ML20247R267

Amend 117 to License DPR-72,providing Addl Requirements for DHR Redundancy

ML20247R267
Person / Time
Site:	Crystal River
Issue date:	05/31/1989
From:	Berkow H Office of Nuclear Reactor Regulation
To:
Shared Package
ML20247R272	List: ML20247R267 ML20247R288
References
NUDOCS 8906070188
Download: ML20247R267 (24)

Text

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UNITED STATES y,

NUCLEAR REGULATORY COMMISSION 7n ij WASHINGTON O. C. 20555

+to FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BU5hhELL CITY OF GKIhE5VILLE Cll) 0F KISSIMMEE CITY OF LEESBURG CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION, CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES C0tE155 ION AND CITY OF ORLANDO SEBklhG UTILITIES COMMISSION SEMINGLE ELECTRIC COOPERATIVE, INC.

LlTY OF TALLAHASSEE DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAP. GEhERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment ho.117 License No. DPR-72 1.

ine Nuclear Regulatory Cou.ission (the Commission) has found that:

A.

The application f or amendment by Florida Power Corporation, et al.

(the licensees) dated February 16, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as an. ended (the Act),

ano the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, ano the rules and regulations of the Commission; C.

There is reasonable assurance (1) that the activities authorized by this amendr.ent can be conducted without endangering the health and safety of the public, enJ (ii) that such activities will be conducted in compliance with the Comission's re5clations; D.

The issrance of this amendment will not be inimical to the coninon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfiec.

8906070188 89053 PDR ADDCK 05000302 P

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2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated-in the attachnient to this license amendnient, and paragraph 2.C.(2) of Facility Operating License No. DPR-72 is hereby amended to read as follows:

lechnical Specifications The Technical. Specifications contained in Ap'pendices A and B, as revised through Amendment ho.117, are hereby incorporated in the license.

Florida Power Corporation shall operate the: facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and ~

shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY C0FNISSION

/

j thb kow erbert N. Berkow, Director roject Directorate 11-2 Division of Reactor Projects-I/II-Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: May 31,1989 9

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ATTACHMENT TO LICENSE AMENDMENT NO.117 FACILITY OPERATING LICENSE NO. DPR-72 DOCKET N0. 50-302 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

Remove Insert IVa IVa VIII VIII IX IX XIII XIII 3/4 4-1 3/4 4-1 3/4 4-2 3/4 4-2 3/4 4-2a 3/4 4-2b 3/4 4-2c 3/4 9-8 3/4 9-8 3/4 9-Ba B3/4 4-1 B3/4 4-1 B3/4 9-2 B3/4 9-2 B3/4 9-3 B3/4 9-3 l-1' 1'

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s LIMmNC CbNDITIONS FOR OPERATION AND SURVEILLANCE D SECTION QGE 3/l.2 FvwER DISTRIBUTION LIMITS 3/4.2.1 AXIAL POWER IMBALANCE 3/4 2-1 3/4.2.2 NUCLEAR HEA't FLUX HOT CHANNEL FACTOR - F Q

3/4 2-4 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACT 3/4 2-6 3/4.2.4 QUADRANT POWER TILT 3/4 2-8 3/4.2.5 DNB PARAMETERS 3/4 2-12 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION3/4 kl 3/4.3.2 ENGINEERED SAFETY FEATURE ACnJATION SYSTEM INSTRUMENTATION 3/4 3-9 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation 3/4 3-22 Incore Detectors 3/4 3-26 Seismic Instrumentation 3/4 3-28 Meteorological Instrumentation 3/4 3-31 Remote Shutdown Instrumentation 3/4 b34 Post-accident Instrumentation 3/4 A37 Fire Detection Instrumentation 3/4 khD Radioactive Liquid Effluent Monitoring Instrumentation 3/4 A42 Radioactive Caseous Effluent Monitoring Instrumentation 3/4 3-47 Waste Gas Decay Tank - Explosive Gas Monitoring Instrumentation 3/4 3 33 CRYSTAL RIVER - UNIT 3 IV Amendment No. JJ, 78,69

INDEX '

LIMITING COMITIONS FCR OPERATION ANr) ettRvgILLA,s

' 3ECTION '

i iO.E.5 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation..............

3/44-1 Hot Standby....................

3/44-2 Hot Shutdown...................

3/4 4-2a 1

Cold Shut down.................. :.

i 3/4 4-2c i

3/4.4.2 RELIEF VALVES - SHUTDOWN............

i 3/44-3

'l 3/4.4.3 RELIEF VALVES - OPERATING............. 3/44-4 Code Safety Valves..................

3/44-4 Power Operated Relief Valve.............

1 3/4 4-4a i

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CRYSTAL RIVER - UNIT 3 IVa AmendmentNo.f!I,II7 l

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6 LIMITING CONDITIONS FOR' OPERATION AND SURVEILLANCE REQUIREMENTS l '

SECTION-PAGE 3/4.9' -

REFUELING OPERATIONS 1:

l 3/4.9.1

' BORON CONCENTRATION................-

3/4 9-1

3/492 INSTRUMENTATION...................-

3/4 9-2

' 3/4.9 3' DECAY TIME. -

3/4 9-3.

3/4.9.4 CONTAINMENT PENETRATIONS....:..........

3/4 9-4 3/4 9.5 COMMUNICATIONS...................

3/4 9-5 3/4.9.6 FUEL HANDLING BRIDGE OPERABILITY...........

'3/4 9-6 3/4 9 7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING..

3/4 9-7 3/4.9.8 DECAY HEAT RD10 VAL AND COOLANT CIRCULATION.....

3/4.9-8

.All Water Levels..................

3/4 9-8

. Low Water Level...................

3/4 9-Ba 3/4.99-

' CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM...-

3/4 9-9 3/4.9.10 WATER LEVEL - REACTOR VESSEL............

3/4 9-10 3/4 9 11 STORAGE POOL....................

3/4 9-11 3/4.9.12 STORAGE POOL VENTILATION..............

3/4 9-12 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS.3/4 10-1

' 3/4.10.2

- PHYSICS TESTS.,.................

3/4 10-2 3/4.10 3 NO FLOW TESTS...................

3/4 10-3 3/4.10.4 SHUTDOWN MARGIN..................

3/4 10-4 1

CRYSTAL RIVER - UNIT 3 VIII Amendment No.III

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• INDEX

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LIMITING CONDITIONS FOR OPERAnit.vt n* tw_p,L.ANCE REO'r :c:;

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. 5ECTION 3/h.11 ELLE RADIOACTIVE EFFLUEivT5 g

Liquid Ef&wnts - Concentration 3/4 11-1 Liquid Effluents - Dose 3/4.'11-3 Gaseous Effluents - Dose Rate 3/4 11-7 i

Dose - Noble Gases I

3/4 11-11 Dose - I-131. Tritium and Radioactive Particulate 3/4 11-12 Total Dose 3/4 11.14 3/h.12 RADIOLOGICAL ENVIRONMENTAL MONITORING Monitoring Program -

3/4 12-l' Land Use Census j

3/4 12-10 Interlaboratory Comparison Program l

3/4 12.

CRYSTAL RIVER - UNIT 3 VIIIa Amendment No. 69

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INDEX_

BASES SECTION-PAGE 3/4.0 APPLICABILITY...................

B 3/4 0 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL..................

B 3/4 1-1 3/4.1.2 BORATION SYSTEMS..................

B 3/4 1-2 3/4.13 MOVABLE CONTROL ASSEMBLIES............

B 3/4 1-3 3/4.2 POWER DISTRIBUTION LIMITS.............

B 3/4 2-1 3/4.3 INSTRUMENTATION 3/4 3 1 REACTOR PDOTECTION SYSTEM INSTRUMENTATION.....

B 3/4 3-1 3/4.3 2 ENGINEERED SAFETY FEATURE ACTUATION SYSTDi INSTRUMENTATION.................

B 3/4 3-1 3/4.3 3 MONITORING INSTRUMENTATION.............

B 3/4 3-2 3/4.4.

REACTOR COOLANT 3 TEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION...

B 3/4 4-1 1

3/4.4.2 AND 3/4. 4. 3 SAFETY VALVES...............

B 3/4 '4-1 3/4. 4. 4 PRESSURIZ ER....................

B 3/4 4-2 3/4.4.5 STEAM GENERATORS....................

B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE...........

B 3/4 4-4 3/4.4.7 CHEMISTRY.....................

B 3/4 4-5 3/4.4.8 SPECIFIC ACTIVITY.... -............

B 3/4 4>5 3/4.4.9 PRESSURE / TEMPERATURE LIMITS............

B 3/4 4-6 3/4.4.10 STRUCTURAL INTEGRITY................

B 3/4 4 13 l

l CRYSTAL RIVER - UNIT 3 IX Amendment No. N

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SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS'(ECCS) 3/4.5.1 CORE FLOODING TANKS..................................

B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS..........................

B 3/4 5-2 l-3/4.5.4-BORATED WATER STORAGE TANK.......................... B 3/4'5-2 i

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?k CRYSTAL RIVER - UNIT 3 X

INDEX BASES-SECTION PAGE 3/4.9.6 FUEL HANDLING BRIDGE OPERABILITY..........

B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING..

B 3/4 9-2 3/4.9.8 DECAY HEAT REMOVAL AND COOLANT CIRCULATION.....

B 3/4 9-2 l

3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM...

B 3/4 9-2 3/4.9.10 WATER LEVEL - REACTOR VESSEL............

B 3/4 9-3 l

3/4.9.11 STORAGE POOL....................

B 3/4 9-3 l

3/4.9.12 STORAGE POOL VENTILATION..............

B 3/4 9-3 3/D.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS B 3/4 10-1 3/4.10.2 PHYSICS TES73...................

B 3/4 10-1 3/4.10.3 NO FLOW TESTS...................

B 3/4 10-1 3/4.10.4 SHUTD0h PJdGIN..................

B 3/4 10-1 i

l CRYSTAL RIVER - UNIT 3 XIII Amendment No. H,117 l

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INDEX 3ASES nCT'C?;

PAGE 3/4.11 RADIOACTIVE EFUTENTS 3/4.11.1.1 L! QUID EFFLUENTS - CONCENTRATION B 3/4 11-1 3/4.11.1.2 LIQUID EFFLUENTS - DOSE B 3/4 11-1 3/4.11.2.1 GASEOUS EFFLUENTS - DOSE RATE B 3/4 11 2 3/4.11.2.2 GASEOUS EFFLUENTS - DOSE, NOBLE GASES B 3/4 11 2 i

3/4.11.2.3 GASEOUS EFFLUENTS - DOSE, I-131, TRITIUM AND l

RADIOACTIVE PARTICULATE l

B 3/4 11 3-3/4.11.3

- TOTAL DOSE B 3/4 - 114 i

l 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM B 3/4 12 1 i

3/4.12.2 LAND USE CENSUS B 3/4 12-1

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3/4.12.3

. INTERLABORATORY COMPARISON PROGRAM B 3/4 12-1 i

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CRYSTAL RIVER - UNIT 3 l

XIIIa Amendment No. 69 i

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- 3/4.4 REACTOR COOLANT SYSTEM COOLkNT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATION LIMITING CONDITION FOR OPERATION 3.4.1.1 Both reactor coolant loops and both reactor coolant pumps in each loop shall be i

an operation.

APPLICABILITY:

MODES I and 2*.

ACTION

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a.

With one reactor l coolant pump not in operation, STARTUP and POWER OPERATION may be ~ initiated and may proceed provided THERMAL POWER is' restricted to less than that allowed by Specification 2.2.1 and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the Nuclear Overpower Trip Setpoint is reduced to the same values.

b.

' The provisions of specification 3.0.4 are not applicable.

l-SURVEILLANCE REQUIREMENTS 4.4.1.1 The Reactor Protection System Instrumentation channels specified in the l

applicable ACTION statement above shall be verified to have had their trip setpoints changed to' the values specified in Table 2.2-1 for the applicable number of reactor l

coolant pumps operating either:

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after switching to a different pump combination if the a.

switch is made while operating, or b.

Prior to reactor criticality if the

'tch is made while shutdown.

4.4.1.2' The above requi. red coc! ant loops shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

• See Special Test Exception 3.10.3.

CRYSTAL RIVER - UNIT 3 3/44-1 Amendment Nos. 77, ll, H,117

REACTOR COOLANT SYSTEM HOT STANDBY LIMITING CONDITION FOR OPERATION 3.4.1.2 a.

The reactor coolant loops listed below shall be OPERABLE:

1.

Reactor Coolant Loop (A) and at least one associated reactor coolant pump.

2.

Reactor Coolant Loop (B) and at least one associated reactor coolant pump.

b.

At least one of the above loops shall be in operation.*

APPLICABILITY:

MODE 3 ACTION With less than the two above required reactor coolant loops OPERABLE, a.

restore the required loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

With no reactor coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and initiate action to return a reactor coolant loop to operation.

The provisions of specifications 3.0.3 and 3.0.4 are not applicable.

c.

SURVEILLANCE REQUIREMENTS 4.4.1.2.1 The above required reactor coolant pumps, if not in operation, shall be determined to be OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availability.

4.4.1.2.2.

At least one cooling loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

'All reactor coolant pumps may be de-energized for up to I hour provided, (1) ne operations are permitted that would cause dilution of the reactor coolant system boron concentration, and(2) core temperature is maintained so as to assure subcooling throughout the reactor coolant primary system.

CRYSTAL RIVER - UNIT 3 3/44-2 Amendment No. 77,117

REACTOR COOLANT SYSTEM HOT SHIJTD0'JN LIMITING CONDITION FOR OPERATION 3.4.1.3 a.

At least two of the loops listed shall be OPERABLE:

1.

Reactor Coolant Loop (A) and at least one associated reactor coolant

Pump, 2.

Reactor Coolant Loop (B) and at least one associated reactor coolant

Pump, 3.

Decay Heat Removal Loop (A),

4.

Decay Heat Removal Loop (B),

b.

At least one of the above loops shall be in operation.**

APPLICABILITY:

MODE 4 ACTION a.

With less than the two above required loops OPERABLE, initiate corrective action to return the required loops to OPERABLE status as soon as possible or be in COLD SHUTDOWN within 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.

b.

With no loop in operation, suspend all operation involving a reduction in boron concentration of the Reactor Coolant System and initiate corrective action to return the required loop to operation.

The provisions of specifications 3.0.3 and 3.0.4 are not applicable.

c.

• • All reactor coolant pumps and decay heat removal pumps may be de-energized for up to I hour provided, (1) no operations are permitted that would cause dilution of the reactor coclant system boron concentration, and (2) core temperature is maintained so as to assure subcooling throughout the reactor coolant primary system.

CRYSTAL RIVER - UNIT 3 3/4 4-2a Amendment No.117

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.1.3.1 The required Reactor Coolant pump (s) and/or Decay Heat Removal pump (s)if not in operatbn, shall be determined to be OPERABLE at least once per. 7 days by '

verifying co: rect breaker alignments and indicated power availability.

6.',.l.3.2 At least one loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

CRYSTAL RIVER - UNIT 3 3/4 4-2b Arendment No.117 I

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REACTOR COOLANT SYSTEM COLD SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.1.4 Two# decay heat removal (DHR) loops shall be OPERABLE

• and at least one DHR loop shall be in operation.**

APPLICABILITY:

MODE 5 ACTION a.

With less than the two above required loops OPERABLE, initiate corrective action to return the required loops to OPERABLE status as soon as possible.

b.

With no DHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and initiate corrective action to return the required DHR loop to operation.

SURVEILLANCE REQUIREMENTS 4.4.1.4 The DHR loop shall be determined to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

1. The filled and intact reactor coolant system with one steam generator operable (per Specification 3.4.5) may be substitued for one decay heat removalloop.

• The normal or emergency power source may be inoperable.

• *The operating decay heat removal pump may be de-energized for up to I hour provided,(1) no operations are permitted that would cause dilution of the reactor coolant system boron concentration, and (2) core temperature is maintained so as to assure subcooling throughout the reactor coolant primary system.

l l-3/4 4-2c Amendment No.117 e________________-

REFUELING' OPERATIONS

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CP.ANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING LIMITING CONDITION FOR OPERATION l

3.9.7 Loads in excess of 2750 pounds, except for movement of the missile shield and pool divider gate as necessary for access to the fuel assemblies, shall be prohibited from travel over fuel assemblies in the storage pool.*

l APPLICABILITY: With fuel assemblies and water in the storage pool.

ACTION:

l With the requirements of the above specification not satisfied, place the crane load in a safe condition. The provisions of Specification 3.0.3 are not applicable.

I SURVEILLANCE REQUIREMENTS 4.9.7.1 Crane interlocks and/or physical stops which prevent crane travel with loads in excess of 2750 pounds over fuel assemblies shall be

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demonstrated OPERABLE within 7 days prior to crane operation and at least once per 7 days during crane operation.

4.9.7.2 Prior to operating tne crane in the cask handling mode, verify that:

a.

No fuel assemblies are in the storage poo'l adjacent to the cask loading area, and b.

The watertight gate between storage pools is in place and sealed.

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• except for the removal of old spent fuel racks and the installation of the high density spent fuel storage racks in the spent fuel storage pool.

The missile shield shall cover the spent fuel in the alternate pool during rack handling.

CRYSTAL RIVER - UNIT 3 3/4 9-7 Amendment No. 36 l

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REFUELING OPERATIONS l

3/4.9.8 DECAY HEAT REMOVAL AND COOLANT RECIRCULATION ALL WATER LEVELS LIMITING CONDITION FOR OPERATION 3 9.8.1 At least one decay heat removal loop shall be in operation.

l APPLICABILITY:

MODE 6.

ACTION:

a.

With less than one decay heat removal loop in operation, except as provided in b. below, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System.

Close all containment penetrations providing direct access from the containment abnosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

b.

7he decay heat removal loop may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of CORE ALTERATIONS to prevent water turbulence problems.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.8.1 A decay heat removal loop shall be de+ ermined to be operating and circulating reactor coolant at a flow rate of y2700 gpm at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

CRYSTAL RIVER - UNIT 3 3/49-8 Amendment No.117 i

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. REFUELING OPERATIONS '

' LOW WATER LEVEL LIMITING CONDITION FOR OPERATION t

3.9.8.2 Two decay heat removal (DHR) loops shall be OPERABLE.

APPLICABILITY: MODE 6 when the water level above the top of the irradiated fuel assemblies seated within the reactor pressure vessel is less than 23 feet.

ACTION a.

With less than the two required DHR loops OPERABLE, initiate corrective action to return the required loops to OPERABLE status.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.8.2 No additional surveillance requirements other than those required by

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Specification 4.0.5.

CRYSTAL RIVER - UNIT 3 3/4 9-Sa Amendment No,117

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3/4.4-REACTOR COOLANT SYSTEM'-

COOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATION

, LIMITING CONDITION FOR OPERATION p

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3.4.1.1 Both reactor coolant loops and both reactor coolant pumps in each loop shall be in operation.

s APPLICABILITY:

MODES 1 and 2*.

g ACTION l

With one reactor coolant pump not in operation,- STAR' TUP and POWER a.

OPERATION may be initiated and may proceed provided THERMAL

~ POWER is restricted to less than that allowed by Specification 2.2.1 and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the Nuclear Overpower Trip Setpoint is reduced to the same values.

b.

The provisions of specification 3.0.4 are not applicable.

I

. SURVEILLANCE REQUIREMENTS 4.4.1,1 The ~ Reactor Protection System Instrumentation ' channels specified in the l

applicable ACTION statement above shall be verified to have had their trip setpoints chmged to the values specified in' Table 2.2-1 for the applicable number of reactor l

coolant pumps operating either a.

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after switching-to a different pump combination if the switch is made while operating, or b.

Prior to reactor criticality if the switch is made while shutdown.

4.4.1.2 The above required coolant loops shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

• See Special Test Exception 3.10.3.

CRYSTAL RIVER - UNIT 3 3/44-1 Amendment Nos. 77, 77, ff,117

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R.EACTOR COOLANT SYSTEM-HOT STANDBY h

LIMITING CONDITION FOR OPERATION -

h 34.1.2 a.

The reactor coolant loops listed below shall be OPERABLE:

1.

. Reactor Coolant Loop (A) and at least one associated reactor coolant pump.

'2.

Reactor Coolant Loop (B) and at least one associated reactor coolant pump.

b.

At least one of the above loops shall be in operation.*

APPLICABILITY:

MODE 3 ACTION With less than-the two above required reactor coolant loops OPERABLE, a.

restore the required loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.

With no reactor coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and initiate action to return a reactor coolant loop to operation, The provisions of specifications 3.0.3 and 3.0.4 are not applicable..

c.

. SURVEILLANCE REQUIREMENTS 4.4.1.2.1 The above required reactor coolant pumps, if not in operation, shall be determined to be OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availability.

4.4.1.2.2. - At least one cooling loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

• All reactor coolant pumps may be de-energized for up to I hour provided, (1) no operations are permitted that would cause dilution of the reactor coolant system boron concentration, and(2) core temperature is maintained so as to assure subcooling throughout the reactor coolant primary system.

L CRYSTAL RIVER - UNIT 3 3/44-2 Amendment No. 77,117

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l bi' 3/4.9 REFUELING OPERATIONS-BASES =

3/4.9.1 BORON CONCENTRATION The limitations on minimum boron concentration ensure that: ~1)the reactor will remain subcriticai-during CORE ALTERATIONS, and 2) a uniform boron concentration is maintained for reactivity control in the water.

volumes having direct access to the reactor vessel. The limitation of a K

of no greater.than 0.95, which includes a conservative. allowance f8 uncertainties, is sufficient to prevent reactor criticality during refueling operations.

3/4.9.2: INSTRUMENTATION The OPERABILITY of source range neutron flux monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.

3/4.9.3 DECAY TIME

.. The minirrum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor pressure vessel ensures that sufficient time has elapsed to allow' the radioactive decay of the short-lived fission products..This decay time is consistent with the assumptions used in the safety analyses.-

3/4.9.4 CONTAINMENT PENETRATIONS The requirements on containment penetration closure and OTRABILITY ensure that a release of radioactive material within containment will be restricted from leakage to the environment. The OPERABILITY and closure requirements are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressuriza-tion potential ~while in the REFUELING MODE.

3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity condition during CORE ALTERATIONS.

CRYSTAL RIVER - UNIT 3 B 3/4 9-1

REFUELING OPERATIONS

-BASES

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l 3/4.9.6 FUEL HANDLING BRIDGE OPERABILITY The OPERABILITY requirements of the hoist bridges used for movment of fuel assemblies ensures that:

1) fuel handling bridges will be used for movment of control rods and fuel assemblies, 2) each hoist has sufficient load capacity to lift a fuel element, and 3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING Re restriction on movement of loads in excess of the Laminal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. B is assumption is consistent with the activity release assumed in the accident analyses.

3/4.9.8 DECAY HEAT REMOVAL AND COOLANT CIRCULATION l

Le requirement that at least one decay heat removal loop be in operation ensures. that (1) sufficient cooling capacity is available to reove decay heat and maintain the water in the reactor pressure vessel below 140 F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effect of a boron dilution incident and prevent boron stratification.

Re requirement to have two DHR loops OPERABLE when there is less than 23 feet of water above the core ensures that a single failure of the operating DHR loop will not result in a complete loss of decay heat removal capability. With the reactor vessel head reoved and 23 feet of water above the core, a large heat sink is available for core ecoling. Bus, in the event of a failure of the operating DHR loop, adequate time is provided to initiate emergency procedures to cool the core.

E4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM Ihe OPERABILITY of this sytem ensures that the contairrnent purge and exhaust penetrations will be automatically isolated upon detection of high radiation levels within the containment. Be OPERABILITY of this system is required to restrict the release of radioactive material kom the containment atmosphere to the env'ronment.

CRYSTAL RIVER - UNIT 3 B 3/4 9-2 Amendment No. H,ll?

REFUELING OPERATIONS BASES 3/4.9.10 WATER LEVEL - REACTOR VESSEL WATER LEVEL Re restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. Le minimm water depth is consistent with the assumptions of the safety analysis.

3/4.9.11 STORAGE POOL Re requirement for missile shields to be installed over the storage pool ensures that the tornado missile protection assumptions are satisfied.

W e restrictions on minim m water level ensure that sufficient water depth is available to remove 99% of the assmed 10% iodine gap activity released from the rupture of an irradiated fuel assembly, he minimum water depth is consistent with the assmptions of the safety analysis.

3/4.9.12 STORAGE POOL VENTILATION Re requirement for the auxiliary building ventilation exhaust system servicing the storage pool area to be OPERABLE ensures that all radioactive material released from an irradiated fuel assembly will be filtered through the IEPA filters and charcoal adsorber prior to discharge to the atmosphere. Be OPERABILITY of this system and the resulting iodine renoval capacity are consistent with the assmptions of the safety analyses.

CRYSTAL RIVER - UNIT 3 B 3/4 9-3 Amendment No.117

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