Text

Proposed Tech Specs Re Shutdown Cooling Sys
	ML18057A890
Person / Time
Site:	Palisades
Issue date:	05/01/1991
From:	; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	;
Shared Package
ML18057A889	List: ML18057A888; ML18057A890;
References
	NUDOCS 9105130055
	Download: ML18057A890 (40)
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ATTACHMENT 1 Consumers Power Company Palisades Plant Docket 50-255 TECHNICAL SPECIFICATIONS CHANGE REQUEST SHUTDOWN COOLING SYSTEM PROPOSED PAGES May 1, 1991 19 Pages 910501

~11()~1 :30055 (>5000255

~ i l :

~D~- ADOCK PDR i. i F'

, I SECTION

~ADES PLANTDESCRIPTION TECHNICAL SPECIFI~S PAGE NO 1.0 DEFINITIONS 1-1 1.1 REACTOR OPERATING CONDITIONS 1-1 1.2 PROTECTIVE SYSTEMS 1-3 1.3 1NSTRUMENTATION 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-lb 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 3-25d 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 * -EF~LUENT.RELEASE (DELETED) __ 3-50

\

\ 0 i

Amendment No. pl, ,,, ,7, ~ 1~~. JJ~, Ji~.

TSPR8902

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.l.1 and appropriate corrective action implemented. With one pump ant of service, return the pump to service within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (return to four-pump operation) or- be in hot shutdown (or below.) .with. the reactor td pped (from the C-06 panel, opening the 42-01 and 42-02 circuit breakers) within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . Start-up (above hot shutdown) with less than four pumps is no.t permitted and power operation with less than three pumps is not_permitted.

c.

The measured four primarl coolant pumps operating reactor vessel flow shall be 140.7 x 10 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~, 1~*, 1~7, 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.

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 hi~her 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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in hot shutdown within the next I2 hours.

Basis When primary co;olant 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 resul~ in a reactivity insertinn.

Sufficient mixing of the primary coolant is assured if one shutdown cooling or one primary coolant pump is in operation.< 1 > The shutdown cooling pump will circulate the primary syste.m 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 to5 terminate 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 cool ant system during a dilution operation.

Administrative procedures will provide for use of pressurizer sprays to maintain a nominal spread between the boron concentration in the pressurizer and the primary system during the addition of boron. <2 >

3-Id Amendment No ~7, ~~' JJ7, JJ~, J~J, TSPR8902

j' 3.1 PRIMARY COOLANT SYSTEM CPCS) (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 ~f an operable Steam Generator and at least one ope~able 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 provided:

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

AND D. Core outlet temperature stays at least 10°F below saturation temperature.

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

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

B. If only 1 SOC train is operable arl'd 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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 -init-iate corrective action to return the required loops or trains to operation.

3-25d Amendment No.

TSPR8902

3.1 PRIMARY COOLANT SYSTEM (PCS) (Continued) 3.1. 9 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 one 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. Primart Coolant System Loop 1 consistinl of an operable Steam enerator and at 1east one operab e Primary Coo.l ant Pump (PCP).

2. Primart Coolant System Loop 2 consistinl of an operable Steam eneratcir and at least one operab e Primary Coolant Pump (PCP).

3. Shutdown Cooling Train A.

4. Shutdown Cooling Train B.

EXCEPTION All PCPs and Shutdown Cooling may be intentionally secured provided:

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

~equired 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

2. Immediately initiate corrective action to return the Tequired loops or trains to.operation, 3-25e Amendment No.

TSPR8902

.I, 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 (SDC) shall be operable, and at least one train shall be in operation.

EXCEPTIONS:

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

a. The other SDC train is in operation.

2. All Shutdown Cooling may be intentionally secured provided:

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

~ Core outlet temperature does not exceed 200°F.

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

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

B. If no SDC 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.

3-25f Amendment No.

TSPR8902

3. l'

.3. l.'9 PRIMARY CO~ SYSTEM CPCS) (Continued)

SHUTDOWN COOLING (Continued)

BASIS 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 appropri~te 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 loo~s 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 when the PCS loops.are not 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,

~xcept durtng intefvals when the required loops or trains can be intentionally re~dered inop~rable provided additiohal constraints are followed. Single fatlur~ considerations require a second loop or train (either PCS or shutdown cooling) be operable.* 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 treating steam. Natural circulation is adequate as a ba~kup means for core heat removal, however it may not provide adequate mixing of *the* *pcs cool ant dliri ng* 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 considerations require a 3-25g Amendment No.

TSPR8902

'3 .1 ~

3 .1. 9 PRIMARY COO. SYSTEM (PCS) (Continued)

SHUTDOWN COOLING (Continued)

BASIS (Continued) second loop, train, or the secondary side water level of both steam generators be above the actual minus 84 percent level. Minus 84 percent is located 197.9 inches below the centerline of the main feedwater ring. A steam generator secondary water level of at least minus 84 percent covers at least one-third of the effective steam generator heat transfer 2area and is sufficient to support natural circulation in the PCS 0 * >.

With the PCS temperature ~200°F and the loops not filled, a sin~le shutdown cooling train provides sufficient heat removal capability for removin~ decay heat. To provide adequate mixing of the PCS coolant during PCS boron concentration changes, forced circulation is required duririg this operating condition except during intervals when the required trains can be intentionally rendered inoperable provided additional constraints are followed. Single failure considerations, and the unavailability of the steam generators as a heat removing component, require that a second shutdown cooling train be operable.

All forced circulation may be isolated provided actions are taken to 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. When the PCS temperature is

~200°F, not exceeding 200°F ensures the availability of a single phase natural circulation.

-A redundant train of SOC may be intentionally rendered inoperable 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 oper9ting equipment is consistent with the intent of Generic Letter 88-17, Loss of Decay Heat Removal. It i~ 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 testin~ 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, SOC 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 Remova . 11 (2)

Consumers Power Company Engineering Analysis EA-GFP-90-03, Revision 0 "Technical Review of ABB/CE Letter OPS-91-046. 11 3-25h 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 t.he Pr~ mary Coo 1ant System at a temperature greater than 300° F, the requirements of Specification 3.5.1 may be modified to permit the followin9 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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

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

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 Suet ion

{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-SA 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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , hot shutdown within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in cold shutdown within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the lo~est stable power level consistent with reliable Main Feedwater System operation.

3-38a Amendment No. ~~'

TSPR8902

3.7 ELECTRICAL SYSTEMS App 1icabil ity 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.

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

operable:

a. Station power transformer 1-2 (2400 V).

b. Start-up transformer 1-2 (2400 V).

c. 2400 V engineered safeguards buses IC and ID.

d .. 480 V distribution buses 11 and I2.

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

f. I25 V d-c bu.ses No. I 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.

Bpth diesel gener~t9rs, with a minimum of 2500 gal1ons of fuel in each day_tank a minimum of. I6,000 gallons of fuel in the .

underground storage tank.

j. ~witchyard 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 followin9 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . If the violation is not corrected within~24 hours, the reactor shall be placed in a cold shutdown condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3-41 Amendment No.

TSPR8902

3.7 3.7.3 ELECTRICAL ~MS {Continued)

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 cap~ble 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 capable of being supplied by offsite power while the other engineered safeguards bus (ID or IC) is operable and capable of being suppl~ed 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. f~e l"',

AND C. Immediately suspend crane operations over irradiated fuel, ,

D. Suspend operations with a potenti~l for draining the PCS or fuel pool, E. Initiate action to restore the required electrical sources

- To oper*abl e status: * -

3-45a Amendment No.

TSPR8902 \

.l

3. 7 .

3.7.3

. fl ELECTRICAL SYSTEM (Continued)

SHUTDOWN COOLING ELECTRICAL REQUIREMENTS (Continued)

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

fl' Table 3.17.4 (Cont'd)

Minimum Operable Minimum Degree of

Permissible Bypass No Functional Unit Channels Redundanc:t Conditions

8. Pressurizer Wide 2 (m, 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 Ch> below 300°F Control Valve

14. Auxiliary. F:.eedwat_er 2 per J

Not _required Actuation System steam below 300°F Sensor Channels generator'*> *

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) 1 Not Required Al ar111 Bel.ow 25% ot Rated Power

18. Reactor Vessel. 2(j,k, 1,m) None Not Required Water Level Below 300°F 3-8la Amendment No~~7, ~~' ~~' 11~, 11~, Ji~.

TSPR8902

TABLE 3.24-2

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

1. . WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor (RIA 1113)

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

b. Effluent System Flow Rate Measuring Device (Fl 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 BLOWDOWN 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** I-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 arid 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.

3-118 Amendment No. ~~. ~7.

TSPR8902

3.2~ ALTERNATE S~WN 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and Cold Shutdown within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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 Amendment No. J~~.

TSPR8902

_...... (*

12.

Table 4.2.2 (Contd)

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 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 'hours 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. Steam Generator Secondary Wat~r Level For any steam generator required to meet the shutdown cooling requirements of specification 3.1.9, its secondary water level shall be verified at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to be above minus 84%.

4-15b Amendment No. ~J, ~~,

TSPR8902

TABLE 4.21.1 (Continued)

ALTERNATE SHUTDO~N 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 (N*001A) startup141

8. Auxiliary Feedwater Low Suction a. Calibrate Refueling a. Apply known pressure to pressure sensor Pressure Switch ,

Cycle CPS*0741D)

9. SIRll Tank Level Indication (LI *03328)

10. Auxiliary Feedwater Flow Rate 121 Indication *

a. Check 1' 1

.b. Calibrate

a. Calibrate Quarterly Refueling Cycle Refueling Cycle

a. Compare independent level readings

b. Apply known differential pressure to level sensor

a. Apply known differential pressure to sensor(s)

( FI-07278)

CFI-07498)

11. Auxiliary Feedwater Flow Control 131 a. Check

Refueling a. Verify Control Valves CCV-0727 & CV-0749) Cycle

12. Auxiliary Feedwater P~ Inlet a. Check Refueling a. Verify Control Steam Valve CCV-05228) Cycle (1)

(2)

(3)

(4)

Quarterly checks are not required when the PCS temperature is less than or equal to 300°F.

Satisfies Table 4.1.3-15 Requirement.

See Specification 4.9b.

Prior to each startup, if not done previous week.

(Next Page is 4-90) 4-88 Amendment No. 87, J22, JJ6, TSPR8902

r, TABLE 4.24-2 (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 0 M Above 300°F

6. ENGINEERED SAFEGUARDS ROOM VENT SYSTEM (1)

a. Noble Gas Activity Monitor D M TABLE NOTATIOW Q(l) (2)

Above 210°F 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 ex1sts. *

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 sh-all 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 ~alibrating 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous or batch releases are made.

D M

p At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months At least once per 31 days Prior to radioactive batch release TABLE FREQUENCY NOTATION Q At least once per 92 days R At least once per 18 months w At least once per week

4-94 Amendment No. ~~' Ji~,

TSPR8902

ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 TECHNICAL SPECIFICATIONS CHANGE* REQUEST SHUTDOWN COOLING SYSTEM EXISTING PAGES MARKED-UP WITH PROPOSED CHANGES May 1, 1991 19 Pages

SECTION PALISADES' PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A DESCRIPTI.ON 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 P-ROTECTIVE SYSTEM 2-4 Table 2.3.1 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-lb 3 .1.1 Operable Components 3-lb 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. j 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. /. 9 c

'5:),~rc1o u-r'J ~ h iltb 3-..2.sd 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 ;f.

3.7 ELECTRICAL SYSTEMS 3-41 3.8 REFUELING OPERATIONS 3-46 3.9 EFFLUENT RELEASE (DELETED) 3-50 i

Amendment No. 31, J1, J7, 8J, 108, 118, -H&-

Septemeer §, 1989 TSP0689-0136-NL04

. 3. 1 PRIMARY COOLA~'STEM App 1i cabil ity -

Applies to the operable status of the primary coolant system.

Obiective 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 ont of service, return the pump to service within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .. 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 primarl coolant pumps operating reactor vessel

.flow shall be 140.7 x 10 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 coo1ant i s above :ai!f F. I 300 e.

1

3. t

3. 1. l (Conc'd)

Operable Componencs (Cont'd) h.

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

(1) Primary coolant cold leg temperature is > 430°F.

(2} PCS cold leg temperature is :ii 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 > 210°F AND S/G secondary temperture is less than 100°F higher than PCS temperature.

(4) Shutdown cooling is isolated from the PCS AND PCS cold leg temperature is ~ 170°F and ~ 210°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 ~ 120°F and < 170°F AND S/G secondary temperature is less than 100°F higher than PCS cold leg temperature.

JOO

i. The PCS shall not be heated or maintained above ~F unless a /

minimum of 375 kW of pressurizer heater capacity is available from both buses lD and. lE. Should heater capacity from either bus lD and lE fall below 375 kW, either restore the inoperable heaters to provide at least 375 kW of heater capacity from both buses lD and lE within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in hot shutdown within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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 if one shutdown cooling or one primary coolant pump is in operation. (l) Th~

shutdown cooling pump will circulate the primary system volume in less than 60 minutes when operated at rated capacity. By imposing a minimum shutdown coolinR pump flow rate of 2810 gpm, sufficient t.ime is provided for the operatofsfo terminate the boron dilution .under asymmetric flow conditions. . The pressurizer volume is relatively inactive-, therefore vill tend. to have a boron concentration higher than r**t of the primary coolant system during a dilution operation.

A4wfnf8trative procedures will provide for use of pressurizer sprays to maintain a nominal spread between the boron concentration in ( 2) tb* pr**aurizer and the primary system during the addition of boron.

3-ld Amendment No f7, IJ, 111, lll, ~

ol!pl'tl i!6, U98 TSP0290-0262-NL04

.... ----~

'(__. 3. i. PRIMARY COOLANT SYSTEM (PCS) (Continued)

( 3.1.9 SHUTDOWN COOLING - This section only applies with fuel in the reactor.

Joo

( a. PCS Temperature >200°F and ~~°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 I provided:

)

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

AND

b. Core outlet temperature stays at least 10°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 ax:e operable:

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

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

.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 Z:- Immediately initiate corrective action to return the required loops or trains to operation.

Amendment No. _____,/

TSP0689-0140-NL04

.. 3. 1. PRI~Y~l.Al!T SYSTEM (PCS)

-~

3.1. 9 SHUTDOWN COOLING (Continued)

b. PCS Temperature S200°F - Loops Filled

//

/ ~* ~

At least one of the loops or trains

// .

listed below shall be (

\

operable and in operation and one addiytonal loop or train *\

shall be operable or the secondary si~e water level of each

steam generator sha"il be higher than/minus 84\:._P-""°""'-\ /c..,c.I I .

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.

EXCEPTION:

Shutdown Cooling Train B.

All PCPs and Shutdown Cooling may be intentionally

. provided:

se:.:~:.~ed

/

\

a. No operations are permitted that would caus~

reduction of the PCS boron concentration, AND I h:'""" 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. I~ a required Steam Generator has less than the specified water level:

L 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.

3-25. e.. Amendment No.

TSP0689-0140-NL04

" e. ~ ;. ._,,.,,.~-

ee

.~~:::.----;----*-------------------

/ 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 (SDC) shall be operable, and at least one train shall be in operation.

\

EXCEPTIONS: !

1. One SDC train may be intentionally rendered inoperable (

for testing or maintenance provided: '

a. The other SDC train is in operation.

)

2. All Shutdown Cooling may be intentionally secured .

provided:

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

/

ACTION AND

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

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

1. Immediately initiate corrective action to return I

two trains to operable status.

B. If no SDC trains are in operation when required: I

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

\

AND

2. Immediately initiate corrective action to return

./

.1 the required trains to operation.

\

)

\

/~

~- '~. 3-25*~ J/

--._______ Amendment. No.

~

TSP0689-0140-NL04

f .'9

. . ~~ -~

3. l. 9 SHUTDOWN COOLING (Continued) ~ ~"

BASIS ~ ~f~

A shutdown cooling train may vary in actual component configuration, method

~ ~~ f ;~ ~ ~

of operation and control, but it shall always accomplish the objective of /"t:J *- .1i transferring decay heat from the reactor to Lake Michigan as the ultimate , ~ li."'S

.... Q \.i .

heat sink. As a minimum, a shutdown cooling train requires: a shutdown '\*.. o cooling pump, one component cooling water pump, one service water pump, and * '~ ~ ~

appropriate piping, valves and controls for the equipment to perform its J:-- ~ ~

function. All of this equipment must also have adequate electrical power ~ ~ ~

to be operable. 1 1

~ -~

-1~ "1 "Loops filled" means the Primary Coolant system (PCS) loops are intact, not blocked by dams and totally filled with coolant. This permits partial ~ u. ~

draining of the PCS_provided air has not entered the PCS loops. (] \~8 l 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

.8 ::~l")V/

~

J 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 ~

od f *~

~ ~

,~

level is raised, to prevent natural circulation in the res. For this reason.~ ~ .~

the steam generators cannot be considered operable when the PCS loops are ~ ~ ~

~ not completely filled with coolant and the air sweeps completed. ~ ~ ~ ~

I .!JOO With the PCS temperature >200°F and <~F a single primary coolant loop f

~

~ *~

~. ~

or shutdown cooling train provides sufficient heat removal capability for ~ ~

removing decay heat. Natural circulation is adequate for core heat V7 ~

removal, however it may not provide adequate mixing of the PCS coolant SJ ~ ~

during PCS boro.n concentration changes. Therefore, forced circulation is ~ * ~~

required during these operating conditions; except during intelvals when ~ J ~

the required loops or trains can be intentionally rendered inoperable -N ~

provided additional constraints are followed. Single failure considerationsj require a second loop or train (either PCS or shutdoWri cooling) be operable.

With 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 than 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 additon, 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 considerations require a second loop, train, or the secondary side water level of both steam generators be abov minus 84 * ~A steam generator secondary water level of at least a mi s 84 is s ffic t to support natural circulation in the Pcs.<*Jz)

/Jl,M- 8-'lpLieHJ/ ,f /ac~Hd /97. 9,,,,,;c.A4LJ .Jp/ow

-r-JA c.1>.,.£n~-1fl¥4 ~ ,,,,,,01h/"~~ I-Jn& .

TSP0689-0140-NL04 3-25'~

Amendment No.

'r' '

/

/'

3. 1.

PRIMARY COOLANT. SYSTEM (PCS) (Continued)

3. l. 9 SHUTDOWN COOLING (Continued)

BASIS (Continued)

With the PCS temperature S200°F and the loops not filled, a single shutdown cooling train provides sufficient heat removal capability for removing decay heat. To provide adequate mixing of the PCS coolant during PCS boron concentration changes, forced circulation is required during this operating condition except during intervals when the required trains can be intentionally rendered inoperable provided additional constraints are followed. Single failure considerations, and the unavailability of the steam generators as a heat removing component, require that a second shutdown cooling train be operable. . 300 All forced circulation may be isolated provided actions are t~o prevent dilution of the PCS and avoid situations that could produc~;;; *in the reactor vessel. When the PCS temperature is >200°1 and <lii 0 l, maintaining

~10°F subcooling ensures the availability of single phase natural circulation *. When the PCS temperature is S200°l, not exceeding 200°1 ensures the availability of a single phase natural circulation.

A redundant train of SDC may be intentionally rendered inoperable for testing or maintenance for any time interval provided the other SDC train is in operation. No time limit is specified because the time interval that is needed fo each required evolution could vary. This method of ~,

operating equipmen is consistent with the intent of Generic Letter 88-17, Loss of Decay Heat emoval. It is recommended that equipment be maintained and tested as appro riate to create an acceptable level of confidence that the systems will be ble to perform their decay heat removal function.

The ref ore, appropriat testing or maintenance is c.onsidered prudent and .

justified, without an specific time limit related to equipment that may be inoperable to permi such evolutions. In all cases, the intent is to take reasonable actf ns 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, SC will not be rendered inoperable in situations where PCS temperature is lose to i00°l or the PCS heatup rate would \

result in the PCS tempera re exceeding 200°1 in a relatively short period of time. -r-1 -+- --!-:' -r- /.

1 n'l. /UJfJ SDC- 1ra1;,S-Q,4Lmo1 10To '1

/ n ria,,p~d~Ts-/n~ -Tk '1 S' hCvtJZ.. C-trw1~ crYJ

~VC.ktrn .

ti) /1BB/C.li ~7/~ DPS-91-0't~b 'ftlt;,,-_,,~ VG J.~~41 af)u/;4J

~ u ppai'T /YoTur"J C11-C.1.1 IQPllYJ DFc.o't/7"1'4TRQ.."7>'101/<:./ 11* .

~ ~) (}<ms-_u~~~~~'t £;ic.1~~;Y1G Ama./ys1S- E/J-tTFF'- ?tJ-o3 iN5f{Zf ~1s1"'1 0 /P°J,.-m_cc./ i<<W14<) o/A/38/cE Le~ ops-~1-0~1:.*1.-;,-

TSP0689-0140-NL04

i' 3.5 STEAM AND FEEDWATER SYSTEMS

~1

Applicability Appli** to the operating status of the staa.i and feedwat*r ayste!R8.

Objective To aaf ine certain conditions of th* st*~ and feedwater system necessary to aaa;.ire adequate decay iv at removal.

Specif icationa *. ... . ;¢ 3.5.1 The primary COOk.~t s1:1all not be heat6d 1.b~;. #':' unleH th* I following condi:i~~* are mat:

a. Both electric d.riven Auxiliary Feed,,ater Pwapa and one fire protect1o:*. pu;~i> shall be operable~ Th* 1team driv~a pump shall be ope"~abl* prior to 1r'.l~.i:lg th* reactor critical.

b. Th* Auxi~. tary Fead1.racer ~ystt111 Inatnmwntaz.ioa shall !!!111et th*

lllinillr..in c.perabil:Ly requirem*wte addreaaad in Tl!chni-.:d ~. **

Specif1;~~1o~ 3.17.

,~*

c. All flow control valv** aa1ociatad with th* Auxiliary Feedvatar Sy1te~ 1ball be op~rab!~.

d. All valv*** interlocka ~ud piping a**ociaud with th* above cow~onanta required !o func:ion during accident con'11Cions shall be or*-,rabl*.

e. A mi*:1s:.3 of 100,0CO g::lkru of water in th* condensate storae<

and pri:.71ry cool::i.t tty*ter. makr;;:up u**;*'*~* combined.

f. The ~,*~.in stea atop vtPlvee shall be operable and cap11.ble of cl.Jr.Ug in five saco"l<'* or l*** under no-flow conditioa.

. ' 300 3.5.2* Witu -:ha Priury Coolant Syat:aa at a tuqaeratur~:.grr;~t*r *:ban .lal°F, I the require*uta of Si:ecificat1on 3.5. l uy be mdified to ~-.-an&:t.t th*

f olloviDa caa41tiou to exiat. If. th* .*y~;:i,10 ia not ru~ored to meet:

the: ntl'd~**rDca.:of S~ecification 3.S. l vith~.il the time period a~ belov) ref~r to Specification 3.S.3.

~~{~ al. aailiary feedvater pUllf may be inoperable for a period of . _.

,, hou****

b. Tvo au:iliary feadv*ter p".D'.*?"' ~ ....y be placel 111 mauual, for i;eacina, for a period of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

3-38 Aaendllaat No. ~~.-9-e' JH:tae.,. 39, 1986

t.tenwctecl 10/87/86 TSPlQ86-0l47B-Nt.04

3.5 3.5.2 STEAM AND FEEDWATER SYSTEMS (Cont'd)

(Continued)

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

d. The service water makeup to the Auxiliary Feedwacer 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 flov control valve on each train may be inoperable for a period of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months provided the corresponding redundant flow control valve and a pump in the other pip* train are operable .

.300 3.5.3 With the Primary Coolant System at a temperature greater than ~F I and if the system does not satisfy th* requirements of Specification 3.5.l or th* conditions ~f Specification 3.S.2 except as noted in Specification 3.S.4, the reactor shall be placed in hot standby within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . hot shutdown within th* following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in cold shutdown within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3.5.4 With all Auxiliary Feedvatar Pump* inoperable immediately initiate corrective action to ra1tor* at least one Auxiliary Feedvatar Pump ~

to OPEWLE statu* a* soon aa posdble and reduce power vithin 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to th* lowest stable povar level consistent with reliable Main Feedwater System operation. ~

3-38a Amendllen t No . -%--

JaRw 1~* JO, 1996 TSP0885-0268-NL04

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.

3.7.1 Specifications The primary coolant system shall not be heated or ..intained at temperatures above .li'S'°F if the following electrical sy*tems are not operable: 31>0

a. Station power transformer 1-2 (2400 V).

b. Start-up transformer 1-2 (2400 V).

c. 2400 V engineered safeguards buaea lC and lD.

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 bu****

h. Two station batteries and the d-c 1ystems including at least one battery charger on each bua.

i. Both dieael 1euarator1, with a wfnjpJP of 2500 aallona of fuel in each day tank and a ainillua of 16,000 1allon1 of fuel in the underground atorage tank.

j. Svitchyard battery and the d-c ay*tea with one battery charge~.

k. 240 V a-c pow9r panel* No l and 2, and their associated ACB br....r 4i1tribution ayat ....

l. 2..-. ha 11.

3. 7. 2 The requ1r.-nt1 of Specification 3. 7 .1 uy be modified to. th* extent that one of the following conditions will be allowed after the reactor has been made critical. If any of the prov11ion1 of tho** exceptions are violated, the reactor chall be placed in a hot 1hutdovn condition*

within 12 houra. If the violation i1 not corrected within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the reactor 1hall be placed in a cold 1hutdovn condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3-41 TSP0585-0208A-NL04

ELECTRICAL SYSTEMS (Continued)

SHUTDOWN COOLING ELECTRICAL REQUIREMENTS

.300 With' the primary coolant system at ~}2-5°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 lD) )

shall be operable and capable of being supplied by offsite power and an operable diesel generator.

." \

OR )

\

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 safeguards bus (lC or lD) shall be operable and capable of being supplied by off site power while the other engineered safeguards bus (lD or lC) is operable and capable of being supplied by an operable diesel generator.

i i

ACTION

/

With less than the required electrical sources operable:

I I

I A. Immediately initiate action to suspend core alterations, ) ..___,

AND i

i B. Immediately initiate action to suspend movement of irradiated fuel, )

AND \ I I

c. Immediately suspend crane operations over irradiated fuel,

/

I AND D. Suspend operations with a potential for draining the PCS J or fuel pool, I AND

< I Initiate action to restore the required electrical sources to operable status.

j 3-45a Amendment No. _;

TSP0689-0140-NL04

,. .; 3 * .,

I ELECTRICAL SYSTEMS (Continued)---------~-- ~-

I 3.7.3 SHUTDOWN COOLING ELECTRICAL REQUIREMENTS (Continued)

Basia I

'-......_\

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

l. The plant can be maintained in the shutdown or refueling mode for extended time periods, and I

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, that train must still function following the loss of one

. electric supply (offsite 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 I

(off site 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 I

)

f of an activity, such as fuel movement or crane operation, in order to get into a safe and conservative position.

/

\

) \

\

)

'\

I

)

NJ

\

TSP0689-0140-NL04

--------Amendment

i ~.

Table 3. 17. 4 (Cont'd)

Minimum Operable Minimum Degree of

Permissible Bypass No Functional Cnit Channels Redundancy Conditions (m, p, q)

8. Pressurizer Wide 2 None Not reouired in Range Water Level Cold or Refueling Indication . 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 None Not required when Valves (Acoustic Valve PORV isolation valve Monitor or Temperature is closed and its Indication) indication system is operable lL 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~ I JOI:>° (h)

13. Auxiliary Feed Flow 1 per flow None Not required Rate Indication Control be 1 ow .J<;""' F Valve .3()()0 I I

- 14. Auxiliary Feedwater 2 per ste~ 1 Not required Actuation System generator e) below ~F I 0

Sensor Channels JOD

15. Auxiliary Feedwater 2(f) 1 Not required Actuation System below ~F I Actuation Channels 300 l(g)

16. Excore Detector None Not Required Below Deviation Alarms 25% of Rated Power

17. Axial Shape Index 2 (i} 1 Not Required Below Alarm 25% of Rated Power (j, Y ,l ,m)

18. Reactor Vessel 2 None Not Required ~

Water Level Below ~F I 300° 3-8la Amendment No. S1, f8, 9f, 11J, 118, ~

~eptemhe~ 13, 1989 TSP0889-0176-NL04

TABLE 3.24-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY 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 (1) At All Times 37 (RIA 2325)

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 SAn:TY AND DUMP VALVE DISCHARGE LINE

.Joo

a. Gross Gamma Activity Monitor ** 1 per Above ~° 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.t Setpoints for these instruments are governed by Emergency Implementing Procedures or operating procedures.

3-118 Amendment No 8', &T-A.pl'H 29, U85 TS1084-0001-NL02

3.25 ALTE.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~* I Jf, J.I .

APPLICABILITY:

Reactor coolant temperature ~~ 3 o o 0 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and Cold Shutdown within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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

Basis 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 ftre could damage systems normally used to shut down the reactor. Th1*11 capability ie consistent with Regulatory Guide 1.97 and Appendix R to lOCRSO.

3-134 Amendment No.~

TSP1185-0335-NL04 ""' "

1989

Table 4.2.2 (Contd)

Minimum Frequencie!.~r .Equipment Tests

12. Iodine Removal System Th* Iodine Removal System shall be demonstrated op*rabl*:

a. At least one* p*r 31 days by verifying that each valv* (manual, pow*r operated or automatic) in th* flow path that is not locked, sealed or otb*nri.se secured in position, is in its correct position.

b. Ac lea*t one* p*r 6 month* by:

1. Verifying that tank8 T-102 and T-103 contain th* llinimum requir*d volumes.

2. Verifying th* cou~encration of hydrazine in T-102 and sodium hydrozidQ iil T-103.

c. At least one* per refu*ling cycle, during shutdown, by verifying that each automatic valve in th* flow path actuates to its corr*ct position.

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

a. At l*88C one* per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by ch*cking th* valve position indicator in th* control room

b. At l*a*t one* every 6 11Dnth* by p*rforming a l*ak race test between the valv***

y-'

.> 14. Stea Generator Secondary Water Level i

For any steam generator required to meet the shutdown cooling /

requirements of specification 3.1.9, its secondary water level shall be verified at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to be abov* minus 4-lSb TSP0983-0270-NL04

TABLE 4.21. 1 (Continued)

ALTERNATE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Surveillance Channel Descrjptjon

functjon Frequency Surveillance Method

7. Source Range Neutron Monitor a. Test Prior to a. Internal test signal <performed i.lder Table 4.1.3>

(Ml-1/lC) startup1* 1 1

a. Auxl l iary Feedweter LGM Preaaw-e SWi tch

....dJ.-

a. Calibrate Refuel ins Cycle

a. Apply known pressure to pressure sensor (PS*0741D>

9.

10.

SllN Tri Level Indication (Ll-03328)

AuXll lary Feedweter Flow Rate111 Indication

a. Check 1' 1

b. C.l ibrate

a. Calibrate Quarterly Refuel ins Cycle Refuel ins Cycle

a. Coq>are indepeudent level readings

b. Apply known differential pressure to level sensor

a. Apply known differential pressure to sensor(&)

(fl-07278)

(fl-07491)

11. Auxiliary Feedweter Flow Control 111 a. Check Refueling a. Verify Control Valves (CV-0727 & CV*0.749) Cycle

12. Auxiliary Feedweter Puq:> Inlet a. Check Refueling a. Verify Control Ste* Valve CCV-05228) Cycle (1) fCS "f..-p.a-te.Tu'"'-

Quarterly check are not required when th481'1.t is less

<2> Satisfies Table 4.1.3-15 Requirement.

(3) See Specification 4.9b.

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

than~

O\. e.41> 11 .. \

""\""0 3,oooF I

(Next Page is 4-90) 4-88 Amendnent No. ~'.I. JU, -Htr

...fcbrua11 15, 1991

TABLE 4.24;_2 (cont)

CHANNEL HODES IN WHICH CHANNEL SO_URCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED

5. MAIN STEAM SAFETY AND DUMP VALVE DISCHARGE LINE

a. Gross Gamma Activity Monitor

6. ENGINEERED SAFEGUARDS ROOM VENT SYSTEM

a. Noble Gas Activity Monitor (1) 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 syst'em 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 CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous or batch releases are made.

TABLE FREQUENCY NOTATION D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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. U, ~

-May JO, HIS~

TSP0287-0003-NL02

ML18057A890

Text

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