ML20127N373

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Amend 147 to License DPR-72,removing Certain Fire Protection Items from CR-3 TS & Modifying License Condition to Establish Change Control Process for Fire Protecion Program
ML20127N373
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 01/22/1993
From: Berkow H
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20127N376 List:
References
NUDOCS 9301290183
Download: ML20127N373 (39)
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Text

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NUCLEAR REGULATORY COMMISSION t

WASHINO TON. D. C. 20M5 l

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[.(Q&lDA_EQVER CORPORATION CITY OF ALAC_tIALA ElLLOLIBlitt!iELL (Uf 0F GAINESVILLE CLILDLK1511MMEE ElTY OLL((11BBS OTY OF NEW SMYRNA MACH AND UTillllES COMMISSION. CITY OF NEW SMYR.![A.3[AG LILY OF OCALA Q_RLANDO UTillTIES COMMISSION AND CITY OF ORLANDO SEMINOLE FLECTRIC COOPERATIVE. INC.

U TY OF TALLAhA1111 QQGEI NO. 50-30]

CRYSTAL RIVER UNIT 3 Wl) CLEAR Gf1 GATING PLANT AM_MQMENT_IQ_f ACILITY,,qEff311NG L1 CENSE Amendment No.147 License No. DPR '/2 1.

The Nuclear Regulatory Cormission (the Commission) has found that:

A.

The application for amendment by Florida Power Corporation, et al.

(the 1;censees) dated February 22, 1991, as supplemented November 6, 1991, May 28, 1992, and December 21, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulatioas set forth in 10 CFR Chapter I; c

8.

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

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

iSe issuance of this amendment will not be inimical to the common 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 satisfied.

2.

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

9301290183 930122 DR ADOCK 0S00 2

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i Ishnical soecifications The Technical Specifications contained in Aspendices A and 8, as revised through Amendment No.147, are here)y incor) orated ?n the Itcense.

Florida Power Corporation shall operate t1e facility in accordance with the Technical Specifications.

In addition, paragraph 2.C.(9) of Facility License No. DPR-72 is amended a

to read as followa:

Fire protection 4

Florida Power Corporation shall implement and maintain in effect all provisions of the approved fire protection program as described in the l

Final Safety Analysis Repnet for the facility and as approved in the Safety Evaluation Report: 94ted July 27, 1979, January 22, 1981, January 6, 1983, July 18, 1985 and March 16, 1988, subject to the j

following prnvisions:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achiave and maintain safe shutdown in the event of a fire.

3.

This license amendment is effective as of its date of issuance and shall i

be implemented within 120 days of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION P

He bert N. Ber ow, Director P oject Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation 4

Attachment:

Changes to the Technical Specifications l

Date of Issuance: January 22, 1993 I

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NUCLEAR REGULATORY COMMISSION

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8, ATTACHMENT T0 LICENSE AMENDMENT NO. 147 FACIllTY OPERATING llCENSE NO. OPR-72 DOCKET NO. 50-302 Replace the following ) ages of the Appendix "A" Technical Specifications with the attached pages.. T1e revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

The corresponding overleaf pages are also provided to maintain document completeness.

-Remove laltrl IV

.IV VII VII' XII XII 3/4.3-35 3/4 3-35 3/4 3-40_

3/4 3-40 3/4 3-41 3/4 3-41 3/4 7-38 3/4 7-38 3/4 7 3/4 7 3/4 7-40 3/4 7-40 3/4 7-41 3/4 7-41 3/4 7-42 3/4 7-42.

3/4 7-43 3/4 7-43 3/4 7-44 3/4 7-44 3/4 7-45 3/4 7-45 3/4 7-46 3/4 7-46 3/4 7-47 3/4 7 47 6-1 6-1 6-la

'6-la 6-5 6-5 6-17 6-17 8 3/4 3-2 8 3/4 3-2 B 3/4'3-3 8 3/4 3-3 B 3/4 7-6 B 3/4 7-6 l,

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BQG LIMITING CONDITIbNS FOR OPERATION AND SURVEILLANCE REQUIREMENTS j

SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.I AXIAL POWER IMBALANCE 3/4 2-1 3/4.2.2 NUCLEAR HEAT FLUX HOT CHANNEL FACTOR -F 3/4 2-4 n

3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR -F" 3/4 2 6 AH i

3/4.2.4 QUADRANT POWER TILT 3/4 2 8 3/4.2.5 DNB PARAMETERS 3/4 2 12 4

3/4.3 INSTRUMENTA113 l

3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION 3/43-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 3/4 3-9 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation 3/4 3-22 Incore Datectors 3/4 3-26 Seismic Instrumentation 3/4328 Meteorological Instrumentation 3/43-31 Remote Shutdown Instrumentation 3/4 3-34 3

Post-sccident Instrumentation 3/4 3-37 i

Wasta Gas Decay Tank - Explosive Gas Monitoring instrumentation 3/4 3-53 Toxic Gas System J

Chloride Detection 3/4 3-55

- Sulfur Dioxide Detection-3/43-56 CRYSTAL RIVER - UNIT 3 IV Amendment No. 13, 35, 65, 17f, 191, 147

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3/4,6 REACTOR COQi. ANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCUL Startup and Power Operation............ATION 3/4 wt Ho t s ta ndby...................

3/4 b 2 Hot Shutdown.............

Cold Shutdown.............

3/6 b2a 3/4.6.2 3/4 b 2c RELEF YALVES. 5HUTDOWN............

3/4.4.3 3/4 b3 RELIEF VALVES. OPERATING.......... 3/4 b4 Code Safety Valves...............

3/4 b4 Power Operated Rollef Yalve.............

3/46-4a i

CRYSTAL R!YER. UNt? 3 IVa Amendment file,g. III l

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IffDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANL.E REQUIREMENTS j

SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.2 STEAN GENERATOR PRESSURE / TEMPERATURE LIMITATION 3/4 7-13 3/4.7.3 CLOSED CYCLE COOLING WATER SYSTEM Nuclear Services Closed Cycle Cooling System 3/4 7-14 Decay Heat Closed Cycle Cooling Water System 3/4 7-15 3/4.7.4 SEA WATER SYSTEM Nuclear Services Sea Water System 3/47-16 Decay Heat Sea Water System 3/4 7-17 3/4.7.5 ULTIMATE HEAT SINK 3/4 7-18 3/4.7.6 FLOOD PROTECTION 3/4 7-19 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SY!. TEM 3/4 7-20 3/4.7.8 AUXILIARY BUILDING VF.NTILATION EXHAUST SYSTEM 3/4 7-23 3/4.7.9 HYORAULIC SNUBGERS 3/4 7 25 3/4.7.10 SEALED SOURCE CONTAMINATION 3/4 7-35 3/4.7.11 DELETED 3/4.7.12 DELETED 3/4.7.13 RADIOACTIVE WASTE SYSTEMS Wasta Gas Decay Tanks 3/4 7-48 Wasto Gas Decay Tank - Explosive Gas Mixture 3/4 7-54 l

l CRYSTAL RIVER - UNIT 3 VII Amendment No. 73, H. H 1, '47 l

~ E933, UMmHG CONDmONS FOR OPERATION AND $1myEn.LA.uC3.'.gc'Jdi.:yft;3 SEC iiON n

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ELECTRIC _AL POWER SYSTEMM 3/4.1.1 A.C. SOURCES Operating 3/4 81 Shutdown J/4 36 3/4.3.2 ONSITE POWER D15TPJBUTION SYSTEMS A.C. Distributlan - Operating 3/4 5-7 A.C. Distribution - 3hutdown 3/4 89 D.C. Natribution - Operating 3/4 bio D.C. Distribution - Shutdown 3/4 S 12 menem

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O CRYSTAL RJYEA - UNIT 3 VUa Amendment fle., 69 I

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3/4.6 CONTAINMENT $Y$7(M$.

3/4.6.1 P R IMAAY C0NTAIMENT................................

8 3/4 6 1 3/4.6.2 DEP RESSURI 2ATION AND COOLING SYSTD6...............

3 3/4 6 3 3/4.6.3 CONTAINMENT ISOLATION VALVE........................,

p 3/4 6-4 3/4.6.4 COM8037!8LE GA$ CONTR0L.............................

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llCRYSTALR!yER. UNIT 3 XI

IMil BASES SECTION

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3.A.6 PLANT SYSIEM c

3/4.7.1 TURBINE CYCLE B 3/4 7 1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LINITATION B 3/4 7-3 3/4.7.3 CLOSED CYCLE COOLING WATER SYSTEM B 3/4 7-3 3/4.7.4 SEA WATER SYSTEM B 3/4 7-3 3/4.7.5 ULTIMATE HEAT SDlK B 3/4 7-4 3/4.7.6 FLOOO PROTECTION B 3/4 7 4 3/4.7.7 CONTROL ROOM ENERGENCY VENTILATIGN SYSTEM B 3/4 7 4 3/4.7.8 AUXILIARY BUILDING VENTILATION EXHAUST SYSTEM B3/47-5 3/4.7.9 HYDRAIJLIC SNUBBERS B 3/4 7 5 3/4.7.10 SEALED SOURCE CONTAMINATION B 3/4 7 6 3/4.7.11 DELETED 3/4.7.12 DELETED 3/4.7.13.1 WASTE GAS DECAY TANKS B 3/4 7-7 3/4.7.13.2 DELETED 3/4.7.13.3 DELETED 3/4.7.13.4 DELETED 3/4.7.13.5 EXPLOSIVE GAS MIXTURE B 3/4 7 8 CRYSTAL RIVER - UNIT 3 XII Amendment No.

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0 ISBLE 3 E c-5 REMGTE SHUTDOWN HONITORING INSTRUMENTATION N

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E READOUT ME/.SUREMENT CHANNELS M

INSTRUMENT LOCATION RANGE OPEDABLE w

1.

Reactor Trip Breaker CRD switchgear room open-close 1 per trip breaker and l

Indication 124 foot elevation I per secondary tria breake j 2.

Reactor Coolant Remote shutdown panel 120-920*F 1 per loop Temperature - Th 3.

Reactor Coolant Pressure Remote shutdown panel 0-2500 psig 1

4.

Pressurizer Level Remote shutdown panel 0-320" HA 1

i' 5.

Steam Generator Pressure Remote shutdown panel 0-1200 psig I per steam generator "w

6.

Steam Generater Level Remote shutdown panel 0-1001 1 per steam generator 7.

Decay Heat Removal Remote shutdown panel 0-300*F 1 per cor,ler Temperature 8.

Motor Driven Emergency Intermediate Building 0-2000 psig I per pump Feedwater Pressure 95 f:st elevation p

9.

Nuclear Services Closed Auxiliary Building 0-300 psig I

g Cycle Cooling Pumps 95 foot elevation y

Discharge Pressure E

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Nuclear Services Closed Auxiliary Butiding 0-250*F 1 per cooler Cycle Cooling Cooler 95 foot elevation Outlet Temperature

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DELETED CRYSTAL RIVER UNIT 3 3/4 3-40 Amendment flo. 79, 90,147 '

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1 CRYSTAL RIVER - UNIT 3 3/4 3 41 Amendment No. 13, 147

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I Pages 3/4 3-42 thru 3/4 3-52 are deleted.-

Next page is 3/4 3-53 i<

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I CRYSTAL RIVER - UNIT 3 3/4 3-42 Amendment No. 88.141. -

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ilAY 4 1992

PLANT SYSTEMS J

SURVEll.l.ANCE REQUIREMENTS (Continued)

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1.

With a half-life grcater than 30 days (excluding Hydragen 3) and 2.

In any form other than gas.

b.

Stored sources not in' use - Each sealed source and fission detectcr shall be tested prior to use o,* transfer to another licensee unless tested within the previous six months. Sealed sources and fission detectors transferred without a certificate i

indicatin2 the last test date shall be tested prior to being Placed into use.

c.

Startup sourtes and fission detectors - Each sealed startup source and fission detector shall be tested within 31 days prior to being subjected to core flux or installed in the core and following repair or maintenance to the source.

4.7.10.1.3 Reports - A report shall be prepared and submitted to the Comission on an annual basis if sealed source or fission detector leakage tests reveal the' presence of 10.005 microcuries of removable contamination.

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CRYSTAL RIVER - UNIT 3 3/4 7 37

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l CRYSTAL RIVER - UNIT 3 3/4 7-38 Amend:aent No. J3, 59.-147

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l CRYSTAL RIVER - UNIT 3 3/4 7-39 Amendment No. 13, 147

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1 CRYSTAL RIVER - UNIT 3 3/4 7 40 Amendment No.13,147

DELETED Amendment No. 73. 90. 147 CRYSTAL RIVER - UNIT 3 3/4 7 4g _

DELETED i

CRYSTAL RIVER - UNIT 3 3/4.7 42 Amendment No. J3. 147 1

DELETED CRYSTAL RIVER - UNIT 3 3/4 7-43 Amendment No, 73,147.

I DELETED CRYSTAL RIVER - UNIT 3 3/4 7-44 Amendment No. J3, H. 147

DELETED 1

CRYSTAL RIVER - UNIT 3 3/4 7-45 Amendment No. 73,147

DELETED l

CRYSTAL RIVER - UNIT 3 3/4 7-46 Amendment No. 13, 147

DELETED i

CRYSTAL RIVER - UNIT 3 3/4 7 47 Amendment No. 13,55,147

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vt.grr sistans.

3/4.7'.13 RADICACTIVE WASTE SYSTEMS t

i WASTE GAS DECAY TANKS i

LIMITING CONDITION FOR OP M TION I

3.7.13.1 The quantity of radioactivity contained in each waste Gas Decay Tank shall be limited to less than or equal to 39000 curies (considered as Xe 133).,

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AFFLICASILITY:

At all times.

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&!2I15E8 With the quantity of radioactivity la any Waste a.

Gas Decay Tank esoeeding the above limit, immediately surM ad all additions of radiometive anterial to that tank,ithin its limit.

and withia 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents-to w t

b.

The provisions of SpeciEThations 3.0.3 and 3.0.4 are not applicable.

SURVII""CE REQUIREMENTS 4.7.13.1 The quantity of radioactive material contained in each Waste Gas Decay Tank shall be determined to be within the limit at least once per 7 days whenever radioactive materials are being added to the tank, and at least once coolant system degassing operations. per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during primary l

CRYSTAZ, RIVER - UNIT 3 3/4 7-48 Amendment No. 69

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6.0 ADNINISTRATIVE CONTROLS i

i 6.1 Resp 0NSIBILITY l

6.1.1 The Director, Nuclear Plant Operations shall be responsible for overall-l facility operation and shall delegate in writing the succession to this j

responsibility during his absence.

6.2 ORGANIZATION

)

j OFFSITE 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS i

Onsite and offsite organizations shall be established for facility operation and i

2 corporate management, respectively.

The onsite and offsite organizations shall i

include the positions for activities affecting the safety of the nuclear power plant.

a.

Lines of authority, responsibility, and cossaunications shall be-established and defined from the highest management levels through

-intermediate levels to and including all operating organization positions.

These relationships shall be documented and updated, as -

i appropriate, in the foru of organization charts, - functional' l

descriptions'of department responsibilities and relationships, and job descriptions for key personnel positions, or-in equivalent forms of 3

i documentation.

These requirements shall-be documented in the Final l

Safety Analysis Report.

l b.

The _ Director, Nuclear Plant Operations shall be rosponsible for overall unit safe operation' and shall have control over those onsite j

activities-necessary for safe operation and maintenance of the plant.

i c.

The -Vice President, Nuclear Operations shall have corporate j

responsibility; for overall. plant nuclear safety and'shall take any i

measures needed to ensure acceptable performance of the staff in i

operating, maintaining, and providing technical support to the plant

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to ensure nuclear. safety.

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d.

The individuals who train the operating staff and those who carry out 1

health physics and quality assurance functions may report to the-i appropriate onsite - manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

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CRYSTAL RIVER - UNIT'3 6-1 Amendment:No. 5,13,26.111,722, g

147:

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s 6.0 ADMINISTRATIVE CONTROLS 6.2.2 FACILITY STAFF Each on duty shift shall be composed of at least the minimum shift a.

crew composition shown in Table 6.2.1.

i b.

At least one licensed Operator shall be in the control room when fuel is In the reactor.

I At least two licensed Operators shall be present in the control room c.

during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.

j d.

An individual qualified in radiation protection procedures shall be on i

site when fuel is in-the reactor.

e.

All CORE ALTERATIONS after the initial fuel loading shall be directly i

supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator limited to Fuel Handling who has no other concurrent responsibilities during this operation.

i

'f.

DELETED g.

The shift supervisors shall hold a senior reactor operator.ltcenst i,

The operators required to have a license shall hold at least a reactor operator license.

4 CEYSTAL RIVER - UNIT 3 6-la Amendment No. 28. IZ2.147 '

ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF OUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N)B.1-1971 for comparable positions, except for the Chemistry and Radiation Protection Superintendent who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and the Operations Technical Advisor, who shall have a Bachelor's degree,.or the equivalent, in a scientific or engineering discipline with specific training in plant design and response and analysis of the plant for transients and accidents.

6._ 4 TRAIL 4!NG 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Vice President, Nuclear Operations and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.

6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW COM41TTEE (PRC)

FUNCTION 6.5.1.1 The Plant Review Committee shall function to advise the Diractor, Nuclear Plant Operations (DNPO) on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The Plant Review Comeittee shall be composed of nine members and one chairman from Huclear Operations Supervisory Personnel responsible for the following areas:

operations, health physics, security, maintenance, modifications, engineering, nuclear safety, and quality. These positions will be designated by the DNPO in Administrative Procedures.

81IERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PRC Chairman to serve on a temporary basis; no more than two alternates shall participate agvetingmembersinPRCactivitiesatanyonetime.

MEETING FREE M Y 6.5.1.4 The Ppt shall meet at least once per calendar month and as convened by the PRC Chairman or his designated alternate.

Amendment No. I,77,U.M,57,777, CRYSTAL RIVER - UNIT 3 6-5 122,147 l

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kYun'~of the Ptc shall consist of the Chairasi oc his 6.5.1.5

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alternate and five seabers including alternates.

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6.5.1.6 The Plant Review Consittee shal?. be responsible for:

Revi6w of 1),aWpMuros and changes thereto as required by' '

a.

Specification 6.4.2, 2) and other proposed proceduree or changes thereto as W by the Directe,r, Nuclear Plant Operations

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to affect nuclear safety.

b.

Review of all proposed tests and esperimente that affect nuclear

safety, e.

Review of all proposed chacten to the Appendia 'A*- Technical Specifics.tions.

d.

Review of all presosed changes or modifications to p'laat r'stess-or equipment that af feet nuclear safety, and changes to radtaste systens which could significantly alter their ability to meet Appendiz 1.

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Invastigation e all -violations of the Technical Specifications e.

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including the review and forwarding of reports covering j

evaluation and reconsendations to prevent recurrence to the vice Prestdant, Hv. clear operations and to the Chairman of the Nuclear General Review Connittee, f.

Review of all REPORTABI.E EVENT 3.

g.

Review of facility operations to detect potential nuclear safety hasards.

h.

Performance of special reviews, in sstigations, or analyses and reports thereon as requested by the ' Chairman of the Nuclear Genaral Review Consistee.

is' Review of the Plant Security Plan and lapleasatlag procedures.

J.

Review of the maargency Plan and implinenting procedures.

i CRYSTAt RIVER - UNIT 3' 8-6 Amendment No. l.25,57.H. i 79,111 iAY 5 1989

ADMINISTRATIVE CONTROLS SpECIAL-REPORTS 6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement,- Region II, within the time period specified for each report. These reports shall be submitted covering the activities identified below. A separate Licensee Event Report, when required by 10 CFR 50.73(a), need not be submitted if the Special Report meets the requirements of 30 CFR 50.73(b) in addition to the requirements of the applicable referenced Specification, a.

ECCS Actuation, Specification 3.5.2 and 3.5.3.

b.

Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

c.

Inoperable Meteorological Monitoring Instrumentation Specification 3.3.3.4.

d.

Seismic event analysis, Specification 4.3.3.3.2.

e.

Deleted.

f.

Specific Activity, Specification 3.4.8.

g.

Results of Steam Generator Tube Inspection. Specification 4.4.5.5.b.

h.

Deleted.

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m.

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n. -Deleted, o.

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CRYSTAL RIVER - UNIT S 6-17 Amendment No. 5, 73, 69, 90, W !

147

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3/4.3 INSTRUMENTADON i

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BASES l

l 3/4.3.1 and 3/4.3.2 REACTOR PROTECTION SYST.M (RPS) AN ENGINEERED SAFETY FEATURES ACTUATlON SY5 TEM (E5FA3) IN5TRt.MENTATI l

1 l-The OPERABILITY of the RPS'and E5FAS instrukentation systems ensure that 1) the i

associated ESFAS action and/or RP5 trip will be tratiated when the~ paramster monitored by each channel or combination thereof exceeds its setpoint,2) the specifled coincidence logic is maintained, 3) sufficient redundancy )la maintained to permit a channel to 4

l cf service for testing or maintenance, and 4 sufficient system functional capability is i

available for RPS and ESFAS purposes from diverse parameters.

i The CPERASILITY of - these sy.i.ms is required-to provide the. overall rellahulty, l

redundance and diversley assumed available In the facility design for the protec.lon and mitigatien of accident and transient conditions. The integrated operation of each of these systems is c:nsistent with the assumptions used in the accident analyses.

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The surveillance requirements specifled fee these systems ensee that the overal system

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tune-icnal capacility is mainta;ned comparable to the'erisinal design standards. The I,

periodic surveiUancs tests. performed' at the minimum frequencies are suff!cient to j

demens: rate mis capability. The E5FAS Functional Unit CHANNEL FUNCTIONAL TESTS l

shan be perf:rmed in accordance with Regulatory Culde 1.22 (Revision 0,1972).

The measurement of response time at the =;Wed frequencies provides assurance cat L

2e RPS and ESFAS action function associated with each channel is esmpleted within the i

time umit assumed la the safety analyses. No credit was taken in'the analyses far those j

channels with reponse times indicated as not applicable.

j Response time may be demonstrated by any series of sequential, overlapping or totM i

enannel test measurements provided that such test demonstrate the total channel i

response time as defined. Sensor response time verification may be demonstrated by either 1) la place, onsite er offsite test measurements or 2) utillaing replacement wwors -

with certified response times.

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CRYSTAL RIVER - UNIT 3 5 3/4 3-1 keendeont No. 66 m

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i 3/4.3 INSTRUMENTATION i

BASES l

3 i

3/4.3.3 MONITORING INSTRUMENTATION i

i 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERA 8ILITY 'of the radiation monitoring channels ensures that 1) the j

radiation -levels are continually measured:in the areas served-by the : individual channels and 2) the alam or automatic action is initiated when the radiation level J

trip setpoint is exceeded, j

The CHANNEL CALIDRATION 'of the Reactor Building High Radiation Monitor is

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j perfomed in 11tg for at least _one_ decade below 10 rad /hr.

In Albt calibration by electronic signal substitution is used for all: range decades above-10 rad /hr.

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l 3/4.3.3.2 INCORE DETECTORS:

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. -The OPERA 8ILITY of tho' incore detectors ensures that the measurements i

obtained from use of this. system accurately represent the spatial neutron flux distribution of the reactor core..See Bases. Figures 3-1 and 3 for examples of acceptable minimum incore detector arrangements, t

3/4.3.3.3 SEISMIC INSTRUMENTATION

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The OPERA 8ILITY of the seismic instrumentation ensures thatisufficient capability is available to promptly determine the. magnitude of a seismic event so A

that the-response of those : features important to-_ safety may be evaluated.

This capability is required to permit comparison of the measured response to that used in the design' basis for-the facility.

This instrumentation is consistent.with the i

recommendations of Safety Guide 12:" Instrumentation fGr Earthquakes", March 1971.

]LULJ.4 -

METEOROLOGICAL INSTRUMENTATION The OPERA 81LITY of the ~ meteorological instrumentation n ensures. that' sufficient meteorological data is available for estimating potential radiation doses to the ~public as a result of routine or. accidental release of radioactive materials to the. atmosphere. This capability is required to evaluate the needs for initiating:

protective measures. to protect the = health.-and safety -of the public.

'This instrumentation xis consistent _ with ' the recommendationstof Regulatory Guide - 1.23:

"Onsite Meteorological Programs", February 1972. -

3/4.3.3.5 RENDTE SHUTDOW INSTRUMENTATION The OPERA 8ILITY. of the remoteTshutdown instrumentation ensures that sufficient capability is available to permit shutdown'and maintenance of HOT STAND 8Y of the facility from_ Tocations outside 'of the control room. 1 This - capability _ is required in the event cetrol room capability.is lost and is consistent with General-Design Criterion 19 of. Appendix 'A".,10-CFR 504

. CRYSTAL RIVER - UNIT-3.

l8 3/4 3-2 1 Amendment No.: JJi.147

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3/4.3 INSTRUMENTATION BASES 3/4.3.3.6 POST-ACCIDENT INSTRUMENTATION The OPERABILITY of the post-accident instrumentation ensures that sufficient information is availtb's on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light-Water Cooled Nu: lear Power Plants to Assess Plant Conditions During and Following an Accident",

December 1975.

3/4.3.3.7 DELETED i

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CRYSTALLRIVER - UNIT 3 B 3/4 3-3 Amendment No. 73,.147 -

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i Bows Figure 31 Incore instrunetation Specificate<m Acceptable Mmimum AX1AL POWER IMSALANCE Arrangement.

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CRYSTAL RIVER - UNIT S B 3/4 3-4 l

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l PLANT SYSTEBS l

j BASES l

314.7.8 AUXILIAAY BUILDiMB VDiffLATION EYMA18W SYST,3 The OPERA 81LITY of the Auxiliary Building ventilation exhaust system I

ensures that sult&ble ambient conditions for personnel and equipment are maintained for all operating periods and that tha effects of post accident conditions in tne Auxiliary Building are mitigated.

Supply and exhaust duct systems are arranged to direct air froe areas of low to higher activity eventually directing it to the main exhaust filter system and from there through the fans to the exhaust

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vent. The main 6xhaust filters include rcughing, HEPA tnd charcoal cells.

3/4.7.9 HYDRAULIC SNUstEas i

The hydraulic snubbers are required OPERABLE to ensure that the structural integrity of the reector coolant system and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads. "he only snubbers excluded from this inspection program are those installed on nonsafety-related systems, and than only if their failurs or failure of the system on which they are inttalled would have no adverse effect on any safety-related system.

The inspection frequency apslicable to snubbers containing seals fabricated frots matsrials witch have been demonstrated compatible with their operating environstont is based upon maintaining a constant level of sncbber protection. Therefore, the required inspection inturval varies invursely with the observed snubber failures.

To provide further assurance of snubber reliabilityl be functional a

l representative sample of the installed snubbers wil tested during plant shutdowns at 18 month intervals. Thase tests will include stroking of the snubbers to verify proper piston l

. movement, lock.up and bleed. Observed fallares of these sample snubbers will require functional testi of additional units. To minimize personnel exposures, seubbers.nstalled in high radiation zones or in esoecially difficult to remove locations may be exempted fras these functional testing requirements provided the OPERASILITY of' these snubbers was demonstrated during functional testing at o' ther the completion of their fabrication or at a subsequent date.

l CRYSTAL RIVER - UNIT 3 8 3/4 7 5 Amendment No. 52,142, MAY 4 1992

PLANT SYSTEMS BASES 3/4.7.10 SEALED SQV M QHIAMINATION The limitations on removable contamination for sources recuiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.

This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.

3/4.7.11 DELETED 3/4.7.12 del.ETED l

CRYSTAL RIVER - UNIT 3 B3/4 7-6 Amendment No. 73, 65, 147

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