. Forced circulation (starting the first primary coolant ?UM?)

I shall not be initiated unless one of the following conditions :s ...

met: I

)

(l)

(Z)

Primary coolant cold leg tem~erature is > 430.F.

PCS cold le* temperatur* is 5 430.F and S/G secondary

~

\~

temperature is less than PCS cold leg temperatur1.

(3) Shutdown coolin~ is isolated from the PCS AND PCS cold leg temperature is > zio*r AND S/G secondary temperture is less >

~)

than ioo*r higher than PCS temperature.

( 4) . Shucdovn cooling i1 isolated f roa th* PCS AND PCS cold leg te=l'*ratura is ~ 11o*r and i 21o*t ANl> S/G secondary temperature 1s 1111 thaa. 2o*r h1&h*r than PCS cold leg te=l'*rature.

(5) Shutdovu. coolin1 11 isolated froa the PCS AND PCS cold leg ,)

temperature i1 ~ 120*1 and < i10*1 AND S/G secondary temperature 11 1111 than ioo*r hi&h*r than PCS cold leg temperature.

JCO

~

1. The PCS shall not be heated or maintained above ~F unl111 a /

minilllull of 375 kW of pre11urizer heater capacicy ia available from both buses 10 and.LE. Should heater capacity from either bua lD and LE fall below 375 kW, either re1core the inoperable heater* to provide at leaac 375 kll of heater capacity froa both bu*** 10* and l! within 72 houri or be ia hoc shutdown within the next 12 houri.

-Ba1i1 When priaary coolant boron concentration ia bein1 changed, the proces1 mu.c be uniform throu1hout the primary coolant sy1cea volume co prevent 1cratif ication of *priaary coolant ac lov.r boron concentration which could reaulc in. a reactivity 1n*ertion.

Suf Ucient aizina of the priaary coolant ia aaaured il one sl\utdown cooling or one priury coolac Puaf 1* in o,.ration.(l) The shutdOVD coolinl pump vill circ"1at* the priaary *Y*t .. volume ia le1a cha 60 U!luta* when OtMracad ac ratacl ca,&eit'J'. By ia'po*in1 a minillua ahutdovn coolina pump flow race of 2110 .,., sufficient time is provide* for cha o,eracof fo cer9inate th* boron dilution under aa,...cric flair cOllditian.1. 5 Th* preaauriaar voluae 1a relatively iBactiw-, therefOTe will encl to bne a born concentration higher t:Ma nee of die priaarJ cooluc *Y9t .. duriq' a dilutiC1l o,eration.

At?f*f*crati** procedure* vill prcn'id* for u.* of p?~aaurizor s~raye tcr .U.Caia. a nominal *l'r*acl becwen th* boron conc*ntracion in ( z) die pn*auria*r ad cha priury *Y*t* durtn1 the addition of boron .

• • • 111. %%1. J,ai""'

• TSP0290-0262-ll.04

J. L. ?R!~-~y CCOlANT SYST~ (?CS) (Continued)

J. l. 9 SHUTDOWN COOt!NG - This section only applies with fuel in the reactor.

Joa

a. PCS T*!p*r&tur* >200°F and ~~°F At least two of the loops or trains listed below shall b*

operable and at least one loop or train shall b* in operation:

"'\

( 1. Primary Coolant System Loop l con1isting of an op*rable Ste1m Generator and at least one operable Prim.ry Coolant Pump (PCP).

/

2. Primary Coolant Syat .. Loop 2 consiating of an operable Steam Generator and at least one operable Primary Coolant /

PUJlllt (PCP).

3. Shutdovn Cooling Train A.

4. ShutdoWll Cooling Train B.

!XC!PT!ON: '-.

Ali PCP* and Shutdovn Coolin1 may be intentionally securedSU" upf"1'1 hout-provided:

)

• • No operation* are peraitted that would cauae reduction of the PCS boron cotlcentration, AND b:- Core outlet t ..p1ratur1. atay1 at lea1t to*r balov saturation tem;1ratur1.

ACTION I I

A. If only 1 PCS loo' 11 operable and no SOC train* are operable: j

l. I..ediately initiate co~ective action to return a secoacl loop or train to operable 1tatu1.

B. If only l SOC train ii operable and no PCS 1001>>1 are operable:

1. '"'lmlldiately initiate co~ective action to return a

~econd loop or train to operable 1tatu1, AID Z. If a 1econd loOf or traa cmmoc be retuned to operable 1tatu1 b1 1111 cha 200*1 within 24 houri.

c. If no PCS loop* o~ Slnacdovn Coolinl train* are in operation vhen required:

1. Illmliadiately 1u1pand all operation* inTclvin1 a

• reduction in PCS boron coucentratiou, AND Y:- Im11ediately initiate corT*Cti*e action to return th*

• required loop* or train* to a,eration.

AandMnc tfo.

TSP0689-0140-NL04

2. L.  ?~::!A.:(,,'!

/'----- --~

.::C'!.A..'IT SYS:~

r?C'S) (Conc!.:'lued)

J. l. 9 *5Ht'~Ow"N COOL!~G (Continued) ~/

-.., * ,t(Y" ~

! b. PCS TeUlt)eratur1 ~200°F - Loops Filled a-' *

~ '

Ac lea*c one of r::he loops or r::r~s list*d below shall be /

operable and in operation and...One additional loop or traia shall be operable or r::he secondary si~e wacer level of each s r::eam generator* shall be higher than/minus 84\:_ F""u.--r /.,"4-J /

\ l. Primary Coolant Sy1c1m Loop l con*iscing of an I operable Steam Generator and at leaat one operable Primary Coolant Pump (PCP). J

(

\ 2. Primary Coolant Syst .. LoOl' 2 con*i*ting of an "

operable Steam Generator and at leaat one operable

""( Primary Coolant l'um1t (PCP). I I

3. Shutdowti Cooling Train A.

\. \

4. Shutdevtl Coolin1 Train B. I EXC!PT!OMi ~

Ali PCP1 and Shutdown Coolin1 may ~. int1ntionally >>e<:<<od}

provided:

vp1)1.ov

• I ~5~t2f a. ~o op1ration1 ar* pel"llitt*d that would cau1&

r1duction of the PCS boron concentration, I AND

\ S:- Cor* outl*t t1aperatur1 do** not exc11d 2oo*r.

I ACT!ON I

~ l A. If only one PCS loop or SDC train 11 operable when two are required:

(

I'

1. I~iat1ly initiate corrective action to r1tur11 th*

required 1001'1 or traina to operable 1tatu1. '

B. If a required Steaa Generator ha1 le11 than the specified vater lev*l:  !

)

l. Immediately initiate corrective action to r11tore tbe required Staaa Generator vater level.

\

c. If no PCS loop* or Shutdavn Coolins traill1 ar* ill )

.'\

operatioa when r1quirld:

1. Immediately 1Uapand all o,eration* involYin1 a )

AND

~

reduction in PCS boron concentration, Immediately initiate corr*ctiv* action co retur11 the required loop* or train* to operation.

3-2su..f Aaendaac No.

TS10689-0l40-NL04

J.l.

.-' ------ . _/ --- -

PRIY.ARY COOLANT SYST'EM (?CS) (Continued)

---

~-....--.........

• J. t. 9 SHUTDO\lN COOLING (Continued)

c. PCS Tellll'erature ~2oo*r - Loop* not filled

'l'vo Shutdowu Cooling trains (SDC) shall be operable, and at least one train shall be in operation.

EXCEPTIONS:

1. One SOC train may be intentionally rendered inoperable /

for testing or maintenance provided:

• • Th* other SDC Crain ii in operation

• fCa_ vP ~

2. All Shutdovn CooU.111 may be intentionally secured/\ J. t:fou<_

provided:

a. No o~eration* are per'llitted chat would cau** I reduction of che PCS boron concentration,

\

~

\

J

\

b. Core outlet te!ll'*rature do** not ezceed 200*1. (

ACTION

• I I

\

I I

A. If only one SDC train is required:

1.

o~erabl* when cvo are Illll9diately initiate corrective action co returu cvo train* to operable statu*.

I I

\ If no S])C train* are in operation when required: '

B.

)

1. t..iiately *U8f*d all Ql'eratian* involvi111 a reduction in PCS boran concentratioa,

-z.

AID I:m:diately initiate corrective action to returu the required train* to operation.

I I

\

\

I I

)

/

I"""

')

-~ - l-Z~ ~ Mina.at Mo. j

---

~ I TS10689-0l40-HL04

-nJ. l,

/' --- ----"

. ~

?~ r~.AR Y C~OLAN'!' SYST'D{ (PCS) (Continued)

' ( --

~

'/

_,- - l

.} ,

3. l. 9 BASIS A

SHt'TDOW'N C00t!'!1G (Continued)

Po,lJE>Atbo' sp~c.,'J,e.. ~,&,

~.-yte>Ji.;_e)~ 1-e..Jvwodr--1Ts~l.JT'd",_, l.c-oh/it::.-....7,. ~~* . \J "1J.41;,.s". How.,.,...,,. w11ic,,-T-k.'?-"';Wl *"-!;~'°"' "wJ;., clts(i.;s-~,,;~ -fl...L ~Jv-rdc"-1Cd'Oln,~...~,,,.s,_J-::Jf,,J, shutdown cooling train may vary in actual collll'onent configuration:( method

~/,7~ .... -

~

"' f

,~ ~

g

~

of operation and control, but it shall always accollll'lish che objective of *~ ~

,..,,I transferring decay heat from the reactor to Lake Michigan as the ultimate ~ ~ 'S

/

heac sink. As a minimum, a shutdown cooling train requires: a shutdown ~ 0 o 1,;

J\ cooling pum;i, one component cooling water punq>, one service water punq>, and *~ .~ .j

~*,/

appropriate piping, valves and controls for th* equipment to perform its ~ ~ 1\

function. All of chis equipment muat also have adequate electrical power .~.... ~;i '-- ~

to be operab 1e. , "1* -: .1.,

~ (J '

/

"toops filled" means the Primary Coolant system (PCS) loop* are intact, not -~ ~ ~

blocked by dama and totally filled with coolant. This permit* partial f- 0 i draining of th* PCS provided air has not entered the PCS loopa. o Th* loop* are considered "not filled" after th* PCS has been drained so air has entered the loops and air sweeps have not been completed to r ..ov* th*

~

'~8/v/

~\

gJ ~

air. Once th* PCS loope hav* b**n drained to any o:t*nt (install 1t1aa f \~

generator nozzle dams for example) there could be sufficient air trapped in 0 ~ ,~

th* upper portion of the steam generator u-tubea, even after the PCS water ~ ~ ~

level is raised, to prevent-natural circulation in ~cs. For this r*a*on, ~a ,~

the steam generators cannot be con*idered operable 1 th* PCS loop* are ~ f~ ~

.:!t:ela. completely filled with coolant and the air sweep* ce11pleted. .. ~ . ~ -j 360 f ~ *~

With th* PCS tmlll'*rature >2oo*r and <~l a single primary coolant 1001' ~ ~- ~

or shutdown cooling train provide* sufficient heat removal capability for 't'~ ~ ~

removing decay heat. Natural circulation i* adequate for core beat . £,/VJ ~

removal, however it may not provide adequate mixin1 of the PCS coolant ~~.~ ~ ';'

during PCS boron concentration change*. Therefore, forced circulation ii ~ i~ ~~

required during th*** operatin*1 condition*, except durin1 intei.val* when { ~ j "7 the required loop* or train* can be intentionally rendered inoperable ~~ ~

provided additional conatraint* are followed. SiB1l* failu~* aeeaidewatioa~

f~h'.'"'

01

..'- '118*'--

c.Y'A...{9t>4ie = Dt>ptn

-" "' ..,tn'1' 40op.-rq ~Fol S'-.&..A4otUI~ * ~:0.-, ~p-.-.,/

'*if" *a~pma:t1lo~*11..,.1....,~1n*., 1,4.r./ ~ ..:r"""-va I a~i.;11 \

th the PCS temperature <2oo*r and t

• loop* filled, a 11n1l* prlaary ,

I coolant loop or shutdovn coolin1 train provide* sufficient heat reaoval \

capability for rnovin1 decay heat. The stea 1enaratore raove heat by (

bulk haating of che secoaclary 1id* vacer rather than craatin1 st*. .

• I Natural circulation i* adacruat* ** a backup however it uy not prOYide adequate mixin1 of the PCS ccclet durin1 PCS

• • an* for core heat remaval, ,

\

'J 1

I boron concentrati01l chans*** In additon, it i* difficult to maintain

\ PCS cmperature <2oo*r, if the only uthod of core heat r*oval i*

\ natural circulation. Tiler.tore, forced circulatioa 1* required durin1 th*** op*ratinl conditiona, ezce't durin1 intertala vhen th* required I

l loop1 or train* can be intentionally secured provided additional .

constraint* are f ollaved. ..final* failure eGGaideratian* raqair* a iicoud i-eop, train, e~ the saaolldary 1id* wacer level of bocb ice.. generatoc*-'"

a* abev* moms* 84.. -..IA st** generator secondary vatar level of at leaet ('

t to aupport natural circulation in the PCs.< *,,a)

~ 8~~-~ a* /oc.::Hd 197. 91neAm J-Jc_,

=r).. ~~~,/J;-" ~ ?}#Olv1.avc--,;,, J'lh6 *.  ;

3-25f~h* /

Aaendaent No.

- - - ..,,,.,I ,,,,.

TSP0689-0140-HL04

~

,..------.-.~~v~,~-------

3. L. PRL~Y COOLAN'!' SYSTEM (PCS) (Continued) --... *

• 3. 1. 9 BASIS SHUTDOWN (Continued)

~1th the PCS temperature COOLI~G (Continued)

Re.$'";,,,*'- er ~n. -fffd /oop'-~,;,

~ q b/t<_ p J..-o.J1 tz4.a

• fl_

"11?4?'~ ~p ~/rf:"' I>/ v,Y ~C)-->

I /.

4 rl~e.o.y At'e./~ (/'11~ J aa.p q .6///7Z1 .

0°F and the loops not filled, a single f ~

n S° ~ -e 04..6v)'~ <U_ ~o /

J,...fl...

Q2J Q;

..., An; b1*eJIA1;;1!i*?Jun1/r>ro//...v.)v/7/;, .:t.. ~s.r po ;~

shutdown cooling train rovides sufficient heat removal capability for removing decay heat. Z.a provt4e s4e~tiaee *i*ing 0£ the PCS eoolane during KS Qgz:;a uauauacigca r:h &RIJU, fg:c:1d eirealactoa ts e e"{ttin4 d1uia1 ehis epewacica1 coadiciga **cep* 4ttring iat1l'Yal1 ~ea lRe required e~aiftl ean QI iac1ationall1 eend1t1d inoperable provtdid additional eonacrai~ts are /

-lollowad. Si.ail* f ail'tll'* cou1ideraci;n1, and tb1 uaavailae ilit'1' of the steam gene!'ators as a heat l'emevin1 component, require that a second-I I

I H1:lEEiewn eeolin1 tra1n ea operaele

• So+h 'St)(! o...,4 PCS ot'd:l fe*e** circulation~ b1 !ai:'*C*d,provided action* are dilution of the PCS and'l;~oid situation* that could produc steam in the reactor vessel. When the PCS t.amperature is >2oo*p and <)K*r, maintaining

~1o*r subcooliJ11~~"sure1 th* availability of single -pha1* natural

),

"fo -t"./Z4,ff$1'11:i#d ~ ~p-ro O'l'IA- ou,... ~

300 eu to prevent

/

)'

/

circulation. ~ °CS~'l'cs temperature -=. ~2oo*r ~ tp1ad:ias- ZP'kf ~/so ensures th* availability of a single pha1e natural circulation.

l I

I A tNdQlidin~ train of SDC m.ay be intentionally rendered ino~erable for testing or maintenance for any tim. interval provided the other SDC train is in operation. No time limit is specified becau1e the time interval that is needed fo each required evolution could vary. Thi1 method of operating equipmen is con1i1tent with the intent of Generic Letter 88-17,

)

Losa of Decay Heat *oval. It i* recoimended that equipMnt b* maintained and tested as appro riate to create an acceptable level of confidence that th* system* will be bl* to perform their decay heat removal function.

Therefore,appropriat te1tin1 or maintenance 11 con1idered prudent and justified, without an specific time limit related to equipment that m.ay be inoperable to permi such evolutiona. In all ca1e1, the intent i1 to take rea1onable act

• to ainiaize the u1e of ezception No. l of specification 3.1.9.c. If it i1 required to u** exception No. l of specification 3.1.9.c, S vill not be rendered inoperable in situation*

where PCS t*lll'*rature i* 101* to 200*1 or the PCS heatu~ rate would .

result in th* PCS taapera re ezceedinl 200*1 in a relatively short (

period of tiu. //,4. °1WtJ SDC. f;.o1;,,s- Q.&£. :nol-/OT-/'1 111~~d...,,,7 ~,,,~ -t-k.., s:~ C.,.,.,.,.-no,c.-,

~l/c.J;;,, tl-t?d d,,.s'c.ha-t1.P p1p/ni:.. 1~c.JvtlJ 11~ //tJ/~

M0-301S;Wo-30~~,. c v.-saob; C.V-.30-1.5"~C V;{?oSS:

{tj '1-BB/<!6 J.~ OP.S-t:ll-0'1116 ,111,,,,~~ o/6t.""~7 f~~,;~J 1'

S"u pp01I /Yo}ul'r:J/ C 11:~ 1.1/ei'J/11rJ Dtcoy d~lI<'a,.,,,,, 0 116 / .

i Ny;1zr

~ /;;.) Ccrns-_u~F!',w..,,~~'f E;'e.1~4M;"ff:.. Ahfo/~sir EA-~rP-1tJ-o'j-,

• t<...,, ,,,.., o 7PeJ,,,,,e *I K.,,,..., <>/.1988/u- L" ~ ops-'!1-a.,6 *1 Amendment N o J J

TSP0689-0l40-NL04

3. 5 ST!.AM ANO F!tilWATER SYS!EMS

• Applicabili;z Appli** co che operacing scacu* of the see~ and feedvac*r sy1ca11a ..

Obj ecCive ro caf ina c1rcaia coadicion* of the *t*Ma and f *edvac1r sy1c1s n1c1*1ary co ***>&re ad.equau decay iliac r..aval.

SeecUicacion1 . :..*. 3~

3.S.l Th* primary cool:.~c 1'1all aoc be heats~ .11b;* ~ wilua I folloviDI condi:i~~* are met:

a. Boch *l1ccric driven Awlili&ry r1a~c1r Puaf* and one fire proc*ctto*'. p*!~l'7 *ball be operable~ The IC** driv.-11 puaii 1t1&ll be op~~abl* prior co r.1~1:11 cha nac~or critical.

b. Th* Auzi~. of.Ary Fee4'..a car Sy1!! ** Iucrumnca~1a11 1ball ?ll9et cha m.1Dilr.;.a cperabili~.y requir ...~tl adclre111d 1A T11ctmi ... d Speci!i;a:io~ 3.17.

c. All flow c01atrol valvt1 a1aociace4 vitb cbe Au.ziliary readvater Syatc 1ball be op~ru!~.

d. All valve1, iAC*~locu :\U pipiD1 u1ociaucl rich che above cOlii~onenc1 r*quired !o func:ioa duru1 accident c~1C1oaa shall be ar*.rabl*.

• • A E.**:!r.3 of 100,0!'~ g*'.lku of near iD the co11deuac1 1cora~.

ancl ~rt?P:ry cool:.:lc ttJ*C*r. ~up ca*-..~. coabuad.

f. The :""**~.iA 1c. . 1cop valve* 1b&ll be operabla uacl ca,..bi. of cl~~~I 1a fiva ..c~a or la.. UDllar ao-fl09 cOIMlit1otl9.

• 300 3.5.2* Wit&& -;be Pn.ar, Cool.a& Sylc* ac a c_.racu~ lf!'.tC*r *:baa .Ja1*1, */

cha raquir.-ca of Specificac1oa J.S.1 *7 be mclifiad co ;us.tc ctie followtaa c..Ueior.a co auc. If die .*y:::s i* uc ru~or** co ***r:

dl9a~of s,.cificaCiOll 3 * .5.1 vteb.".11 the CiM periocl 9i'T_ 'ff:ot 'elowa r*f~r co Specificacioa 3.5.J.

~~ *

...CiuJ t.eclvacer pump *1 be ~rabla fo~ a period of

b. TIM aailia17 tleclwtar P-.11.*?"' "'~1 be placet 1a amul. tor

~1ac1111, for a period of 4 boara.

AaeDclme!lC Mo. ~ !i , -%-

IIW.,. 381 1986-

• ~*IZWCLacl lC/97/96 TS11Ql6-01471-lfl.04

J. 5 S:'!AM A.'m FE:EDl.'A7!?. SYS7~S rc~nc Id) 3.S.2 (Coac1nued)

c. 1"h* fire wacer ~akeup co ehe Auxili~ry Feedwacer ?ump Succ~on (P-8A and P-88) 12l&Y be inoperable for a period of i day1 provided che pump service wacer 12l&keup co ?*8C, pump ?*8C, a~~

ics correspondinc flov concrol valves are operable.

d.  !'he ser-tic* wacer makeup co che Auxiliary Feedvac1r Pu=11 Succion (P-8C) may be inoperable for a period of 7 days provided chi fir* wacer makeup co P-8A & P-81, pu=11* ?-~A ar.~

P-81 and chair corr1epondin1 flov concrol valves are operabLe.

• • One flov concrol valve on each crain may be inoperable for a p*riod of 72 houri provided chi corr1epondin1 redundanc flow concrol valve and a p~ in che ocher pip* cr&in are operabl1.

3 * .5. 3 With che Primary Coolanc Sy1c1* ac a C191'1racur1 1r1ac1r chaa ~F I and it che 1y1c .. do11 aoc 1aci1fy ch* :1qu1r ... ac1 of Specif icac1oa 3 * .5.l or ch* condicion1 of Sp1cificac101a 3 * .5.2 1xc1pc a1 aoc1d 1n Sp*cifieaciou 3 . .5.4e th* reaccor 1ball be placed in hoc 1candby vicbin 6 houri. hoc 1bucdovt1 vicbia the follovilll 6 houri and in cold ahucdOvtl vichin ch* follovinl 24 houri.

3 * .5. 4 Wicb all Ausili&r7 f11dvac1r "8mp8 1Ao,1rabl1 i ...diat1l7 iAiCi&CI corr1cciv* accion to r11cor* ac l***C one AuziliAry F11dwac1r Pua, 4, co OP!IAILI 1cacu1 a1 1oon .. po11ibl1 and r1duc1 pov*r vitbia 24 houri co chi lov11c 1cabl1 povtr 11v1l co1S1i1c1nc vith reliable Main F11dvac1r Sy1c1* op1racion. ~

AMada1n c ~o. -%-

iaR t1 IS)' lQ: LIJU

3.7 ELECTRICAL SYSTEMS Applicabilitz Applies to the availability of electrical power for the operation of plant components.

Objective To define tho** condition* of electrical pover availability n1ce11ary to provide for 1af1 reactor operation aDd the continuin1 availability of 1n1in1er1d 1af1ty featur***

3.7.l Specification*

The primary coolant 1y1t .. 1h&ll not be lle&ted or .. intained at te9l)u*ature* above ~r if th* follaviD.c electrical 1y1c. . are not f operable: 3IJO

• • Station power tranafor.er 1-2 (2400 V) *

b. Start-up cran.fo-r.er 1-2 (2400 V).

c. 2400 v 1n11D**r*d 1af esuard1 b~* lC and lD.

d

• 480 V diatribution bu*** 11 and. 12.

f.

I*

h.

KCC No 1, 2, 7 and 8

• 125 V d-c bu*** No l and 2.

Four preferred a-c: bua***

Tvo 1tation batterie* and the 4-c 17*t... 1Dclud1n1 at l***t one battery cbar1er OG each lnaa.

1. loch 41...1 ....ratoT*, ritla a e1**ee of 2500 pllou of fuel in each cla7 taak llld a a1n1,... of 16,000 sallOGa of fuel iA the und*raroaad acorqe tank.

j. SV1tch7arcl ktte17 ad the d-c 11*t* with one batterJ cbar11r.

k. 240 f a-c poser panel* lo 1 act 2, ad their uaociatecl ACI br*a'*~ 4"9tritiliit1oa S719t-..

1. 2411Y ... 11.

3.7.2 The r~CI of SpecificatiOG 3.7.l .., be ao41fied to th* eztent that oa. of CIMI follow1aa c01Mlit1oaa will be allOV9d after th* reactor haa been ucl* critical. If 8111 of tile prnuiou of tho** esca,tiona are violated, the reactor (hall be placed iA a hot abatclOWD condition within 12 hoar** If th* riolAtioD u oot corrected wtclda 24 houri, the reactor aball be placed in a cold alnatdovn cODdition within 24 houri.

3-41 TSP0583-020S.-RL04

J. 7 ~~CTR!CAL SYST::fS (Continued)

J. 7. 3 SHUTDOWN COOtI~G ELECTRICAL. REQU!REM!'STS

• \

a.

.JOO Wit~ the ptim&ry coolant !yscem ac ~3'!'!°F, and with fuel in che reactor, che !hutdown cooling crain(s) shall be electrically powered as follow*:

If one crain of shutdown cooling is required co meet specification 3.l.9:

/

\

1. The appropriate engineered saf1guard1 bu1 (lC or 10)

I shall be operable and capable of btin1 supplied by /

\I offsite power and an operable die1el generator.

Oil

/

i

\ I b.

2. Have two train* of shutdovu coolin1 operable, and meet all che requirements of 3.7.3.b belov.

If cvo train* of shutdown coolin1 ar* requir*d to ***t

~

specification 3.1.9, on* engin**r*d safeauard* bu*

(lC or lJ)) shall be operable ' **kla _..d*I omc/

supplied by off sit* power while the oth*r en1:1.neer1d saf eauard1 bu* (lJ) or lC) i i operable and capable of

/N';12T--;/' bein1 supplied by an operable di***l 1*nerator.

I i ACT I OK

\

~ With l*** than the requir*d *l*~trical source* operable:

A. I**dia'tely 1nitiat* actio11 to 1uapend cor* alterations, I I

/

\I I

B. Immaciiately iDitiat* action to 1u1p1nd .av..ent of irradiated fuel,

/

I I

c. Immmcliately 1u1pend crane operation* over irradiated )

fuel.

~ ~c1,*;r-~f )

D.~~ op1ration* vith a potential tor drainin1 th* PCS or fuel pool, I

AND

~,,..

~-;f',. \"'\ <

I

!. ~tiat* action to re1tore th* required elect?'ical i source1 to op1rabl1 St&tu1

• I

• TSP0619-0140*Mt04 3-45a Amendment No. ./

3. 7 Et~C7~!CAL SYS1EMS (Continu*d)

3. 7. J SHUTDOWN COOLING ELE~ICAL REQUIREMENTS (Continu*d)

• ~

s.. 1.

1'h* operability of th* minimum sp*cif ied power sourc** and associated distribution system* during shutdown and refueling ensures chat:

l. The plant can be uiaintained in che shutdown or r1fueling mode for 1xtended tilll9 perioda, and

2. Sufficient control capability i* available for maintaining the plant stacua.

When a single train of shutdown coolin1 muat b* operable to meet tha minimum equipment operability requir ..anta to remove decay heat, that train mat still functi01l follovin1 th* loaa of ona I I

electric supply (offait* or dieaal 1enerator). (

\

Whan two train* of shutd0V11 coolin1 muat be 01>>*rable to meet th*

minimum equipment operability requir ...nta to rewiove decay heat, J th* lo** of any sin1l* PWll> or th* lo** of ona electrical sup~ly

"\

(off ait* or die*el generator) muat still leave a shutdown coolin1 train operable.

The action statement* vill ainia:lza th* occurrence of poatulatad I

'\

i evant1, hovavar, they should not preclude the orderly completion of an activity, such aa fuel mov..ent or crane operation, in order I to get into a safe and caa1arvative*po1ition. /

i I

/

\

/

\

)

)

)

Aaelldment N~

~-------

TSP0689-0140-IL04

Table 3.~~.;. (Conr::'d)

~inimum ~inimum Peniis s ib le Operable Degree of Bypass

~;o ?u:-:c:i:rnal ~:~ir:: Channels Redupdancy Condir::ions

?!'essurizer Wide 2 (m, p

• q) None Not reouired in 8.

Range :.*acer Level Cold or Refueling

!ndicat:ion Shutdown

9. Pressurizer Code 1 per None Not Required Safety Relief Valves Valve below ~F Position Indication 300° I (Acoustic Monitor or Temperature Indication}

10. Power Operated Relief 1 per Non* Not required when Valves (Acoustic Valve PORV isolation valve Monitor or Temperature is clos*d and its Indication) indication system is op.rable

11. PORV Isolation Valves l per Non* Not required whan Position Indication Valv* reactor is d*pr*ssurized and v*nt*d through a vent ~ 1. 3 sq. in.

12. Subcoolin1 Margin 1 None Not nquired Monitor below~* I Jed'

13. Auxiliary FHd Flow l p*r flow(h) None Not required Rate Indication Control bdov ~F I Valv* .JIJ/J.

14. Auxiliary Fe*dwat*r 2 per steff 1 Not nquind Actuation System generator ) below ~F I S*nsor Channel* Joo*

2<f) 1 Not r*quired

15. Auxiliary FHdvater Actuation Systm b*lov ~ I Actuatiou Channeh .300

16. Excor* Detector i<*> None Not Required Below Deviattoa Alarma 2S% of R&ted Power

17. Axial Sha,. Inda 2<1> 1 Not Required Below Alarm 25% of Rated Paver

18. Reactor Ves*el 2 (j .~,l,a)

None Not Required -J.

Belav ~P I Water Level 30,/

3-81&

Amendment No. ?U,

• 1, u*. *~H,

• TSP0889-0176-NL04 s., **** u. 1989

TABLE 3.24-2

• RADIOACTIVE GASEOUS EFFtrENT INSTRUMENT MONITORI~G MINIMUM

!SSTRt"MENTATION CHANNELS OPERABLE APPLICABILITY ACTION

l. WASTE GAS HOLDUP SYSTEM

a. Noble Gaa Activity Monitor (RIA 1113)

Providin1 Alat'11l and Auto111&tic Termi-nation of Release (l) At All Times 35

b. Effluent Sy1tam Flow Rate Maaaurin1 Davie* (PI 1121) (l) At All Times 36

2. CONDENSER EVACUATION SYSTEM (RIA 0631)

a. Noble Gaa Activity Monitor (1) Above 210°F 37

3. STACK GAS E!TLUElrr SYSTEM

a. Noble Gaa Activity Monitor (RIA 2326 or RIA 2318) (l) At All Times 37

b. Iodina/Particulata/S&Jlll'l*r/Monitor (1) At All Tim** 37 (RIA 2325)

c. Sampler Flow Rat* Monito~

. (l) At All Timas 36

d. Bi R.ange Noble Gaa (lIA 2327) ** (1) Above 210°1 38 i

4. STEAK G!NDATOR BLOWDCMI VENT SYSTEM

a. Noble Gu Activity Monitor (lIA 2320) (1) Above 210°? 37

5. MAIN STEAK SAFITY AID DUMP VALVE DISCBAIGE LID

.JOO Above ~' 38

a. Gro** G..a Activity Mo1litor ** 1 per Main Stea (lli 2323 alMi 2324)

Line

6. ENGINEEllD SAnGUAIDS IOOM VDT SYSTEM 38

a. Noble Gu Act:lrity Monitor ** 1 per room (RIA 1810 and 1811)

• • Setpoint* for th*** inatruaent* are ex911l't*d froa Specification 3.24.5.1 limits.l Setpoint* for th*** inatruaent* are 1overued by Ell9r1ancy I11Pl ... nting

• Procedure* or operatinl procedure*.

3-118 Aaencmant No U, &r Af*'! 29, U85 TSl084-0001-ML02

J

• 25 AL T!R..~A !! SHLJ'!DOW'N SY STEM tL~IT!YG CONDITION FOl OPEJU\T!ON

3. 2~. l Th* Alternate Shutdown Syscam inacrumencacion and com;ion*nts shova in Table 3.2~.l shall be OPERABLE. O~erabilicy shall be d..0111craced by perf otiaing the surveillance* in accordance with Section ~ I Jj. J.l

• APPLICABILITY:

Reactor coolant te'ml'*rature ~_..,.... 3 o o0 F.

ACTION:

a. With 11H than the "Minillua !quipent" ill Table 3. 2,.1 ot>>*rable, re1tor* th* inoperabl* equipment to Op*rabl* within 7 day*, or provide 1quival1nt shutdown capability and r**tore the iAOl)*rabl*

equip**nt co ott*rable within 60 clay*; or be in Hot ShutdOVll within th= next 12 hour* and Cold Shutdown within the follavilll 24 houra.

b. Th* proviaiona of Specificatio1l 3.0.3 aacl 3.0.4 do not a,ply *

. Baaia Th* operability of the AlterD&te Shucdawa Sy1t.. 11!9Ur** tbat any fir*

will not preclude acbieTilll 1afe. abutdown *. The Alternate Shutdown Syat..

compon*nt* are ind.pendent of area* where a ftre coald d...1* 1y1t1..

normally uaed to 1but dow the reactor. Thi.* ca,ability i* coaai1t1nt with R*aul*tory Guida 1.97 &llCI Anadiz I to iocruo.

3-134 Aaaclwnt lo.~

..,. 11, 1911 TS11185-0335-lt04

Table 4.2.2 (Coned)

Minimwl r~eguenci*! fa~ Equip=enc Te*c*

12. !odin* Reacval Sy1c1a The Iodine Removal Sy1c .. *hAll be d..anacrac1d operabl*:

a. At leaac once per 31 day1 by verifytn1 cbac each valve (manual, pov*r operated or auco..cic) in cbe f lov pacb chac 11 noc locked, 1ealed or ocbenr11e secured in po1ition, ia in 1c1 corr*cc po1ieion.

b. At leuc once per 6 aantha by:

1. VerifyiDI Chat tank.I T*l02 alMl t-103 coataiA the w1n1*&m required volumea.

2. Verifyin1 cbe c~encracion of hydraaille in T-102 UMl 1octiua hydrozid* 1A T-103.

c. Ac hue oaca per nfuliq cycle, duriq 1hucdon, by verifyi.q chac eac:b aucoucic valv* 1A tb* flow pach accuaca1 co ica COrTICC poaicioa. /

v

~ \l ;

~\\

1

13. Concaiamanc Puri* alMl Ventilacioa Iaolacion Valv** 7"' ,,....-/

\'..I/'/J- /

Th* Concaimenc Puri* UlCI Vat11acioe Itolacioa Val*** shall be ( I/'

I /

decenlinad clo1ed:

I

/

• • Ac i ...c oace per 24 hoar* '1 ch*ckills cha val** po1itioa iDdicaCOT ill cha COllCrol roam

b. Ac 1...c oace eYer)' 6 ..acb.a b7 perforailll a leak race caac beCW* cJae TalYUo

> 14.

., .~aerator required to Met che 1hucdCND cooliD1

.,ecificacioa 3.1.9, it* 1ec0Ddary near lnel

/

\ ...,_'l!'iW ac i ...c cmc* per 12 b.ara co be no.e aiml*

-( ./- .,,

_

.~ i ~ I~ sJ,,.rcl~ ~ohw"ta i N;_'-"

70 ""'"'7~ .,s-J.,ra'o,..,,

ct,, /A'2. k~1.11i,a/

~oJ,,,;1:1 "- ,,~~..u

,,.,.e-,;., c.~J..,,/

. -..7..s-JS"Cr,n.

j:Ut1.-nip/r)11J.

~./. 9:

,,,!f;,;~ay;w,~s-y,: b-'.

d-6~,h#,,,~d To .b~ 0,~Rl'l~J.£ 07t-. P"' 7 a_,,s- Jy 11-*o/,,1.-e:.~ OT bH~k>>J o/,6",,,,~.r "'"IO ,,,<J,i,"J;dpow""1 DC II e} \

IH'oi'loJu//T'f'. ~ ),

. b 7k ~lud ~ G~;;,-~~)rl,.11 j; . -

TS10915-0270-lll.04 4... "I

• _JJ_ cl !I. d il'-'1"' 1..ld Of'eeABJ..I:

_,~"<r"'"'""s~ -i.nQI' ';';r.o, 1-wl.,.ob-<<.~ -~.f% *orl~~lvnet IZ. "°"'"S . . rf~'" .

.CP"'1Arl'1N7~ <!4'0/o.,t-/oop~..s-J,~11 6 ..... ~1/1.;d ?'o k ,;, ~6>-r;~ ~<I

• (! l.1'CV/c-1i11;., uoih1 l!.<Jo/o-Ttd'/er.TtnUll. /l>>f /Z l/6U"S"*

• f'ffticl)

IABLE I,. OOl inued)

!LifR!!Alf Slt\JIQOW!I !!O!f!IOll!NG !HSJRU!tfMI!IIOH SlJ!l!/f ILLN!CE REQU!Rfp!ENJS

&urveillance fr!Cl!MMX Syryej ll!Of! Method QlMJWl pwcipt ,.,

Prior to ** lnt*rr.-l t .. t *illftlll (performd under lable 4.1.l)

Source . _ . llallron llllnl tor *. l*t

1. atartup101 (11*1/X)

• • fuel ine ** Aflply knuwn pr..llUC* to pr..aur* aet'lllor

• • tallbr*t*

• • Cvcl*

• • Clleck'"' au.rterly ** C:..,.r* irGif*idlllt level rudi,.a

9. 11. . 1. . L.wel lndlca&I*

CLl*IJUI>. b. Aflply knuwn differential pr..aur* to level aenaor

... tallbr*t* **fueline cvcl*

lefueline ** AIJply knuwn differential preaaUl"c to aen&or<*>

AY&Uluy f . . . .tar f l

• lat*

181 ** callbr*t*

CVCl*

"* Indication Cfl*IR11>

Cfl*l1411>

lefuel 1111 ** Verify CClntrol a.au luy 1.-.ter flaw CGnlrol 1~ 1 ** CMck

"* v.awe ccv-1121 & cv-~149>

cvcl*

lefuelilll ** Verify Control Ausl l luy f .....ter .... Inlet ** CMck 1z. Cvcle Ihm Velw CCV*IAJI>

\ -r. 300* f=.

/CS "(.-,.....~*"c."I>**

(1) QIWterly dleck er* not r_,.lred .._ ~-- I* l ... than W.. I CZ> latl*fl* 19bl* 4.1.J*1S a.qua....-nt.

CJ> ... lfeCUlcaclon 4.tla.

C4> Prier te Mda atart** If not dane prevl- ..-.

(Heat Page ia 4*90) 1,-68 A11ic1~1icn1 No. llll, JU, -Ho-

~--t-'.r,--WY~ -

TABLE 4.24-2 (cont)

CHANNEL HODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVF.I Ll.ANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIREU

5. MAIN STEAM SAFlft MID DUMP VALVE DISCHARGE LI*

.100

a. Gro** Ge** Activity Monitor D H R(l) Q(2) Above ~°F

6. lllGJllEllllD SUIGl***DS IOCll VDT SYSTIH

a. llobla Gu ActivitJ llooitor D H ll(l) Q(l)(2) Above 210°F TABLE NOTATION (1) The CllAIDIEL JUllCTIOHAL TIST ahall alao deaonetrate that autoaatic isolation of this pathway occurs if inatruaent indicate* aeaaured level* above the alara/trip aet point.

(2) The CllAIOllL FUllCTIOllAL TIST ahall alao demonetrate that control roet1 alara annunciation occurs if either of the follovina condition* aai*t*.

a. lnatruaant indicate* . .aeurad levela above the alara s~t point (not applicable for Item 3.d. HJ Range llobla Gae).

b. Circuit failure.

(3) a. !be CllAlllllL CALIBllATIOlt *hall be performed .uaing one or aore of the reference standards traceable to the lational luraau of Standard* or u*ing atandarde that have been obtained fro* suppliers that participate in aeaaur...nt aaaurance activities with NBS. These standards shall permit calibrating the *J*t. . over it* intended raaae of energy and aeaaur. .ent range.

b. for eub..quant CIHAlllllL CALllllATIOll, *ourcea that have been related to the (a) calibration may be ueed.

(4) CllAIDllL CHICK ehall coneiet of verifying indication of flow during periods of release. CHANNEL CHECK ehall be .... at laa*t once par 24 hour* on daya on which continuous or batch releases are made.

TABLE FREQUENCY NOTATION At least once per 92 days D At laaat once par 24 hour* Q At least once per 18 months H At laaet once per 31 day* R At least once per week p Prior to radioactive batch release W 4-94 Amendment No. , -hY-

~ay JO, l~U~

TSP0287-0003-NL02

• ATTACHMENT 3 Consumers Power Company Pali sades Pl ant Docket 50-255 TECHNICAL SPECIFICATIONS CHANGE REQUEST SHUTDOWN COOLING SYSTEM, REVISION 2 REVISION 1 PAGES WITH REVISION 2 CHANGES MARKED September 26, 1991

• 7 Pages

3.1 PRIMARY COOLANT SYSTEM (PCS) (Continued) 3 .1. 9 SHUTDOWN COOLING - This section only applies with fuel in the reactor.

a. PCS Temperature >200°F and ~300°F At least two of the loops or trains listed below shall be operable and at least one loop or train shall be in operation:

1. Primary Coolant System Loop 1 consisting of an operable Steam Generator and at least one operable Primary Coolant Pump (PCP).

2. Primary Coolant System Loop 2 consisting of an operable Steam Generator and at least one operable Primary Coolant Pump (PCP).

3. Shutdown Cooling Train A.

4. Shutdown Cooling Train B.

EXCEPTION ~ ..,plo I hou All PCPs and Shutdown Cooling may be intentionally secured,provided:

a. No operations are permitted that would cause reduction of the PCS boron concentration. *

~

AJID. Core outlet temperature stays at least l0°F below saturation temperature.

ACTION

• A. If only 1 PCS loop is operabl~ and no SOC trains are operable: *

1. It'lllled1ately initiate corrective action to return a second loop or train to operable status.

B. If only 1 SOC train is operable and no PCS loops are operable:

1. Innediately initiate corrective action to return a second loop or train to operable status, If a second loop or train cannot be returned to operable status be less than 200°F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

C. If no PCS loops or Shutdown Cooling trains are in operation when required:

Innediatel~ suspend all operations involving a reduction 1n PCS boron concentration, Inmediately initiate corrective action to return the required loops or trains to operation.

3-251 e.. Amendment No .

TSPR8902

3.1 PRIMARY COOLANT SYSTEM (PCS) (Continued) 3 .1. 9 SHUTDOWN COOLING (Continued)

b. PCS Temperature ~200°F -

At least one of the loops or tr ns listed below shall be operable and in operation and ne additional loop or train shall be operable or the secondary side water level of each steam generator shaTl be higher than the minus 84 percent level:

1. Primary Coolant System Loop 1 consisting of an operable Steam Generator and at least one operable Primary Coolant Pump (PCP).

2. Primary Coolant System Loop 2 consisting of an operable Steam Generator and at least one operable Primary Coolant Pump (PCP).

3. Shutdown Cooling Train A.

4. Shutdown Cooling Train B.

EXCEPTION P,, uPfo I J, oVI'"

All PCPs and Shutdown Cooling may be intentionally secure~provided: I*

a. No ogerations are permitted that would cause reduction of the PCS boron concentration, AND

0. Core outlet temperature does not exceed 200°F.

ACTION A. If only one PCS loop or SOC train is operable when two are required:

1. Immediately initiate corrective action to return the required loops or trains to operable status.

B. If a required Steam Generator has less than the specified water level:

1. Immediately initiate corrective action to restore the required Steam Generator water level.

c. If no PCS loops or Shutdown Cooling trains are in operation when required:

i.. Immediately susgend all operations involving a reduction in PCS boron concentration,

~ required

!mediately initiate corrective action to return the loops or trains to operation.

3-25'j Amendment No.

TSPR8902

' ( ' .,

3 .1 PRIMARY COOLANT SYSTEM (PCS) (Continued) 3 .1. 9 SHUTDOWN COOLING (Continued)

c. PCS Temperature ~200°F -*Loops not filled Two Shutdown Cooling trains (SOC) shall be operable, and at least one train shall be in operation.

EXCEPTIONS:

1. One SOC train may be intentionally rendered inoperable for testing or maintenance provided: vR.

~ 11p 1ri 1.

a. The other SOC train is in operation.

2. All Shutdown Cooling may be intent i ona 11 y securedf\provided:

a. No operations are permitted that would cause reduction of the PCS boron concentration, AND

b. Core outlet temperature does not exceed 200°F.

ACTION A. If only one SOC train is operable when two are required:

1. I11111ediately initiate corrective action to return two trains to operable status.

B. If no SOC trains are in operation when required:

1. Immediately suspend all operations involving a reduction in PCS boron concentration, AHl2

2. I11111ediately initiate corrective action to return the required trains to operation.

3-25' t Amendment No.

TSPR8902

3 .1 PRIMARY COOLANT SYSTEM (PCS) (Continued)

' ' ' /

3 .1. 9 SHUTDOWN COOLING (Continued) ~h.T.q/u, f p.u.;J,c. rk:uC:-,., ~,,.,or 1~ "'4' i.I Hdvmd~/S"#V'k/ou.-n t!.cchh~ S'f..rl~ "ha-,,,- "

"'~ "-' u~ ~lliG -1..I ~~ "-+-r 41 ' J_ J ' u - J ..LI

• BASIS s -:--r-

'(St~

"/

• TAA.. "#kh77 J "" "" ~ _ . , a1s ~ "ss14 e. ...,~ S71v,/ao'-""1 AC,1~'ldUo tM1WS'TO'f"fd11i"*

t!c 1 *

~"'~6 A shutdown cooling train 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 the ultimate heat sink. As a minimum, a shutdown cooling train requires: a shutdown cooling pump, one component cooling water pump, one service water pump, and appropriate piping, valves and controls for the equipment to perform its function. All of this equipment must also have adequate electrical power to be operable.

"Loops filled" means the Primary Coolant System (PCS) loops are intact, not blocked by dams and totally filled with coolant. This permits partial draining of the PCS provided air has not entered the PCS loops.

The loops are co.nsidered "not filled" after the PCS has been drained so air has entered the loops and air sweeps have not been completed to remove the air. Once the PCS loops have been drained to any extent (install steam generator nozzle dams for example) there could be sufficient air trapped in the upper portion of the steam generator u-tubes, even after the PCS water level is raised, to prevent natural circulation in the PCS. u-~r this reason, the steam generators cannot be considered operable ~the PCS loops are -aat:.completely filled with coolant and the air sweeps completed.

With the PCS temperature >200° F and s300° F a single primary *coo 1ant loop or shutdown cooling train provides sufficient heat removal capability for removing decay heat. Natural circulation is adequate for core heat removal, however it may not provide adequate mixing of the PCS coolant during PCS boron concentration changes. Therefore, forced circulation.is required during these operating conditions, cept during intervals when the required loops or trains can be inte *anally rendered inoperable provided additional constraints are followed. -Si11gle faih1re eoRsideratiens require a seeeRd loop or train (either PCS or shutdown cooling) be operable. Operation of the shutdown cooling trains is limited to when the PCS temperature is s300°F because 300°F is the maximum temperature used in the stress analysis of the shutdown cooling system piping.

When the PCS temperature <200°F and the loops filled, a single primary coolant loop or shutdown cooling train provides sufficient heat removal capability for removing decay heat. The steam generators remove heat by bulk heating of the secondary side water rather that creating steam. Natural circulation is adequate as a backup means for core heat removal, however it may not provide adequate mixing of the PCS coolant during PCS boron concentration changes. In addition, it is difficult to maintain PCS temperature

<200°F, if the only method of core heat removal is natural circulation. Therefore, forced circulation is required during these operating conditions, except during intervals when the required loops or trains can be intentionally secured .provided additional constraints are followed. Single failure coas1deratiens 1eq~;re a-Amendment No.

TSPR8902

-~ ~F ,. ,,

• 3. 1 PRIMARY COOLANT SYSTEM (PCS) (Continued) l 3 .1. 9 SHUTDOWN COOLING (Continued)

~ BASIS (Continued)

~

~

• ~ ~

~1

~ rj

-!eeerHJ 1eep, tieai R, er tl:~e seeoAdary s i 9e liter 1evel of eoH steam

~eAe1 ateYs ee a~ove tAe actual ffiiA~s 84 ~erEeRt level.

..:pQreeAt is loeatee 197.9 iRCRes below tRe eeAterline of tAe main*

Minus 84

' -~ ' ~ l:l'-- .f.eeawate1 1 ;11g-:- A steam generator secondary water level of at least

~ t ~

I

'rr.-...

minus 84 percent covers at least one-third of the effective steam generator heat transfer1 2area and is sufficient to support natural circulation in the Pcs< * >.

~~ ~

~~ ~}

~ ~1 ~~

j E~ -~

~ ~~ ~s d Jf ji I~~ t So+h Sl:>C..~d PCS. - -t"f;;3.111'e.Tt<l-fon'-'Pll> cm.c. lla~r-All fereea circulation may beA~ate8 provided actions are taken to

• i1J

~~

prevent dilution of the PCS and~avoid situations that could produce steam in the reactor vessel. When the PCS temperature is >200°F and

<300°F, maintaining ~10°F subcooling ensures the availability of single phase natural circulation. ~rhe PCS temperature45-

~2000F, ~t exeeed;ng 200°F 1ensures the availability of a single phase natural circulation. L-o/so '/J'/6i~"'J4.,~1H6 A .f'MM:da:A: train of SOC may be intentionally rendered inope'rable for testin~ or maintenance for any time interval provided the other SOC train is in operation. The two shutdown cooling trains are not totally independent since they share common suction and discharge piping No time limit is specified because the time interval that is needed for each required evolution could vary. This method of operati g equipment is consistent with the intent of Generic Letter 88-17, ass of Decay Heat Removal. It is recommended that equipment be main ained and tested as appropriate to create an acceptable level of confi ence that the systems will be able to perform their decay heat rem val function. Therefore, appropriate testin~ or maintenance is consi red prudent and justified, without any specific time limit related t equipment that may be inoperable to permit such .

evolution . In all cases, the intent is to take reasonable actions to minimiz the use of exception No. 1 of specification 3.1.9.c. If it is requ red to use exception No. 1 of specification 3.1.9.c, SOC will not b rendered inoperable in situations where PCS temperature is close to 200°F or the PCS heatup rate would result in the PCS temperature exceeding 200°F in a relatively short period of time.

(1)

ABB/CE Letter ~-91-0496, "Minimum S/G Level Required to Support Natural Circula ion Decay Heat Removal."

(2)

Consumers Power ompany Engineering Analysis EA-GFP-90-03, Revision 0 "Technical Revie of ABB/CE Letter OPS-91-046."

3-2St.i.

Amendment No.

TSPR8902 /~c/vc/;hu vo/v-uJ /1/()-go1~ M0-3011;/ CV-30tJb/

c v- 3 0 .a 5' Ch} d (J v -.:Joss-:.

.,,.. -~ .... ,, ' 3 . 7 ELECTRICAL SYSTEMS (Continued) 3.7.3 SHUTDOWN COOLING ELECTRICAL REQUIREMENTS

• With the primary coolant system at s300°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 3.1.9:

1. The appropriate engineered safeguards bus (lC or 10) 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 3.1.9, one engineered~jeguards bus {lC or 10) shall be operable aA4 ea~ael& ef :Be~supplied by offsite power while the other engineered safeguards bus (10 or lC) is operable and capable of being supplied by an operable diesel generator.

ACTION With less than the required electrical sources operable:

A. I11111ediately initiate action t~ suspend core alterations, B. I11111ediately initiate action to su~pend movement of irradiated fuel,

c. Inmediately suspend crane operations over irradiated fuel, Mil

~uspend operations with a potential for draining the PCS or fuel pool, E. ~nitiate action to restore the required electrical sources to operable status.

3-4sa Amendment No.

TSPR8902

.... _-:i Table 4.2.2 (Contd)

Minimum Frequencies for Equipment Tests

12. 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 that tanks T-102 and T-103 contain the minimum required volumes.

2. Verifying the concentration of hydrazine in T-102 and sodium hydroxide in T-103.

c. At least once per refueling cycle, during shutdown, by verifying that each automatic valve in the flow path actuates to its correct position.

13. Containment Purge and Ventilation Isolation Valves The Containment Purge and Ventilation Isolation Valves shall be determined closed:

• a.

b.

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 At least once every 6 months by performing a leak rate test between the valves.

14.

For any s generator required to meet the shutdown cooling require nts o specification 3.1.9, its secondary water level shall be v 1fied at lea once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to be above minus 84%.

I JI. S hv'Tdor..--., C.oo \ ~l.:>1 70 ~1~ -s/,v"tdot.-n C<Jt:J/me. ~1~7S-a/S"';-JI,_;, !S. J. 9:

a,,,7A.e H!..fJ~'~ILttlc--;b; ~/a..,,Tp1.1n??F1(s),,,6J ~o7~n ~ei77..,,.;,/ s-A"~.11d bfl.. c:J,~4?/u!-'d~/J-.._Ol'E~,981..r em~ ~ 7d~.s Jr v-4All.f1'1G C!cA/lw'cJ

../;;-~b, o//~~]j- ~d 1~ulli:!o/,,d f'~ av~ /o.b.-4JY .

.h, 7he.1-~~~1.4d' s-"Ma-,, ~/t:r1($.) slie-1/ b-ll (l,~,,,,.,,,~d .., I \t...0~4Ji?ABL5 6~ tnut/11111~ --1"k. S"-tt::...-nd04'1 ~e.T..#1 1~~; To la.~ a! - 8'"1 % Q/ lwPe?.s7

~ae. f?-"'1 /,:2.. Aau;S. 4-lSb . *

<71--(r"'~ Amendment No. ~J, ~~.

(!

• 1'9/ /l'4::i( ~ ~/IJ-Jf/ feop/~ho// be ~;/Nol~~ ~J;~

th-id c. J>~ v /111"hn*L. 1-111 c-r~ Ct;ttJ)~T o 7 #o.:17~P1"I ~ /2IZ1 / ::z. ); rJ u ;s TSPR8902