ML20247F541

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Proposed Tech Specs,Deleting Radiological Effluent Tech Specs Requirements
ML20247F541
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 09/11/1989
From:
FLORIDA POWER CORP.
To:
Shared Package
ML20247F535 List:
References
NUDOCS 8909180209
Download: ML20247F541 (77)
v • d • e


Text

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!; ; 4 INDEX

' DEFINITIONS N

.SECTION E8SE l'0-

. DEFINITIONS DEFINED TERMS- 1-1 THERMAL POWER 1-1

-RATED THERMAL POWER 1-1 OPERATIONAL MODE 1-1 ACTION 1-1 OPERABLE - OPERABILITY 1-1 REPORTABLE EVENT 1-2 CONTAINMENT INTEGRITY 1-2 CHANNEL CALIBRATION 1-2 CHANNEL CHECK 1-2 CHANNEL FUNCTIONAL TEST 1-3 CORE ALTERATION 1-3 SHUTDOWN MARGIN 1-3 IDENTIFIED LEAKAGE 1-3 UNIDENTIFIED LEAKAGE 1-4 PRESSURE BOUNDARY LEAKAGE 1-4 CONTROLLED LEAKAGE 1-4 QUADRANT POWER TILT 1-4 DOSE EQUIVALENT I-131 1-4 E - AVERAGE DISINTEGRATION ENERGY 1-4 8909180209 890911

'PDR ADOCK0500g2 CRYSTAL RIVER - UNIT 3 I Amendment No.

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INDEX

' DEFINITIONS" c

SECTION EAGE

.j 1.0' ' DEFINITIONS' DEFINED TERMS ~ 1-1

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'r I . THERMAL POWER 1 RATED THERMAL POWER l-1

< OPERATIONAL MODE 1-1 l: <

ACTION 1-1 OPERABLE - OPERABILITY 1-1

-REPORTABLE EVENT 1-2 l-2

. CONTAINMENT INTEGRITY' CHANNEL CALIBRATION 1-2 CHANNEL CHECK 1-2 CHANNEL FUNCTIONAL TEST 1-3 CORE ALTERATION 1-3 SHUTDOWN MARGIN- 1-3 IDENTIFIED LEAKAGE 1-3 UNIDENTIFIED LEAKAGE 1-4 PRESSURE.B0UNDARY. LEAKAGE 1-4 CONTROLLED LEAKAGE 1-4

. QUADRANT-POWER TILT 1-4 A

DOSE EQUIVALENT.1-131 1-4 E - AVERAGE DISINTEGRATION ENERGY l-4

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8909180209 890911 2 ADOCK 0500 gDR

' CRYSTAL RIVER - UNIT 3 I Amendment No.

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lhD.fl DEFINITIONS' i

SECTION~ Pf_qE 1.0- -DEFINITIONS (Continue <t).

STAGGERED TEST BASIS- 1-5

-FREQUENCY'N0TATION 1-5 AXIAL POWER-IMBALANCE 1-5 REACTOR PROTECTION SYSTEM RESPONSE TIME 1-5 ENGINEERED SAFETY FEATURE RESPONSE TIME 1-6 PHYSICS TESTS 1-6 SOURCE CHECK 1-6 l

PROCESS CONTROL PROGRAM (PCP) 1-6 0FFSITE DOSE CALCULATION MANUAL 1-6 PURGE-PURGING 1-7 VENTING 1-7 INDEPENDENT VERIFICATION 1-7 MEMBER (S) 0F THE PUBLIC 1-8 SITE B0UNDARY 1-8 UNRESTRICTED AREA 'l - 8 OPERATIONAL MODES (TABLE 1.1) 1-9 FREQUENCY NOTATION (TABLE 1.2) 1-10 l

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CRYSTAL RIVER - UNIT 3 la Amendment No.

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i-l' INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS

'SECTION PAGI 3/4.2' POWER DISTRIBUTION LIMITS 9 3/4.2.1 AXIAL 'buER IMBALANCE' 3/4 2-1

'3/4.2.2- NUCLEAR HEAT FLUX HOT CHANNEL FACTOR - Fg 3/4 2-4 3/4.2.3 ' NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - FN H 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 INSTRUMENTATION 3/4 3-1 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 Detectors 3/4 3-26

-Seismic Instrumentation 3/4 3-28 Meteorological Instrumentation 3/4 3-31 Remote Shutdown Instrumentation 3/4 3-34 Post-accident Instrumentation 3/4 3-37 Fire Detection Instrumentation 3/4 3-40 ,

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i CRYSTAL RIVER - UNIT 3 IV Amendment No.

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION EASE L 3/4.7 PLANT SYSTEMS 3/4.7.2 STEAM 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 3/4 _7-16

-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 SYSTEM 3/4 7-20 l 3/4.7.8 AUXILIARY BUILDING VENTILATION EXHAUST SYSTEM 3/4 7-23 1 3/4.7.9 HYDRAULIC SNUBBERS 3/4 7-25 3/4.7.10 SEALED SOURCE CONTAMINATION 3/4 7-35 j 3/4.7.11 FIRE SUPPRESSION SYSTEMS Water System 3/4 7-38 Deluge and Sprinkler Systems 3/4 7-41 Halon System 3/4 7-44 Fire Hose Stations 3/4 7-45 3/4/7.12 PENETRATION FIRE BARRIERS 3/4 7-47 3/4.7.13 RADI0 ACTIVE WASTE SYSTEMS Waste Gas Decay Tanks 3/4 7-4B l

CRYSTAL RIVER - UNIT 3 VII Amendment No.

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IMlEX BASES SECTION EAgf 3/4.7 PLANT SYSTEMS 3/4.7.1- TURBINE CYCLE- B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION 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 l

3/4.7.5 ULTIMATE HEAT SINK B 3/4 7-4 3/4.7.6 FLOOD PROTECTION B 3/4 7-4 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM B 3/4 7-4 3/4.7.8 AUXILIARY BUILDING VENTILATION EXHAUST SYSTEM B 3/4 7-5 3/4.7.9 HYDRAULIC SNUBBERS B 3/4 7-5 3/4.7.10 SEALED SOURCE CONTAMINATION- B 3/4 7-6 3/4.7.11 FIRE SUPPRESSION SYSTEMS B 3/4 7-6 3/4.7.12 PENETRATION FIRE BARRIERS B 3/4. 7.-6 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 DELETED i

CRYSTAL RIVER - UNIT 3 XII Amendment No.

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I, 1 ADMINISTRATIVE CONTROLS

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SECTION- PAGE Meeting Frequency 6-9 Quorum. 6-9 p

Review 1 6 Audits' ;6-10

Authority 6-11' Records 6-11

, 6. 6 - REPORTABLE EVENT'ACTI0ll. 6-11 6.7 ' SAFETY LIMIT VIOLATION 6-12 L8 - PROCEDVRES 12

-6.9 REPORTING RE0VIREMENTS 6.9.1 ROUTINE REPORTS 6-13 f

Startup Reports 6-13

~ Annual Reports 6-14 Monthly Operating Report 6-15

- 6. 9.2 - SPECIAL REPORTS 6-17 6.10 RECORD RETENTION 6-18 6.11 RADIATION PROTECTION PROGRAM 6-19 6.12 HIGH RADIATION AREA 6-19 6.13 ENVIRONMENTAL OVALIFICATION 6-20 6.14' PROCESS CONTROL PROGRAM 6-20 6.15 0FFSITE DOSE CALCULATION MANVAL 6-21 6.16 DELETED i

CRYSTAL. RIVER - UNIT 3 XVI Amendment No.

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l4 DEFINITIONS

' ENGINEERED SAFETY FEATURE RESPONSE TIME iI - 1.25 The' ENGINEERED SAFETY FEATURE RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel .ser.sor until the ESF equipment is capable of performing its safety function:(i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel

- generator starting and sequence loading delays where applicable.

PHYSICS TESTS 1.26 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and 1) described in Chapter 13 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.

SOURCE CHECK 1.27 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

PROCESS CONTROL PROGRAM (PCP) 1.28 The PROCESS CONTROL PROGRAM shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and.71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

1.29 DELETED

- 0FFSITE DOSE CALCULATION MANUAL (0DCM) 1.30 The OFFSITE DOSE CALCULATION MANUAL shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semi-annual Radioactive Effluent Release Reports required by Specifications 6.9.1.5c and 5.9.1.5d.

1.31 DELETED CRYSTAL RIVER - UNIT 3 1-6 Amendment No.

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DEFINITIONS 1.32 DELETED PURGE - PURGING 1.33 - PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other-operating condition, in such a manner that replacement air or gas is required

-to purify the confinement.

VENTING 1.34 VENTING is the controlled process of discharging. air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. . Vent, used in system names, does not imply a VENTING process.

INDEPENDENT VERIFICATION 1.35 INDEPENDENT VERIFICATION is a separate act of confirming or substantiating that an activity or condition has been completed or implemented, in accordance with specified requirements, by an individual not associated with the original determination that the activity or condition was completed or implemented in accordance with specified requirements.

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1 PLANT SYSTEMS DEFINITIONS -

i 3/4.7.13.1 WASTE GAS DECAY TANKS ]

Restricting the quantity of radioactivity contained in each waste gas decay tank provides assurance that in the event of a simultaneous uncontrolled release of all of the tanks' contents, the resulting total body exposure to an individual l at the nearest exclusion area boundary will not exceed 0.5 rem. This is (

consistent with FSAR accident analyses.

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L ADMINISTRATIVE CONTROLS-

~6.7 SAFETY LIMIT VIOLATION 6.7.1- The following actions shall- be taken in the event a Safety Limit is violated:

a. The facility shall be placed in at least HOT STANDBY within one hour.
b. The Safety Limit violation shall be reported to the Commission,.

the Vice President, Nuclear Operations, and to the NGRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PRC. This. report shall describe (1) applicable circumstances preceding _ the violation, (2) effects of the violation upon facility components, systems or structures and (3) corrective action taken to prevent recurrence,
d. The ' Safety . Limit Violation Report shall be submitted to the Commission, the NGRC and the Vice President, Nuclear Operations wi. thin 14 days of the violation.- A separate Licensee Event Report

'need~ not be submitted if the Safety Limit Violation Report meets the. requirements of 10 CFR 50.73 (b) in addition to the requirements above.

6.8 PROCEDURES AND PROGRAMS 6.8.1 SCOPE-Written procedures shall be established, implemented and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November, 1972.
b. Refueling operations.
c. Surveillance and test activities of safety related equipment.
d. Security Plan implementation.
e. Emergency Plan implementation.
f. Fire Protection Plan implementation.
g. Systems' Integrity Program implementation.
h. Iodine Monitoring Program implementation.
i. PROCESS CONTROL PROGRAM implementation.

CRYSTAL RIVER - UNIT 3 6-12 Amendment No.

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.6.8 PROCEDURES AND PROGRAMS (Continued)

I; j. OFFSITE DOSE CALCULATION MANUAL implementation. )

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k. -Quality Assurance Program for effluent and environmental monitoring.

6.8.2 REVIEW PROCESS 6.8.2.1 Each' procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed and approved prior to implementation as - i follows: '{

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a. The Emergency Plan, Security Pl an , Fire Protection Plan and implementing procedures, Administrative Instructions and those test procedures associated with plant modifications that affect nuclear safety shall be reviewed and approved by the PRC and the Director, Nuclear Plant Operations prior to implementation,
b. For all other procedures, the review cycle shall consist of: an intradepartmental review by a Qualified Reviewer, and inter-disciplinary review by Qualified Reviewer (s) in interfacing departments, as specified in administrative procedures, 'and approval by the responsible Superintendent or Manager, as specified by administrative procedures. The PRC shall then review the 10 CFR 50.59 evaluation within 14 days of approval.

6.8.2.2 The training 'and qualification of Qualified Reviewers shall be governed by administrative procedures, with final certification by the Director, Nuclear Plant - 0perations. . Decertification will be required on a periodic basis and upon transfer between departments. As a minimum, all Qualified Reviewers shall meet 'the requirements of ANSI N18.1-1971, Sections 4.2, 4.3, 4.4, or 4.6, or the equivalent.

6.8.2.3 Each procedure and administrative policy of 6.8.1 shall be reviewed on a periodic basis as set forth in administrative procedures.

1 CRYSTAL RIVER - UNIT 3 6-12a Amendment No.

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i ADMINISTRATIVE CONTROLS o 6.8 PROCEDURES AND PROGRAMS (Continued) 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

a. The intent of the original procedure is not altered.
b. The change is approved by two members of the plant ma:iagement staff, at least one of whom holds a Senior Reactor Sperator's License.
c. The change is documented and subsequently reviewed and approved within 14 days of implementation, in accordance with the requirements of Specification 6.8.2 6.8.4 The following programs shall be established, implemented, and maintained:
a. Radioactive Effluent Controls Proaram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the followir,g elements:
1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM,
2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2,
3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM,
4) Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from the unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50,
5) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, 1

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.o e ADMINISTRATIVE CONTROLS 6.8.4a  ; Radioactive Effluent Controls Proaram (Continued)

6) Limitations on the operability and use of the liquid and gaseous - effluent treatment systems to ensure that the appropriate portions of these - systems are used to reduce-

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releases of radioactivity when the projected doses in a 31-day period would exceed.2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50,

7) Limitations on the dose rate resulting from radioactive nnterial released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part.

20, Appendix B, Table II, Column 1,

8) Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from the unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, 9)- Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radio-nuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from the unit to areas beyond the SITE B0UNDARY conforming to Appendix I to 10 CFR Part 50, and
10) Limitations on the annual dose ;c dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources' conforming to 40 CFR Part 190.
b. Radiological Environmental Monitorina Proaram A program shall be provided to monitor the radiation and radio-nuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitocing program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

l 1) Monitoring, sampling, analysis, and reporting of radiation and L radionuclides in the environment in accordance with the l' methodology and parameters in the ODCM, CRYSTAL RIVER - UNIT 3 6-13a Amendment No.

i L_-_____-_-__--_____________-___-___ . - _ _ _ _ _ _ _ _

ADMINISTRATIVE CONTROLS 6.8.4b Radiological Environmental Monitorino Prooram (Continued)

2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and
3) Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

6.9 REPORTING RE0VIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.

STARTUP REPORTS 6.9.1.1 A summary report of plant startup and power escalation testing will be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details requested in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report dres not cover all three events, (i.e., initial criticality, completion of startup test program, and the resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events

, have been completed.

CRYSTAL RIVER - UNIT 3 6-13b Amendment No.

f 1

ADMINISTRATIVE CONTROLS ANNUAL AND SEMIANNUAL REPORTS 6.9.1.4 Annual reports covering tha activities of the unit as described below for the previous calendar. year shall be submitted prior to March I of each year.

The initial report shall be submitted prior to March 1 of the year following initial criticality.

6.9.1.5 Reports required on an annual basis shall include:

a. A tabulation of the number of station, utility, and other personnel (including contractors) receiving . exposures greater than 100 mrem /yr. and their associated man-rem exposure according to work and job functionsl, e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements. Small exposures totaling less than 20 percent of the . individual total dose need not be accounted for. In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.
b. A list of the reactor vessel material surveillance capsules installed in the reactor at the end of the report period and a summary of any withdrawals or insertions of capsules during the report period. In supplying this information, the ownership of each capsule shall be indicated and the irradiation location in the vessel of each capsule which was inserted during the report period shall be identified.
c. Annual Radiological Environmental Operatina Report The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

I IThis tabulation supplements the requirements of 20.407 of 10 CFR Part 20. l CRYSTAL RIVER - UNIT 3 6-14 Amendment No.

co.-

aj ADMINISTRATIVE CONTROLSJ ANNUAL AND SEMIANNUAL REPORTS (Continued)

d. Semiannual Radioactive Effluent Release Report The Semiannual Radioactive Effluent Release Report covering the operation of.the unit during the previous 6 months'of operation shall be submitted within 60 ' days after January 1 and July 1 of each year. The report shall include a summary of the quantities of radioactive liquid ~ and - gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlines in the ODCM and PCP and (2) in conformance .with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

CRYSTAL RIVER - UNIT 3 6-14a Amendment No.

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-DELETED-CRYSTAL RIVER - UNIT 3 6-14b Amendment No.

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' ADMINISTRATIVE CONTROLS i ,

e. ; A list of all challenges to the Pressurizer Power Operated Relief '

Valve'(PORV) and pressurizer safety valves for the' report period.

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,. . CRYSTAL RIVER - UNIT 3 6-14c Amendment No.

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-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 10 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. Inoperable Fire Detection Monitoring Instrumentation, Specification 3.3.3.7.

f.. Specific Activity, Specification 3.4.8.

g. Results of Steam Generator Tube' Inspection. Specification 4.4.5.5.b.
h. Inoperable Fire Suppression System, Specification 3.7.11.1.,

3.7.11.2, 3.7.11.3, and 3.7.11.4.

i. DELETED
j. DELETED
k. DELETED
1. DELETED
m. DELETED
n. DELETED
o. DELETED CRYSTAL RIVER - UNIT 3 6-17 Amendment No.

p .,.

-ADMINISTRATIVE CONTROLS

! ;SPECIAL REPORTS (Continued)'

p. DELETED
q. DELETED.

6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least fine years:

a. Records and logs of facility operation covering time intervals at each power level.
b. Records and logs of principal maintenance activities, inspections, repair. and replacement of principal items of equipment related to nuclear safety.
c. All REPORTABLE: EVENTS submitted to the Commission.
d. Records of surveillance activities, inspections- and calibrations required by these Technical Specifications.
e. Records of reactor tests and experiments.
f. Records of changes made to Operating Procedures.
g. Records of radioactive shipments.
h. Records of sealed source and fission detector leak tests and results.
1. Records of annual physical inventory of all sealed source material of record.

6.10.2 The following records shall be retained for the duration of the Facility Operating License:

a. Records and drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.
b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
c. Records of facility radiation and contamination surveys.
d. Records of radiation exposure for all individuals entering radiation control areas.

CRYSTAL RIVER - UNIT 3 6-18 Amendment No.

_ - _ _ - _ _ _ _ _ _ _ _ . . _ _ _ . _ _ _ _ _ _ _ _ .___-______ _ _-_-- _ m

[ , 6 ADMINISTRATIVE CONTROLS e.. Records of gaseous and liquid radioactive material released to the

' environs.

f. Records of transient or operational cycles for those facility components identified in Table 5.7.-l.
g. Records of training and qualification for current members of the plant staff.
h. Records of inservice inspections performed pursuant to these Technical Specifications.
i. Records of Quality Assurance activities required by the QA Manual.

I

j. Records .of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k. Records .of meetings of the PRC and NGRC.
1. Records for Environmental Qualification which are covered under the provisions of paragraph 6.13.
m. Records of analytical results required by the Operational Radiological Environmental Monitoring Program,
n. Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION ARfA L

6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c) (2) of 10 CFR 20:

a. A High Radiation Area in which the intensity of radiatio, is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a High Radiation Area and entrance thereto shall be controlled by issuance of a Radiation Work Permit'and any individual er group of individuals permitted to enter such areas shall be provided with a radiation monitoring device which continuously indicates the radiation dose rate in the area.

CRYSTAL RIVER - UNIT 3 6-19 Amendment No.

4

Changes to the PCP:

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3n. This documentation shall contain:
1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s),

and L 2) A determination that the change will maintain the overall

, conformance of the solidified waste product to existing 0 requirements of Federal, State, or other applicable regulations.

I b. Shall become effective after review and acceptance by the PRC and l the approval of the Director, Nuclear Plant Operations.

6.15 0FFSITE DOSE CALCULATION MANUAL (0DCM)

Changes to the ODCM:

a. Stall be documented and records of reviews performed shall be retained as required by Specification 6.10.3n. This documentation shall contain:
1) Sufficient information to support the change together with the l appropriate analyses or evaluations justifying the change (s),

! and

2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
b. Shall become effective after review and acceptance by the PRC and the approval of the Director, Nuclear Plant Operations,
c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.

6.16 DELETED CRYSTAL RIVER - UNIT 3 6-21 Amendment No. l

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