Text

Proposed Tech Specs,Deleting CVCS Operability Requirements Currenty in LCOs 3.2 3.17.6 & Associated Testing Requirements Currently in SRs 4.2 & 4.17
	ML18066A328
Person / Time
Site:	Palisades
Issue date:	11/09/1998
From:	; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	;
Shared Package
ML18066A326	List: ML18066A325; ML18066A328;
References
	NUDOCS 9811180074
	Download: ML18066A328 (33)
	v • d • e

ATTACHMENT 1 CONSUMERS POWER COMPANY PALISADES PLANT DOCKET 50-255 TECHNICAL SPECIFICATIONS CHANGE REQUEST RELOCATION OF eves REQUIREMENTS Proposed Pages 9 Pages

9811180074 -981109 ___ --

PDR ADOCK 05000255 P PDR

3.1 PRIMARY CO~NT SYSTEM (PCS) 3 .1.9 SHUTDOWN COOLING (Continued)

An exception to the requirement for continuous circulation through the reactor core is provided. Both SDC and PCS circulation may be stopped for up to one hour provided actions are taken to prevent dilution or draining of the PCS and to avoid situations that could produce steam in the reactor vessel.

During periods without forced circulation, admission of water with less Boron concentration than currently in the PCS could collect in a localized pocket and present a potential reactivity addition upon restart of forced circulation. Maintaining the temperature well below boiling ensures that availability of single phase natural circulation. The one hour time limit is not based on analysis. It was chosen to allow testing (such as test closure of containment isolation or shutdown cooling suction valves which require or result in stopping shutdown cooling flow) or minor maintenance, but to restrict the time without mixing and circulation of the PCS.

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

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

In the condition where the reactor vessel head has been removed and the refueling cavity has been filled for refueling, the mass of water in the pool provides a passive means of decay heat removal. When the cavity is filled to

~ 647 1 elevation, this passive heat sink may be relied upon as the means of decay heat removal allowing maintenance.or testing of SDC, Component Cooling, or Service water components.

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

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

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

(Next Page is 3-29) 3-25m Amendment No. t&l-,

3.2 Deleted 3.3 EMERGENCY CORE COOLING SYSTEM Applicability Applies to the operating status of the emergency core cooling system.

Obiective To assure operability of equipment required to remove decay heat from the core in either emergency or normal shutdown situations.

Specifications Safety Injection and Shutdown Cooling Systems 3.3.1 The reactor shall not be made critical, except for low-temperature physics tests, unless all of the following conditions are met:

a. The SIRW tank contains not less than 250,000 gallons of water with a boron concentration of at least 1720 ppm but not more than 2500 ppm at a temperature not less than 40°F.

b. All four Safety Injection tanks are operable and pressurized to at least 200 psig with a tank liquid level of at least 174 inches and a maximum level of 200 inches with a boron concentration of at least 1720 ppm but not more than 2500 ppm.

c. One low-pressure Safety Injection pump is operable on each bus.

d. One high-pressure Safety Injection pump is operable on each bus.

e. Both shutdown heat exchangers and both component cooling heat exchangers are operable.

f. Piping and valves shall be operable to provide two flow paths from the SIRW tank to the primary cooling system.

g. All valves, piping and interlocks associated with the above components and required to function during accident conditions are operable.

h. The Low-Pressure Safety Injection Flow Control Valve CV-3006 shall be opened and disabled (by isolating the air supply) to prevent spurious closure.

i. The Safety Injection bottle motor-operated isolation valves shall be opened with the electric power supply to the valve motor disconnected.

j. The Safety Injection miniflow valves CV-3027 and 3056 shall be opened with HS-3027 and 3056 positions to maintain them open.

3-29 Amendment No. 3-t, T-4, tat, t36, t43-,

3.17 INSTRUMENTATION SYSTEMS Action (continued}

3.17.6.14 Deleted 3.17.6.15 With the Excore Deviation Alarm inoperable:

a) Calculate the QUADRANT POWER TILT using the excore readings at least once each 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

3.17.6.16 With one or two AXIAL SHAPE INDEX Alarm channels inoperable:

a) Restore the system to OPERABLE status prior to the next startup from COLD SHUTDOWN.

3.17.6.17 With one or two SOC suction valve interlock channels inoperable:

a) Place circuit breaker for the associated valve operator in "Racked Out 11 position. The breaker may be racked in only during operation of associated valve.

3.17.6.18 With one Power Dependant Insertion Alarm channel inoperable:

a) Verify that each regulating group is within the limits of Specification 3.10 withi~ 15 minutes after movement of any regulating rod.

3.17.6.19 With one Fuel Pool Area Radiation Monitor inoperable:

a) Stop moving fuel within the Fuel Pool Area until monitoring capability is restored, and b) Restore monitor to OPERABLE status or provide equivalent monitoring capability within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

3.17.6.20 With one Containment refueling Radiation Monitor inoperable:

a) Stop REFUELING OPERATIONS in the containment.

3.17.6.21 If any action required by 3.17.6.1 through 3.17.6.18 is not met AND the associated completion time has expired, or if the number of OPERABLE channels is less than specified in the 11 Minimum OPERABLE Channels":

a) The reactor shall be placed in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and b} The reactor shall be placed in a condition where the affected equipment is not required, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Amendment No. 3-, fr/-, %, 98, -H5, tt8, tct, -:1-2-4, tr9, 35, 3-76

3.17 e

INSTRUMENTATION SYSTEMS Table 3.17.6 (continued)

Instrumentation Operating Reguirements for Other Safety Functions Minimum Required OPERABLE Applicable No Instrument Channels Channels Conditions

10. PORV Block Valve 2/valveCal l/Val ve At all times, unless Position Indication the PCS is depressurized and vented in accordance with Specification 3.1.8.

11. SWS Break Detector 1(a) 0 HOT STANDBY and above.

12. Flux-~T Power Comparator 4Caj 2 POWER OPERATION

13. Rod Group Sequence 2 1 When more than one CROM is Control/Alarm capable of rod withdrawal.

14. Deleted

15. Excore Detector 1 0 Above 25% RATED POWER.

Deviation Alarm

16. AXIAL SHAPE INDEX 2 Above 25% RATED POWER.

Alarm

17. SOC Sucti~n Valve 2 0 Above 200 psia Interlocks PCS Pressure.

18. Power Dependant 2 1 HOT STANDBY and above.

Insertion Alarm

19. Fuel Pool Area 0 When fuel is in Radiation Monitor fuel pool area.

20. Containment Refueling 0 REFUELING OPERATIONS Radiation Monitor when irradiated fuel is in the Containment.

(a) Specifications 3.0.4 and 4.0.4 are not applicable.

(b) Specifications 3.0.3, 3.0.4, and 4.0.4 are not applicable.

Amendment No. 3-, fil-, %, 98, tt5, H-8, ta, tr-4-, -!-2-9, 36, t6r, 3-78

3.17 INSTRUMENTATION SYSTEMS Basis: Table 3.17.6 (continued)

The SPI system - composed of the SPI input module and the Host computer - also uses the signals from the primary rod position indication synchros to monitor the target rods for the correct group position relative to the other groups.

If the group position is not correct relative to the position of the other regulating groups, an Out-of-Sequence alarm is annunciated on the computer system. If a primary rod position indication synchro input card were to lose power, the corresponding reed switch position from the SPI input module would be used in the Out-of-Sequence monitoring on the SPI system. The Out-of-Sequence alarm provides assurance that the operator is aware of abnormal regulating rod positioning.

When only one control rod is capable of being withdrawn, group sequencing and Out-of-Sequence alarm provide no useful function and are not required.

Action 3.17.6.13 - Group Rod Group Sequence Control/Alarm channel inoperable -

When either sequence function is inoperable, one of the methods of assuring correct control rod alignment is not available. Adequate assurance of correct rod positioning is retained by manual verification of regulating rod position after each occurrence of rod motion.

14. Deleted

15. Excore Detector Deviation Alarm - An alarm is derived by the Excore Detector Deviation Alarm channel on excessive flux tilt. The Excore Detector Deviation Alarm compares the combined average power reading of all four Excore Power Range channels to the average from each channel, and alarms if the setpoint is exceeded. One channel being significantly different from the average could indicate a developing Quadrant Power Tilt (Tq).

The Excore Detector Deviation Alarm is required to be OPERABLE above 25% RATED POWER, when the Tq specification is applicable.

Action 3.17.6.15 - Excore Deviation Alarm inoperable - When the Excore Deviation Alarm is inoperable, continuous monitoring of Tq is unavailable.

The function of Tq monitoring must be maintained by manually calculating Tq each 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

B 3.17-32 Amendment No. 1-62-, +1-t,

4.2 EQUIPMENT AND SAMPLING TESTS TABLE 4.2.1 Minimum Frequencies for Sampling Tests FSAR Section Test Frequency REFERENCE

1. Reactor Coolant Gross Activity Deter- 3 Times/7 days with a None Samples mi nation maximum of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months be-tween samples (T ave greater than 500°F).

Gross Gamma by Fission Continuous when T ave is None Product Monitor greater than 500°FOJ.

Isotopic analysis 1/14 days during power None for dose equivalent operation I-131 concentration Radiochemical for 1/6 months czJ None E determination Isotopic analysis a) Once/4 hours, whenever for iodine, including dose equivalent I-131 I-131, 133, 135 exceeds 1.0 µCi/gram, and b) One sample between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months follow-ing a thermal power change exceeding 15%

of rated thermal power within a one hour period.

Chemistry (Cl and 02 ) 3 times/7 days with a maximum of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months between samples (T ave greater than 210°F).

Chemistry (F) Once/30 days and follow-ing modifications or repair to the primary coolant system involving welding.

2. Reactor Coolant Boron Concentration Twice/Week None Boron

3. SIRW Tank Water Boron Concentration Monthly None Sample

4. Deleted

5. SI Tanks Boron Concentration Monthly 6.1.2 Amendment No. B, 74, tt3-, -!6r, 4-9

4.2 EQUIPMENT SAMPLING AND TESTS Table 4.2.2 Minimum Frequencies for Equipment Tests FSAR Section Test Frequency REFERENCE

1. CONTROL RODS Drop Times of All Refueling 7.6.1.3 Full Length Rods

2. CONTROL RODS Partial Movement Every 92 Days 7.6.1.3 of all Rods (Minimum of 6 In)

3. Pressurizer Set Point One Each 4.3.7 Safety Valves Refueling

4. Main Steam Set Point Five Each 4.3.4 Safety Valves Refueling

5. Refueling System Functioning Prior to 9.11.4 Interlocks Refueling Operations

6. Service Water Functioning Refueling 9 .1. 2 System Valve Actuation on SIS and RAS

7. Primary System Evaluate Daily 4.7.1 Leakage

8. Deleted

9. Deleted

10. Safety Injection Verify that level and Each Shi ft Tank Level and pressure indication Pressure is between independent high high/low alarms for level and pressure.

Amendment No. tr, fil, B-3-, +sr, -l-55, t5f, t6r, tae, 4-11

e e 4.17 INSTRUMENTATION SYSTEMS TESTS Table 4.17.6 (continued)

Instrumentation Surveillance Reguirements for Other Safet~ Functions CHANNEL CHANNEL FUNCTIONAL CHANNEL Instrument CHECK TEST CALIBRATION

11. SWS Break Detector NA 18 months 18 months

12. Flux-~T Comparator 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 31 days 18 months

13. Rod Group Sequence NA 18 months 18 months Control/Alarm

14. Deleted

15. Excore Deviation Alarm NA 18 months 18 months

16. ASI Alarm NA 18 months 18 months

17. SDC Suction Interlocks NA 18 months 18 months

18. PDIL Alarm NA 31 days(ctJ 18 months

19. Fuel Pool Rad Monitor 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 31 days 18 months

20. Containment Refueling 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 31 days 18 months Radiation Monitor (d) Setpoint verification only.

Amendment No. t6r, te-4, t-1-t, 4-82

4.17 INSTRUMENTATION SYSTEMS TESTS Basis: Table 4.17.6 CHANNEL CHECK - Other Safety Function indication channels - A CHANNEL CHECK is perfonned each 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months on each required indicator channel, except the Area Radiation Monitors which are checked each 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , to provide a qualitative assurance that the channel is working properly and that its readings are within limits.

The Acoustic valve position monitors have no indicator, therefore, no CHANNEL CHECK is required.

CHANNEL FUNCTIONAL TEST - Other Safety Function Channels - A CHANNEL FUNCTIONAL TEST is perfonned on each channel providing automatic actions to verify that it produces the proper outputs.

This test is required to be performed at least each 18 months. In several cases it is perfonned as part of the required CHANNEL CALIBRATION. Those channels requiring more frequent testing are discussed below.

CHANNEL FUNCTIONAL TEST - Nuclear Flux Monitoring - The CHANNEL FUNCTIONAL TEST of each Wide Range is required prior to each reactor startup. The CHANNEL FUNCTIONAL TEST consists of verifying proper response of the channel to the internal test signals, and verification that a signal is available from the detector. After 1engthy shutdown peri ads flux may be below the range if the channel indication. Signal verification with test equipment is acceptable.

CHANNEL FUNCTIONAL TEST - Rod Position Indication (CRDM Interlocks) - The Shutdown Rod Insertion and Regulating Rod Withdrawal interlock OPERABILITY must be verified within 92 days prior to each reactor startup and prior to startup after each refueling. If these interlocks are inoperable, the associated channel of rod position indication must be declared inoperable.

CHANNEL FUNCTIONAL TEST - Flux-~T Comparator - The alarm function of the Flux-~T Power C9mparator must be verified by a CHANNEL FUNCTIONAL TEST each 31 days.

CHANNEL FUNCTIONAL TEST PDIL Alarm - (Setpoint Verification) - Each 31 days the PDIL setpoints for the*existing plant power level are verified to assure OPERABILITY of the setpoint calculator.

CHANNEL FUNCTIONAL TEST - Fuel Pool and Containment Area Monitor - Each 31 days the Area Monitor OPERABILITY must be verified by a check with an internal test circuit or with a radioactive source.

CHANNEL CALIBRATION - Other Safety Function Indication Channels - Performance of a CHANNEL CALIBRATION every 18 months ensures that the channels are operating accurately and within specified tolerances. The level switch actuated alann channels for the Condensate Flow Switches on the Containment Air Coolers do not require a calibration because their mounting assures that they are at the proper location. The required CHANNEL FUNCTIONAL TEST assures their OPERABILITY. Operating experience has shown this test interval to be satisfactory.

B 4.17-6 Amendment No. t-6-2-,

ATTACHMENT 2 CONSUMERS POWER COMPANY PALISADES PLANT DOCKET 50-255 TECHNICAL SPECIFICATIONS CHANGE REQUEST RELOCATION OF eves REQUIREMENTS Existing Pages Marked to Show Proposed Changes 12 Pages

3.1 PRIMARY COOLANT SYSTEM (PCS) 3.1.9 SHUTDOWN COOLING (Continued)

An exception to the requirement for continuous circulation through the reactor core is provided. Both SOC and PCS circulation may be stopped for up to one hour provided actions are taken to prevent dilution or draining of the PCS and to avoid situations that could produce steam in the reactor vessel.

During periods without forced circulation, admission of water with less Boron concentration than currently in the PCS could collect in a localized pocket and present a potential reactivity addition upon restart of forced circulation. Maintaining the temperature well below boiling ensures that availability of single phase natural circulation. The one hour time limit is not based on analysis. It was chosen to allow testing (such as test closure of containment isolation or shutdown cooling suction valves which require or result in stopping shutdown cooling flow) or minor maintenance, but to restrict the time without mixing and circulation of the PCS.

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

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

In the condition where the reactor vessel head has been removed and the refueling cavity has been filled for refueling, the mass of water in the pool provides a passive means of decay heat removal. When the cavity is filled to

~ 647 elevation, this passive heat sink may be relied upon as the means of 1

decay heat removal allowing maintenance or testing of SOC, Component Cooling, or Service water components.

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

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

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

!~Nix11:::::g:~:9~:::1rn::~:::::::~:t::g1:l::

3-25m Amendment No. t6+

3. 2 Cl IEMICAL AND VOLUME CONTROL SYSTEM Applicability Applies to the operati ORal stat1:1s of the chemical aRd vol 1:1me coRtrol system.

Obiective To defi Re those coRditi ORS of the chemical aRd vol 1:1me coRtrol system Recessary to ass1:1re safe reactor operati OR.

SpecificatioRs 3.2.1 WheR f1:1el is iR the reactor, there shall be at least oRe flow path to the core for boric acid iRjectioR.

3.2.2 The reactor shall Rot be made critical t1Rless all the followiRg CORditiORS are met:

a. At least two chargiRg p1:1mps shall be operable.

b. 0Re coRceRtrated boric acid traRsfer p1:1mp shall be operable.

c. . The two coRceRtrated boric aei d taRks together shall coRtai R a miRim1:1m of 118 iRches of a 6 1/4 perceRt to 10 perceRt by weight boric acid sol1:1tioR at a temperat1:1re of at least 25°F above sat1:1ratioR temperat1:1re for the coRceRtratioR preseRt iR the taRk.

d. System pipiRg aRd valves shall be operable to the exteRt of establi shi Rg two fl ow paths from the coRceRtrated boric acid taRks to the primary cool aRt system aRd a fl ow path from the SIRW taRk to the chargiRg p1:1mps.

e. Both chaRRels of heat traciflg shall be operable for the above flow paths.

3.2.3 D1:1riflg power operatiofl, the req1:1iremef!ts of 3.2.2 may be modified to allow afly of!e of the followiflg cof!ditiofls to be tr1:1e at af!y of!e time. If the system is Rot restored to meet the req1:1iremef!ts of 3.2.2 withifl the time period specified, the reactor shall be placed ifl a hot sh1:1tdowfi coRditiofl withifl 12 ho1:1rs. If the req1:1iremefits 3.2.2 are Rot satisfied withifl af! additioflal 48 ho1:1rs, the reactor shall be placed iR a cold sh1:1tdowfi cof!ditiofl withiR 24 ho1:1rs.

a. 0Re of the operable chargi fig p1:1mps may be remo*9*ed from service provided that two chargiRg pumps are restored to operable stat1:1s withifl 24 ho1:1rs.

b. Of!e coRceRtrated boric acid taRk may be 01:1t of service provided a miRim1:1m of 118 iRches of 6 1/4% to 10% by weight boric acid 3-26

3.2 CHEMICAL AND VOLUME CONTROL SYSTEM (cont'd)

solutioH at a temperature of at least 25°F above saturatioH temperature is coHtaiHed iH the operable taHk aHd provided that the taHk is restored to operable status withiH 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c. OHly oHe Flew path from the coHceHtratee boric acid taHks to the primary cool aHt system may be operable pro*vi dee that either the other flow path from the coHceHtratee boric acid taHks to the primary cool ant system or fl ow path from the SIRW taHk to the chargiHg pumps is restored to operable status withiH 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

e. OHe chaHHel of heat traciHg may be out of service provided it is restored to operable status withiH 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The chemical aHd volume coHtrol system pro~*i des coHtrol of the primary coolant system boron inventopY.ttt This is Hormally accomplished by usiHg aHy oHe of the three chargiHg pumps iH series with oHe of the two boric acid pumps. AH alterHate method of boratioH will be to use the chargiHg pumps directly from the SIRW storage taHk. A third method will be to eepressurize aHd use the safety iHjectioH pumps. There are two sources of borated water available for iHjectioH through three eiffereHt paths.

a. The boric acid traHsfer pumps caH deliver the coHceHtratee boric acid coHteHts (6 1/4 10 perceHt coHceHtratioH of boric acid) to the chargiHg pumps.

b. The safety iHjectioH pumps caH take suctioH from the SIRW taHk (1720 ppm boroH solutioH).

c. The chargiHg pumps caH take their suctioHs by gravity from either the boric acid or the SIRW taHk.

Each coHceHtratee boric acid taHk coHtaiHiHg 118 iHches of 6 1/4 weight perceHt boric acid has sufficieHt boroH to briHg the plaHt to a cold shuteowH coHditioH. Boric acid pumps are each of sufficieHt capacity to feed all three chargiHg pumps at their maximum capacity.

The coHceHtratee boric acid storage taHk is sized for 6 1/4 weight perceHt boric acid solutioH aHd is capable of storiHg solutioH up to 12 weight perceHt. All compoHeHts of the system are capable of mai Htai Hi Hg 12 weight perceHt solutioH.

3-27

3.2 CHEMICAL AND VOLUME CONTROL SYSTEM (cont'd)

Du13l i cate heati fig equi 13meflt is 13rovi ded Ofl all com13ofleflts of He system to maifltaifl the surface tem13erature to at least lS0°F, which is 30°F above the saturatiofl tem13erature of a 10% solutiofl. If the heater elemeflts fail to maifltaifl lS0°F, sufficieflt time is available to eflergize the redufldaflt heater el emeflts before the 25°F limit above saturati Ofl tem13erature is reached.

Also, the 25°F limit 13rovides assuraflce that the 13laflt cafl be shut dowfl before the 13reci13itatiofl tem13erature is reached.

The SIRH taflk coflteflts are sufficieflt to borate the 13rimary coolaflt ifl order to reach cold shutdowfl at afly time duriflg core life. The limits Ofl which com13ofleflts may be iflo13erable afld the time 13eriods for iflo13erability were selected Ofl the basis of the redufldaflcy ifldicated above afld eflgifleeriflg judgmeflt.

Refereflce (1) FSAR, SectiOfl 9.10.

3-28

1

::::::1::::1~~::1,~9 3.3 EMERGENCY CORE COOLING SYSTEM Applicability Applies to the operating status of the emergency core cooling system.

Objective To assure operability of equipment required to remove decay heat from the core in either emergency or normal shutdown situations.

Specifications Safety Iniection and Shutdown Cooling Systems 3.3.1 The reactor shall not be made critical, except for low-temperature physics tests, unless all of the following conditions are met:

a. The SIRW tank contains not less than 250,000 gallons of water with a boron concentration of at least 1720 ppm but not more than 2500 ppm at a temperature not less than 40°F.

b. All four Safety Injection tanks are operable and pressurized to at least 200 psig with a tank liquid level of at least 174 inches and a maximum level of 200 inches with a boron concentration of at least 1720 ppm but not more than 2500 ppm~