ML20126C111
| ML20126C111 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/09/1992 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20126C113 | List: |
| References | |
| NUDOCS 9212220375 | |
| Download: ML20126C111 (43) | |
Text
_ _ _ - _ _ _ - _ _ _ _ - - _ _ _ - - _
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~g EN NUCLEAR REGULATORY COMMISSION n
- j W ASHINGTON, D. C. 20555
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DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE. INC.
DOCKET N0. 50-413 CATAWBA NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSJ, Amendment No.103 License No. NPF-35 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the Duke Power Company, acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc.
(licensees) dated February 7,1990, as supplemented May 7,1990, June 8 and October 8, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.
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 (i) that the activities authorizea 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 set forth in 10 CFR Chapter I; D.
The 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 wM 10 'M Part 51 of the Commission's regulations and all applicabir o p 2ments have been satisfied.
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. 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.0.(2) of Facility Operating License No. NPF-35 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.103, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.
Duke Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance, and shall be implemented 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION t',
David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: December 9,1992
M
'o UNITED STATES 8-~
fi NUCLEAR REGULATORY COMMISSION
- 3 E.
WASHINGTON, D. C. 20555 h*...
DUKE POWER COMPANY
. NORTH CAROLINA MUNICIPAL POWER-AGENCY NO. 1 PIEDM0NT MUNICIPAL POWER AGENCY DOCKET N0. 50-414 CATAWBA NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.-97 License No. NPF-52 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Catawba Nuclear Station,- Unit 2 (the facility) Facility Operating License No. NPF-52 filed by the Duke Power Company, acting for itself, North Carolina Municipal.
- Power Agency No. I and Piedmont Municipal Power Agency (licensees) dated February 7,.1990 as supplemented May 7,-.1990, June 8.and October 8,-1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the-Comission's ' rules and regulations as _ set forth in 10 CFR Chapter -I; 8.
The facility will operate in conformity with the-application, the provisions of the Act, and the_ rules and regulations of the Comission; 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) thatosuch activities will be conducted in compliance with' the Comission's regulations set forth in-10 CFR Chapter I; D.
The issuance,of this amendment will not be inimical. to the comon:
defense and security or to the health and safety of the public; andi 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.
B 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-52 is hereby amended to read as follows:
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 97, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.
Duke Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance, and shall be implemented 30 days from the date of issuance.
FOR T NUCLEAR REGULATORY COMMISSION
/'O David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
December 9, 1992 1
ATTACHMENT TO LICENSE AMENDMENT NO.103_
FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-_4J1 bid 10 LICENSE AMENDMENT N0. 97 FACIllTY OPERATING llCENSE NO. NPF-52 DOCKET NO. 50-414 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified b contain vertical lines indicating the areas of change. y Amendment number and Remove Paaes Insert P.agn II II VI VI XI XI XII XIIIa XII XIllb XV XIII XV XVI XVII XVI XVIII XIX XVII l-3 XVIII 1-3 1-5 1-5 3/4 3-80 thru 3/4 3-84 3/4 3-85 3/4 3-86 3/4 3-80 3/4 3-87 3/4 3-81 3/4 3-88 3/4 3-89 3/4 3-90 3/4 3-82 3/4 3-91 3/4 3-83 3/4 3-92 3/4 3-92a 3/4 3-84 3/4 3-92b 3/4 3-85 3/4 3-93 3/4 3-86 3/4 3-87 3/4 11-1 thru 3/4 11-6 3/4 11-7 3/4 11-1
__ _ _ _ _ - - - - - - ^ ' - -
2
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. Attachment.(continued) i Remove Paaes Insert Paaes 3/4 11-8 thru 3/4 11-15 3/4 11-16 3/4 11-2 3/4 11-17 3/4 11-3 3/4 11-18 3/4 11-19 l
3/4 12-1 thru 3/4 12-15 B 3/4 3-6 B 3/4 3-6 B 3/4 3-7 8 3/4 3-7 B 3/4 11-1 thru 8 3/4 11-9 B 3/4 11-1, 2 B 3/4 12-1 B 3/4 12-2 6-15 6-15 6-15a 6-15b 6-16 6-16 6-17 6-17 6-18 6-19 6-18 6-19a 6-19 6-21 6-21 6-24 6-24 6-25 I
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DEFINITIONS SECTION PAGE 1.33 DELETED......................................................
1-5 l
1.34 SOURCE CHECK.................................................
1-6 1.35 STAGGERED TEST BASIS.........................................
1-6 1.36 THERMAL P0WER................................................
1-6 1.37 TRIP ACT1ATING DEVICE OPERATIONAL TEST.......................
1-6 1.38 UNIDENTIFIED LEAKAGE.........................................
1-6 1.39 UNRESTRICTED AREA............................................
1 1.40 VENTILATION EXHAUST TREA1HENT SYSTEM.........................
1-6 1.41 VENTING......................................................
1-7 1.42 WASTE GAS H0 LOUP SYSTEM......................................
1-7 TABLE 1.1 FREQUENCY N0TATION......................................
1-8 TABLE 1.2 OPERATIONAL M0 DES.......................................
1-9 CATAWBA - UNITS 1 & 2 II Amendment No.103 Unit 1)
Amendment No. 97 Unit 2)'
_ - -. ~. _ _. _. -. - -
i LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION
_P.'4G E TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION............3/4 3-60 TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........................................
3/4 3-61 Remote Shutdown System...................................
3/4 3-62 TABLE 3.3-9 REMOTE SHUTOOWN MONITORING INSTRUMENTATION............3/4 3-63 TABLE 4.3-6 REMOTE SHUTOOWN HONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS....................
3/4 3-64 Accident Monitoring Instrumentation......................
3/4 3-65 TABLE 3.3-10 ACCIDENT HONITORING INSTRUMENTATION.................
3/4 3-66 TABLE 4.3-7 ACCIDENT HONITORING INSTRUMENTATION SURV REQUIREMENTS............................... EI LLANCE 3/4 3-68 Chlorine Detection Systems...............................
3/4 3-70 TABLE 3.3-11 (Deleted)
Loose-Part Detection System..............................
3/4 3-79 i
Explosive Gas Monitoring Instrumentation.................
3/4 3-80 TABLE 3.3-12 EXPLOSIVE GAS MONITORING INSTRUMENTATION.............
3/4 3-81 TABLE 4.3-8 EXPLOSIVE GAS HONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................................
3/4 3-83 Boron Dilution Mitigation System.........................
3/4 3-85 3/4.3.4 TURBINE OVERSPEED PROTECTION..............................
3/4 3-87 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation..............................
3/4 4-1 Hot Standby..............................................
3/4 4-2 Hot Shutdown.............................................
3/4 4-3 Col d Shutdown - Loops F i11 ed.............................
3/4 4-5 Cold Shutdown - Loops Not Fi11ed.........................
3/4 4-6 CATAWBA - UNITS 1 & 2 VI Amendment No.103 (Unit 1)
Amendment No, 97 (Unit-2) 1
J LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9.8 RESIOUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Leve1.........................................
3/4 9-10 Low Water Leve1..........................................
3/4 9-11 3/4.9.9 WATER LEVEL - REACTOR VESSEL.............................
3/4 9-12 3/4.9.10 WATER LEVEL - STORAGE POOL..............................
3/4 9-13 3/4.9.11 FUEL HANDLING VENTILATION EXHAUST SYSTEM.................
3/4 9-14 1/4.10 SPECIAL TESI EXCEPTIONS 3/4.10.1 SHUTDOWN d'.RGIN..........................................
3/4 10-1 3/4.10.2 GROUP HEJJHT, INSERTION, AND POWER DISTRIBUTION l.IMITS...
3/4 10-2 3/4.10.3 PHYSICS TESTS............................................
3/4 10-3 3/4.10.4 RE AC TO R COO LANT L00 PS....................................
3/4 10-4 3/4.10.5 POSITION INDICATION SYSTEM - SHUT 00WN....................
3/4 10-5 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Liquid Holdup Tanks......................................
3/4 11-1 3/4.11.2 GASE0US EFFLUENTS Explosive Gas Mixture....................................
3/4 11-2 Gas Storage Tanks........................................
3/4 11-3 I
CATAWBA - UNITS 1 & 2 XI Amendmedtt No.103 (Unit 1)
Amendment No.
97 (Unit 2) i-
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BASES SECTION PAGE 3/4.0 APPLICABILITY...............................................
B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTR0L..........................................
B 3/4 1-1 3/4.1.2 B0 RATION SYSTEMS..........................................
B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES................................
B 3/4 1-3 3/4.2 POWER DISTRIBUTION LIMITS (Unit 1)..........................
B 3/4 2-1 3/4.2.1 AXIAL FLUX DIFFERENCE (Unit 1)............................
B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Unit 1).................
B 3/4 2-1 3/4.2.4 QUADRANT POWER TILT RATIO (Unit 1)........................
B 3/4 2-3 3/4.2.5 DNB PARAMETERS (Unit 1)...................................
B 3/4 2-3 3/4.2 POWER DISTRIBUTION LIMITS (UNIT 2).......................
B 3/4 2-5 3/4.2.1 AXIAL FLUX DIFFERENCE (Unit 2)............................
B 3/4 2-5 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR, and REACTOR COOLANT SYSTEM FLOW RATE AND NUCLEAR ENTi'ALPY RISE HOT CHANNEL FACTOR (Unit 2)..........................
B 3/4 2-7 3/4.2.4 QUADRANT POWER TILT RATIO (Unit 2)........................
B 3/4 2-9 3/4.2.5 DNBPARAMETERS(Unit 2)...................................
B 3/4 2-10 3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION...............
B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION................................
.B 3/4 3-3 3/4.3.4 TURBINE OVERSPEED PROTECTION..............................
B 3/4 3-7 Amendment No.103 Unit 1 1
CATAWBA - UMITS 1 & 2 XII Amendment No. 97 ((Unit 2 I
BASES SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION.............
B 3/4 4-1 3/4.4.2 SAFETY VALVES.............................................
B 3/4 4-1 3/4.4.3 PRESSURIZER...............................................
B 3/4 4-2
-3/4.4.4 RELIEF VALVES.............................................
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 4-3 3/4.4.7 CHEMISTRY.................................................
B 3/4 4-5 3/4.4.8 SPECIFIC-ACTIVITY.........................................
B 3/4 4-5 3/4.'<.9 PRESSURE / TEMPERATURE LIMITS...............................
B 3/4 4-7 4
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E CATAWBA
. UNITS 1 & 2 XIII Amendment No.103 (Unit 1)
[
Amendment No. 97 (Unit 2)
BASES SECTION PAGE 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1,3/4.8.2 and 3/4.8.3 A.C. SOURCES, D.C. SOURCES ONSITEE0WERDISTRIBUTION.......................,.........
B 3/4 8-1 3/4.8.4 ELECTRICALEQUIPMENTPROTECTIVEDEVICES...................
B 3/4 8-3 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION................,......................
B 3/4 9-1 3/4.9.2 INSTRUMENTATION...........................................
B 3/4 9-1 3/4.9.3 DECAY TIME................................................
B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.........................
B 3/4 9-1 3/4.9.5 COMMUNICATIONS............................................
B 3/4 9-2 3/4.9.6 MANIPULATOR CRANE.........................................
B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE P0OL BUILDING...........
B 3/4 9-2 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION.............
B 3/4 9-2 3/4.9.9 and 3/4.9.10 WATER LEVEL - REACTOR VESSEL and STORAGE P00L..............................................
B 3/4 9-3 3/4.9.11 FUEL HANDLING VENTILATION EXHAUST SYSTEM..................
B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN...........................................
B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS..... B 3/4-10-1 3/4.10.3 PHYSICS TESTS.............................................
B 3/4 10-1 3/4.10.4 REACTOR COOLANT L00PS.....................................
B 3/4 10-1 3/4.10,5 POSITION INDICATION SYSTEM - SHUTD0WN.....................
B 3/4 10-1 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS.........................................
B 3/4 11-l' 3/4.11.2 GASE0US EFFLUENTS........................................
B 3/4 11-2 CATAWBA - UNITS 1 & 2 XV Amendment No.103 (Unit 1)
Amendment No. 97 (Unit 2)
l DESIGN FEATURES SECTION PAGE 5.1 SITE 5.1.1 EXCLUSION AREA..............................................
5-1 5.1.2 LOW PO PU LAT I O N Z 0 N E.........................................
5-1 5.1.3 MAPS DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADI0ACTIVEGASEOUSANDLIQUIDEFFLUENTS...................
5-1 FIGURE 5.1-1 EXCLUSION AREA.......................................
5-2 FIGURE 5.1-2 LOW PO PU LATIO N 20NE..................................
5-3 FIGURE 5.1-3 UNRESTRICTED AREA AND SITE BOUNDARY FOR RADI0 ACTIVE LIQUID EFFLUENTS................................
5-4 FIGURE 5.1-4 UNRESTRICTED AREA AND SITE BOUNDARY FOR RADI0 ACTIVE GASEOUS EFFLUENTS...............................
5-5
- 5. 2 CONTAINHENT 5.2.1 CONFIGURATION...............................................
5-1
- 5. 2. 2 DESIGN PRESSURE AND TEMPERATURE.............................
5-6
- 5. 3 REACTOR CORE 5.3.1 FUEL ASSEMBLIES.............................................
5-6 5.3.2 CONTROL R0D ASSEMBLIES......................................
5-6 5.4 REACTOR COOLANT SYSTEM 5.4.1 DESIGN PRESSURE AND TEMPERATURE.............................
5-6 5.4.2 V0LUME......................................................
5-6 5.5 METEOROLOGICAL TOWER LOCATION.................................
5-6
- 5. 6 FUEL STORAGE 5.6.1 CRITICALITY.................................................
5-7 5.6.2 DRAINAGE....................................................
5-7 5.6.3 CAPACITY....................................................
5-7
5-7 TABLE'5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS..................
5-8 CATAWBA UNITS 1 & 2 XVI Amendmenc No,103 Unit 1 -
Amendment No. 97 Unit 2
ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY..............................................
6-1 6.2 ORGANIZATION....................................
6-1 6.2.1 0FFSITE and ONSITE ORGANIZATIONS.........................
6-1 6.2.2 UNIT STAFF................................................
6-1 FIGURE 6.2-1 DELETED............................................
6-3 FIGURE 6.2-2 0ELETED............................................
6-4 TABLE 6.2-1 MINIPUM SHIFT CPEW COMPOSITION......................
6-5 6.2.3 CATAWBA SAFETY REVIEW GR0VP...............................
6-6 Function..................................................
6-6 Composition...............................................
6-6 Responsibilities..........................................
6-6 Records...................................................
6-6 6.2.4 SHIFT TECHNICAL ADVIS0R...................................
6-6 6.3 UNIT STAFF QUALIFICATIONS...................................
6-6 6.4 TRAINING....................................................
6-6 6.5 REVIEW AND AUDIT............................................
6-7 6.5.1 TECHNICAL REVIEW AND CONTROL ACTIVITIES...................
6-7 6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB)........................
6-8 Function..................................................
6 Organization..............................................
6-9 Review....................................................
6-10 Audits....................................................
6-10 Records...................................................
6-11 6.6 REPORTABLE EVENT ACTI0N.....................................
6-12 6.7 S AFETY LIMIT VIO LATION......................................
6-12 6.8 PROCEDURES AND PR0 GRAMS.....................................
6-13 6.9 REPORTING REQUIREMENTS......................................
6-15b 6.9.1 ROUTINE REP 0RTS...........................................
6-15b Startup Report............................................
6-15b CATAWBA - UNITS 1 & 2 XVII Amendment No.103 (Unit 1) l Amendment No. 97 (Unit 2)
4 ADMINISTRATIVE CONTROLS SECTION PAGE Annual Reports............................................-
6-16 Annual Radiological Environmental Operating Report........
6-16 Semiannual Radioactive Effluent Release Report............
6-17 Honthly Operating Reports.................................
6-18 Core Operating Limits Report..............................
6-18 i
6.9.2 SPECIAL REP 0RTS...........................................
6-20 6.10 RECORD RETENTION...........................................
6-20 G.11 RADIATION PROTECTION PR0 GRAM...............................
6-21 6.12 HIGH RADIATION AREA........................................
6-21 6.13 PROCESS CONTROL PROGRAM (PCP)..............................
6-22 6.14 0FFSITE DOSE CALCULA~.' ION MANUAL (0DCH).....................
6-23 6.15 MAJOR CHANGES TO LIQUIO, GASEOUS, AND SOLIO RA0 WASTE TREATHENT SYSTEM5..........................................
6-23 6.16 SECTION 16.11 (RADIOLOGICAL EFFLUENT CONTROLS) 0F THE F5AR................................................
6-24
- 7. 0 SPECIAL TEST PR0 GRAM........................................
7-1 l
i Amendment No.103 Unit 1) l Amendment No. 97((Unit 2)
CATAWBA - UNITS 1 & 2 XVIII l
I
DEFINITIONS ENGINEERED SAFETY FEATURES RESPONSE TIME 1.13 TheENGINEEREDSAFETYFEATURES(ESF)RESPONSETIMEshallbethattime interval from when the monitored parameter exceeds its ESF Actuation Setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions pump dischargepressuresreachtheirrequiredvalues,etc.).TimesshallInclude diesel generator starting and sequence loading delays where applicable.
FREQUENCY NOTATION 1.14 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.
IDENTIFIED LEAKAGE 1.15 IDENTIFIED LEAKAGE shall be:
a.
Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that art capturad and conducted to a sump e
or collecting tank, or b.
Leakage into the containment d mos)here from sources that are both specifically located and kr. awn eitler not to interfere with the opera-tion of Leakage Detection Systems or not to be PRESSURE B0UNDARY LEAKAGE, or c.
Reactor Coolant System leakage through a steam generator to the Secondary Coolant System.
MASTER RELAY TEST 1.16 A MASTER RELAY TEST shall be the energization of each master relay and--
verification of OPERABILITY of each relay.
The MASTER RELAY TEST shall include a continuity check of each associated slave relay.
NEMBER(S) 0F THE PUBLIC 1.17 MEMBER (S) 0F THE PUBLIC shall include all. persons who are not occupa-tionally associated with the plant.
This category does not include employees of the licensee, its contractors, or vendors.
Also excluded from this cate are persons who enter the site to service equipment or to make deliveries, gory This category does include persons who use portions of the site for recre-i ational, occupational, or other purposes not associated with the plant.
OFFSITE DOSE CALCULATION MANUAL 1.18 The OFFSITE DOSE CALCULATION MANUAL (00CM) shall contain the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents - in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environ-mental Radiological Monitoring Program.
The Radioactive Effluent' Controls and-l Radiological Environmental Monitoring Programs required by Section 6.8.4 and l
descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semi-annual Radioactive Effluent Release Reports required by Specifications 6.9.1.6 and 6.9.1.7 shall' be contained in Chapter 16.of the Final Safety Analysis Report.
1 E
CATAWBA - UNITS 1 & 2 1-3 Amendment No.103 Unit 1 Amendment. No. 97 Unit 2 m
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DEFINITIONS RATED THERMAL POWER 1.26 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3411 MWt.
REACTOR BUILDING INTEGRITY 1.27 REACTOR BUILDING INTEGRITY shall exist when:
a.
Each door in each access opening is closed except when the access opening is being used for normal transit entry and exit, then at least one door shall be closed, b.
The Annulus Ventilation System is OPERABLE, and c.
The sealing mechanism associated with each penetration (e.g., welds, bellows, or 0 rings) is OPERABLE.
REACTOR TRIP SYSTEM RESPONSE TIME 1.28 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its Trip Setpoint at the channel sensor until loss of stationary gripper coil voltage.
REPORTABLE EVENT 1.29 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR Part 50.
SHDT00WN MARGIN I
1.30 SHUIDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all full-length rod cluster assemblies (shutdown and control) are fully-inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.
SITE BOUNDARY 1.31 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by licensee.
SLAVE RELAY TEST 1.32 A SLAVE RELAY TEST shall be the energization of each slave relay and-
-verification of OPERABILITY cf mh relay.
The SLAVE RELAY TEST shall include a continuity check, as a minimuh, of associated testable actuation devices.
1.33 Deleted l
CATAWBA - UNITS 1 & 2 1-5 Amendment No.103 Unit l}
Amendment No. 97 Unit 2,
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INSTRUMENTATION EXPLOSIVE GAS MONITORING INSTRUMENTATION l
LIMITING CONDITION FOR OPERATION 3.3.3.10 The explosive gas monito-ing instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specification 3.11.2.5 are not exceeded.
APPLICABILITY:
As Shown in Table 3.3-12.
l ACTION:
a.
With an explosive gas monitoring instrumentation channel Alarm / Trip setpoint less conservative than required by the above specification, declare the channel inoperable and take the ACTION shown in Table 3.3-12.
b.
With less than the minimum number of explosive gas monitoring intrumentation channels operable, take the ACTION shown in Table 3.3-12.
Restore the inoperable instrumentation to OPERABLE status within 30 days, or if unsuccessful, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 to explain why this inoperability was not corrected within the time specified.
c.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.10 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION, and ANNALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 4.3-8.
l-4 CATAWBA - UNIT 1 & 2 3/4 3-80 Amendment No.103 (Unit 1) l Amendment No. 977(Unit 2).
s
TABLE 3.3-12 c34 gj EXPLOSIVE GAS MONITORING INSTRUMENTATION j.
MINIMUM CHANNELS 25 INSTRUMENT OPERABLE APPLICABILITY ACTION w
[
WASTE GAS HOLDUP SYSTEM Explosive Gas Monitoring Sy> tem to a.
Hydrogen Monitors 1/ train per station 46 b.
Oxygen Monitors 2/ train per station 45 R
e q>
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i
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$8 5E 55.
pp g *During WASTE GAS HOLDUP' SYSTEM operation 4
TABLE 3.3-12 (Continued)
TABLE NOTATIONS-ACTION STATEMENTS ACTION 45 -
With the number of channels OPERABLE one less than required l
~,
by the Minimum Channels-0PERABLE requirement, operation of this system may continue provided grab samples are taken and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
With both channels inoperable, operation may continue provided grab samples are taken and analyzed at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1
during other operations.
l ACTION 46 -
With the number of' channels OPERABLE one less than required i
by the Minimum Channels OPERABLE requirement, suspend r
oxygen supply to the recombiner, t
l l
l I
CATAWBA - UNITS 1 & 2 3/4 3-82 Amendment No.103 (UNIT 1)
Amendment No. 97 (UNIT 2) i--.
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- P TABLE 4.3-8 nDg EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 7
ANALOG CHANNEL MODES FOR 'wHICH c5 CHANNEL CHANNEL OPERATIONAL SURVEILLANCE g INSTRUMENT CHECK CALIBRATION TEST IS REQUIRED j
[
WASTE GAS HOLDUP SYSTEM Explosive Gas Monitoring System y
- a. Hydrogen Monitors D
Q(1)
M
- b. Oxygen Monitors ~
D Q(2)
M Y.
1 8
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' II aa FF QZ M
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1ABLE 4.3-8 (Continued) l TABLE NOTATIONS During WASTE GAS HOLDUP SYSTEM operation.
]
I (1)
The CHANNEL CALIBRATION shall include the use of standard gas samples in I
accordance with the manufacturer's recommendations.
In addition, a 1
standard gas sam)le of nominal four volume percent hydrogen, balance nitrogen, shall oe used in the calibration to check linearity of the hydrogen analyzer.
i (2) The CHANNEL CALIBRATION shail include the use for standard gas samples in j
accordance with the manufacturer's recommendations.
In addition, a standt.rd gas sample of nominal four percent oxygen, balance nitrogen, shall be used in the calibratic. to check linearity of the oxygen analyzer.
CATAWBA - UNITS 1 & 2 3/4 3-84 Amendment No.10 Unit 1 l
Amendment No. 9 Unit 2 E
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INSTRUMENTATION BORON DILUTION MITIGATION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.3.11 As a minimum, two trains of the Boron Dilution Hitigation System j
shall be OPERABLE and operating with Shutdown Margin Alarm ratios set at less than or equal to 4 times the steady-state count rate.
APPLICABILITY:
MODES 3, 4, AND 5 ACTION:
(a) With one train of the Boron Dilution Mitigation System inoperable or not operating 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or, restore the inoperable train to OPERABLE status within (1) suspend all operations involving positive reactivity changes and verify that valve NV-230 is closed and secured within the next hour, or (2) verify two Source Range Neutron Flux Monitors are OPERABLE with Alarm Setpoints less than or equal to one-half decade (square root of 10) above the steady-state count rate and verify that the combined flowrate from both Reactor Makeup Water Pumps is less than or equal to 150 gpm (Mode 3 or 4) or 75 gpm (Mode 5) within the next hour.
(b) With both trains of the Boron Dilution Mitigation System inoperable or not operating, restore the inoperable trains to OPERABLE status within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or (1) suspend all operations involvir:g positive reactivity changes and verify that valve NV-230 is closed and secured within the next hour, or (2) verify two Source Range Neutron Flux Monitors are OPERABLE with AlarmSetpointslessthanorequaltoone-halfdecade(square-root of 10) above the steady-state count rate and verify that the corbined flow rate from both Reactor Makeup Water Pumps is less than or equal to 150 gpm (Mode 3 or 4) or 75 gpm (Mode 5) within the next hour, SURVEI! LANCE REQUIREMENTS 4
4.3.3.11.1 Each train of the Boron Dilution Mitigation System shall be demon-l strated OPERABLE by performance of:
(a) A CHANNEL CHECX at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, CATAWBA - UNITS 1 & 2 3/4 3-85 Amendment No.10 Unit 1 l
Amendment No. 9 Unit 2
INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Continued)
(b) An ANALOG CHANNEL OPERATIONAL TEST at least once per 31 days, and (c) At least once per 18 months the 80MS shall be demonstrated OPERABLE by:
(1) Verifying that each automatic valve actuated by the BDMS moves to its correct position upon receipt of a trip signal, and (2) Verifying each reactor makeup water pump stops, as designed, upon receipt of a trip signal.
4.3.3.11.2 If using the Source Range Neutron Flux Monitors to meet the require-ments of Technical Specification 3.3.3.11, (a) The monthly surveillance requirements of Table 4.3-1 for the Source Range Neutron Flux Monitors shall include verification that the Alarm Setpoint is less than or equal to one-half decade (square root of 10) above the steady-state count rate.
(b) The combined flow rate f rom both Reactor Makeup Water Pumps shall be verified as less than or cqual to 150 gpm (Mode 3 or 4) or 75 gpm (Mode 5) at least once per 31 days.
l l
CATAWBA - UNITS 1 & 2 3/4 3-86 Amendment No.103 (UNIT 1)
Amendment No. 97 (UNIT-2)
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INSTRUMENTATION 3/4.3.4 TURBINE OVERSPEED PROTECTION LIMITING CONDITION FOR OPERATION 3.3.4 At least one Turbine Overspeed Protection System shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3.
ACTION:
a.
With one stop valve or one control valve per high pressure turbine steam line inoperable and/or with one intermediate stop valve or one intercept valve per low pressure turbine steam line inoperable, restore the inoperable valve (s) 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 close at least one valve in the affected steam line(s) or isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
With the above required Turbine Overspeed Protection System otherwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> isolate the turbine from the steam supply.
SURVEILLANCE REQUIREMENTS 4.3.4.1 The provisions of Specification 4.0.4 are not applicable.
4.3.4.2 The above required Turbine Overspeed Protection System shall be demonstrated OPERABLE:
a.
At least once per 7 days while in MODE 1 and while in MODE 2 with the turbine operating, by cycling each of the following valves through at least one complete cycle from the running position:
1)
Four high pressure turbine stop valves, 2)
Six low pressure turbine intermediate-stop valves, and 3)
Six low pressure turbine intercept valves, b.
At least once per 31 days while in MODE 1 and while in MODE 2 with the turbine operating, by direct observation of the movement of each of the above valves and the four high pressure turbine control valves, through one complete cycle from the running-position, c.
At least once per 18 months by performance of a CHANNEL CALIBRATION on the Turbine Overspeed Protection Systems,* and d.
At least once per 40 months by disassembling at'least one of each of the above valves (including the four high pressure turbine control valves) and performing a visual and surface inspection of valve seats, disks and stems and verifying no unt ceptable flaws or corrosion.
"This surveillance need not be performed until prior to entering HOT STANDBY following the Unit I first refueling.
(This applies to Unit 1 only.)
CATAWBA - UNITS 1 & 2 3/4 3-87 Amendment No.10 Unit 1 Amendment No. 9 Unit 2
o RADIDACTIVE EFFLULNTS 3/4.11.1 LIQUID EFFLUENTS LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.1 The quantity of radioactive material contained in each temporary l
unprotected outdoor tank shall be limited to less than or equal to 10 Curies, excluding tritium and dissolved or entrained noble gases.
APPLICABILITY:
At all times.
ACTION:
a.
With the quantity of radioactive material in any of the above tanks exceeding the above limit, immediately suspend all additions of.
radioactive material to the tank, within 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 within the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.7.
b.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.1 The quantity of radioactive material contained in each of the above tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.
i l
3/4-11-1 Amendment No.103 (Unit 1)
. l 1
CATAWBA - UNITS 1 & 2 Amendment No. 97 (Unit 2) i L
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RADIOACTIVE EFFLUENTS i
3/4.11.2 GASEOUS EFFLUENTS l
EXPLOSIVE GAS MIXTURE I
LIMITING CONDITION FOR OPERATION 3.11.2.1 The concentration of oxygen in the WASTE GAS HOLDUP SYSTEM shall be l
limited to less than or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume.
APPLICABILITY:
At all times.
ACTION:
a.
With the concentration of oxygen in the WASTE GAS HOLOUP SYSTEM greater than 2% by volume but less than or equal to 4% by volume, reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, b.
With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM greater than 4% by volume and the hydrogen concentration greater than 4% by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 4% by volume; then take ACTION a. above, c.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.1 The concentrations of hydrogen and oxygen in the WASTE GAS HOLOUP l
SYSTEM shall be determined to be within the above limits by continuously monitoring the waste gases in the' WASTE GAS HOLDUP SYSTEM with the hydrogen and oxygen monitors required OPERABLE by Table 3.3-12 of Specification 3.3.3.10.
l
- CATAWBA - UNITS 1 & 2 3/4 11-2 Amendment No.103 (Unit 1) l Amendment No.- 97 (Unit 2)
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RADI0 ACTIVE EFFLUENTS CASE 005 EFFLUENTS l
GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.2 The quantity of radioactivity contained in each gas storage tank l
shall be limited to less than or equal to 97,000 Curies of noble gases (con-sidered as Xe-133 equivalent).
APPLICABILITY:
At all times.
ACTION:
With the quantity of radioactive material in any gas storage tank a.
exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 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 within the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.7.
b.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.2 The quantity of radioactive material contained in each gas storage l
tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tank.
CATAWBA - UNITS 1 & 2 3/4 11-3 Amendment No.103(Unit 1) l Amendment No. 97(Unit _2)'
1
..-_--____ _ ____ a
l INSTRUMENTATION BASES s
3/4.3.3.9 LOOSE-PART DETECTION SYSTEM The OPERABAILITY of the loose part detection instrumentation ensures that sufficient capability is available to detect loose metallic parts in the.
Reactor System and avoid or mitigate damage to Reactor System components.
The allowable out of-service times and surveillance requirements are consictent with the recommendations of Regulatory Guide 1.133, " Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors," May 1981.
3/4.3.3.10 EXPLOSIVE GAS MONITORING INSTRUMENTATION The explosive gas instrumentation is provided for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the WASTE GAS HOLDUP SYSTEM.
CATAWBA - UNITS 1 & 2 B 3/4 3-6.
Amendment No.03(Unit 1)
Amendment No.97 (Unit 2)
l INSTRUMENTATION BASES 3/4.3.3.11 BORON DILUTION MITIGATION SYSTEM l
The operability of the Boron Dilution Hitigation System ensures that pro-tection against a loss of shutdown margin f rom a boron dilution event is pre-sent.
This system uses two source range detectors to monitor the subcritical multiplication of the reactor core.
An alarm setpoint is continually calcu-lated as 4 times the lowest measured count rate, including compensation for background and the statistical variation in the count rate.
Once the alarm setpoint is exceeded, each train of the Boron Dilution Hitigation System will automatically shut off both Reactor Makeup Water Pumps, isolate flow to the charging pumps from the Volume Control Tank, and align the suction of the charging pumps to highly borated water from the RWST.
These actions automa-tically isolate the potential sources of diluted water and allow injection of highly borated water into the Reactor Coolant System.
In the event that the Boron Dilution Mitigation System is inoperable or not operating, the Source Range Neutron Flux Monitors may be used to provide protection against a loss of shutdown margin from a boron dilution event.
If the Source Range Neutron Flux Monitors are used to monitor the subcritical multiplication of the reactor core, the alarm setpoint must be calibrated and periodically checked to ensure that it is less than or equal to one-half decade above the steady-state count rate.
In eddition, the flow from the Reactor Make-up Water Pumps must be verified as below specified limits.
These actions ensure that adequate time is available for the operator to recognize and terminate a dilution event prior to a loss of shutdown margin, 3/4.3.4 TURBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed.
Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety-related components, equipment, or structures.
CATAWBA - UNITS 1 & 2 B 3/4 3-7 Amendment No.iO3(Unit 1)
Amendment No. 97(Unit 2)
3/4.11 RADIOACTIVE EFFLUENTS g
BASES 3/4.11.1 LIQUID EFFLUENTS I
3/4.11.1.1 LIQUID HOLDUP TANKS l
The tanks included in this specification are all those outdoor radwaste tanks that are not surrounded by liners, dikes or walls capable of holding the tank contents and tht do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System.
Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B. Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.
3/4.11.2 GASEOUS EFFLUENTS l
3/4.11.2.1 EXPLOSIVE GAS HIXTURE l
This specification is provided to ensure that the concentration of poten-tially explosive gas mixtures contained in the WASTE GAS HOLDUP SYSTEM is main-tained below the flammability limits of hydrogen and oxygen.
(Automatic control features are included in the system to prevent the hydrogen and oxygen concen-trations from reaching these flammability limits.
These automatic control features include isolation of the source of hydrogen and/or oxygen, automatic diversion to recombiners, or injection of dilutants to reduce the concentration below the flammability limits.) Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CcR Part 50, 3/4.11.2.2 GAS STORAGE TANKS l
The tanks included in this specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by another Technical Specification.
Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting whole body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed 0.5 rem.
This is consistent with Standard Review Plan 11.3, Branch Technical Position ETSB 11-5, " Postulated Radioactive Releases Due to a Waste Gas System Leak or Failure," in NUREG-0800, July 1981.
CATAWBA - UNITS 1 & 2 B 3/4 11-1 AMENDMENT NO.103 (Unit 1) l AMENDMENT NO. 97 (Unit 2)
MMINISTRATIVECONT_ROLS PROCEDURES AND PROGRAMS (Continued) e.
Post-Accident Sampling A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and 1 articulates in plant gaseous effluents, and containment atmosnere samples under accident conditions.
The program shall include tie following:
1)
Training of personnel, 2)
Procedures for sampling and analysis, and 3)
Provisions for maintenance of sampling and analysis equipment, f.
Radioactive Effluent Controls Program 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 Chapter 16 of the FSAR,(2)shallbeimplementedbyoperatingprocedures,and(3)shall include remedial actions to be taken whenever the program limits are exceeded.
The program shall include the following elements:
1)
Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and set-point 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 gaseouseffluentsin,accordancewith10CFR20.106andwiththe 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 each unit to UNRESTRICTED AREAS conform-ing to Appendix I to 10 CFR Part 50, 5)
Determinationofcumulativeandarojecteddosecontributions from radioactive effluents for t1e current calendar guarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, 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 releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of CATAWBA - UNITS 1 & 2 6 Amendment No.103 Unit 1 Amendment No. 97 Unit 2
_ ____.__m._
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 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 material 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 each 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 radionuclides in particulate form with half-1*ves greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE B0UNDARY conforming to Appendix I to 10-CFR Part 50, and-
- 10) Limitations on the annual dose or 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.
g.
Radiological Environmental Monitoring Pt-ogram A program shall be provided to monitor the radiation and radionuclides 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 moaltoring' program and modeling or-environmental exposure pathways.
The program shali (1) be containad in Chapter 16 of the FSAR,-(2) conform to-the guidance of Appendix I to 10 CFR Part 50, and'(3) include the following:
1)
Monitoring, sampling, analysis, and reporting of radiation and radionuclides-in the environment in accordance with the.
methodology and parameters in the 00CM, 2)
A-Land Use Census to ensure that changes in the usa 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 a Interlaboratory Comparison Program to ensure that independent checks on the precision and-accuracy of the measurements of radioactive materials in the environmental ~
sample matrices are performed as part of the quality assurance i
program for environmental monitoring.-
CATAWBA - UNITS 1&2 6-15a-Amendment No.103 (Unit 1)
Amendment No. 97 (Unit 2)
e ADMINISTRATIVE CONTROLS 6_. 9 REP 0inNG REQUIREMENTS iGUiiNE REPORTS 6.S.1 In addition to tne applicable reporting requirements of Title 10 Code af Federal Regulations, the following reports shall be submitted to NRC,in at A-i m:e with 10 CFR 50 4.
<~
y o.;
anary report of plant startup and power escalation testing shall be subm to
'ollowing(1)receigtofanOperatingLicense
.4volvingaplannedincreaseinpowerlevel,(.$)(2)amendnientto the lict installation of fuel i.. 4s a different design or has bee 1 manufactured by a different fuel sup.i.
(4) modifications that may have significantly altered the nuclear, therm,n e
,draulic performance of the unit.
5.9,22 The Jtartup Report sN11 address each of the tests identified in the Finai Safety Analysis Report and shall include a descri) tion of the measured vehes of the operating conditions or characteristics o)tained during the test program and a comparison of these values with design predictions and specifica-tions.
Any corrective actions that were required to obtain satisfactory operatiori shall also be descrioed. - Any additional s)ecific details required in license conditions based on other commitments shall )e included in this report.
6.9.1.3 Startu) Reports shall be submitted withi
- 1) 90 days following comp?etion of tie St
'9p. c.it Program 11 por o9erdio(2) 90 da)s rollowing resumptio commencement of comme.-
n, or (3 9 months following initial criticali'y, whichever is earlinst'.
If the Startup Report does not cover all thrt, avern (i.e.
initial critkality, completion of Startup Test Program, and resumpti.)n or c,ommencement of commercial Operation), supplementary reports shall be submitted at least every 3 months uriti? all three events have been completed.
CATAWBA - UNITS 1 & 2 6-15b Amendment No.101 Unit 1 Amendment No. 97 Unit 2
- 4 ADMINISTRATIVE CONTROLS 1/
ANNUAL REPORTS 6.9.1.4 Annual Reports covering the activities of the unit as described below for the arevious calendar year shall be submitted prior to March 1 of each i
year.
T1e initial report shall be submitted prior to March 1 of the year following initial criticality.
6.9.1.5 Annual Reports shall include the activities of the unit as described below:
a.
Personnel Exposures Reports required on an annual basis shall include a tabulation on an annual basis of the number of station, utility, and other personnel (including contrac-tors) receiving exposures greater than 100 mrem /yr and their associated man-rem 2/
exposureaccordingtoworkandjobfunctions
, e.g., reactor operations and surveillance,tenance) ions inservice inspection, routine maintenance, special maintenance (describe main
, waste arocessing,d based on pocket dosimeter, TLD, or and refueling.
The dose assignments ur variou; duty funct may se estimate e
S(;
film badge measurements.
Small exposures totalling less than 20% of the indi-
'o vidual total dose need not be accounted for.
In the aggregate, at least 80% of
^
the total whole-body dose received from external sources should be assignad to specificmajorworkfunctions.
/
b.
Primary Coolant Specific Activity Reports reguired on an annual basis shall include the results of specific activity analysis in which the primary coolant exceeded the limits of Specifica-tion 3.4.8.
The following information shall be included:
1)Reactorpower history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was ex-4 ceeded; 2) Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while ilmit was exceeded and results
~
of one analysis after the radioiodine activity was reduced to less than limit.
Each result should include date and time of sampling and the radiciodine concen-trations; 3)ich the limit was exceeded; y starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the firstM Graph of Clean-up, system flow histor sample in wh one other radiciodine isotope concentrat;on in microcuries per gra~ is a func-tion of time for the duration n the saec Tic activity above the steady-state level; and 5) The time duration when tie speci Ne activity of the primary coolant exceeded the radiciodine limit.
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ***
6.9.1.6 Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.
The report shall include summaries interpreta-tions, and analysis of trends of the results of the Radiological, Environmental Monitoring Program for the reporting period.
The material provided shall be 1/ A single submittal may be made for the station.
The submittal should i
combine those sections that are common to both units.
2/ This tabulation supplements the requirements of 6 20.407 of 10 CFR Part 20.
"*A single submittal may be made for the station.
l CATAWBA - UNITS 1 & 2 6-16 Amendme.it No.103 { Unit 1) l Amendment No. 97 (Unit 2)
ADMINI5TRATIVE CONTROLS ANydALRADIOLOGICALENVIRONMENTAL'OPERATINGREPORT(Continued) consistent with the objectives outlined in (1) Chapter 16 of the FSAR and (2)
Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT
- l
- 6. 9.- l. 7 The Semiannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months of operation shall be sub-mitted within 60 days after January 1 and July 1 of each year.
The Radioactive Effluent Release Report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.
The mater-ial arovided shall be (1) consistent with the objectives outlined in Chapter 16 of tie FSAR and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.
- A single submittal may be made for the station.
The submittal should combine those sections that are con. mon to both units.
CATAWBA - UNITS 1 & 2 6-17 Amendment No.103 Unit 1 Amendment No.- 97 Unit 2
ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORTS 6.9.1.8-Routine reports of operating statistics and shutdown experience, in-cluding documentation of all challenges to the PORVs or t,afety valves, shall be submitted on a monthly basis to the NRC in accordance with 10 CFR 50.4, no later than the 15th of each month following the calendar month covered by the report.
CORE OPERATING LIMITS REPORT 6.9.1.9 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:
1.
Moderator Temperature Coefficient BOL and EOL limits and 300 ppm surveillance limit for Specification 3/4.1.1.3,
- f..
Shutdown Bank Insertion Limit for Specification 3/4.1.3.5, 3.
Control Bank Insertion Limits for Specification 3/4.1.3.6, 4.
Axial Flux Difference Limits, target band *, and APLND* for Specification 3/4.2.1, RTP ND** p (X,Y,Z) and l
5.
Heat Flux Hot Channel Factor, F
, K(Z), W(Z)**, APL W(Z)BL**frSpecification3/4.3.2,and
,9 tamm g7p 6.
Nuclear Enthalpy Rise Hot Channel Factor, FAH (X,Y) or, FAH anns and Power Factor hitiplier, MFAH
, limits for Specifica-tion 3/4.2.3.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by NRC in:
1.
WCAP-9272-P-A, " WESTINGHOUSE RELOA0 SAFETY EVALUATION METHODOLOGY,"
July 1985 Q( Proprietary).
(Methodology for Specifications 3.1.1.3 - Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Bank Insertion Limit, 3.1.3.6 - Control Bank Insertion Limits, 3.2.1 - Axial Flux ND
~
- Reference 5 is not applicable to target band and APL. ND
- References 4 and 5 are not applicable to W(Z), and APL,andW(Q.
l
- Reference 1 is not applicable to FAH.
- Reference 5isnotapplicabletoFhPand MF3g.
CATAWBA - UNITS 1 & 2 6-18 Amendment No.103 (Unit 1) l Amendment No. 97 (Unit 2)
ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPCRT (Continued)
Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 -
Nuclear Enthalpy Rise Hot Channel Factor.)
2.
WCAP-10216-P-A, " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ q
SURVEILLANCE TECHNICAL SPECIFICATION," June 1983 (W Proprietary).
(Methodology for Specifications 3.2.1 - Axial Flux Difference (Relaxed Axial Offset Control) and 3.2.2 - Heat Flux Hot Channel Factor (W(Z) surveillance requirements for F Methodology.)
q 3.
WCAP-10266-P-A Rev. 2, "THE 1981 VERSION OF WESTINGHOUSE EVALUATION MODEL
~
USING BASH CODE," March 1987, (W Proprietary).
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
4.
BAW-10168PA, Rev.1, "B&W Loss-of-Coolant Accident Evaluation Model for-Recirculating Steam Generator Plants," January 1991 (B&W Proprietary).
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
5.
DPC-NE-2011P-A, " Duke Power Company Nuclear Design Methodology for Core Operating-Limits of-Westinghouse Reactors," March, 1990 (DPC Proprietary).-
(Methodology for Specifications 3,1.3.5 - Shutdown Rod-Insertion Limits, 3.1.3.6 - Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference,.
3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor.)
6.
DPC-NE-3001P-A, " Multidimensional Reactor Transients and: Safety Analysis Physics Parameter Methodology," November 1991 (DPC Proprietary).
(Methodology:for Specification 3.1.1.3 - Moderator Temperature Coeffi-cient, 3.1.3.5 - Shutdown Rod Insertion Limits, 3.1.-3.6 -1 Control Bank Insertion-Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor,- and 3.2.3 - Nuclea'r Enthalpy Rise Hot _ Channel: Factor.)
7.
DPC-NF_-2010P-A, " Duke Power Company McGuire Nuclear Station Catawba Nuclear: Station Nuclear Physics Methodology for Reload Design," June 19851 (DPC-Proprietary).
(Methodology for Specification 3.1.1.3 - Moderator Temperature
-Coefficient.)
8.
DPC-NE-3002A, "FSAR Chapter 115 System Transient Analysis Methodology," -
November 1991.
-(Methodology used in the system thermal-hydraulic analyses which determine.the core operating limits) g CATAWBA --UNITS 1 & 2-6-19 Amendment No'.103 (Unit 1)
AmendmentLNo }97 (Unit 2)-.
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ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued) 9.
OPC-NE-3000P-A, Rev. 1, " Thermal-Hydraulic Transient Analysis Methodology,"_ November 1991.
(Modeling used in the system thermal-hydraulic analyses)
The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC in accordance with 10 CFR 50.4.
4 CATAWBA - UNITS 1-& 2 6-19a Amendment Pk).103 (Unit 1)
Amendment No. 97 (Unit 2)
ADMINISTRATIVE CONTROLS SPECIAL REPORTS-6.9.2 Special reports shall be submitted to the NRC in accordance with 10 CFR 50.4 within the time period specified for each report, 6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of T1De 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.
The following records shall be retained for at least 5 years:
Records and logs of unit operation covering time interval at each a.
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; d.
Records of surveillance activities, inspections, and calibrations required by these Technical Specifications; Records of changes made to the procedures required by Specification e.
6.8.1; f.
Records of radioactive shipments; g.
Records of sealed source and fission detector leak tests and results; and h.
Records of annual physical inventory of all sealed source material of record.
6.10.2 The fnllowing records snall be retained for the duration of the unit Operating License:
Records and drawing changes reflecting unit design modifications made a.
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 radiation exposure for all individuals entering radiation-l control areas; d.
-Records of gaseous and liquid radioactive material released to the l
environs; e.
_Recoros of transient or operational cycles for those unit components identified in Table 5.7-1;.
f.
Records of reactor tests and experiments; g.
Records of training and qualification for current members of the unit staff; i
CATAWBA --UNITS 1 & 2 6-20 Amendment No.103 Unit.1)
Amendment No. 97((Unit 2)
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j 4
ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued) h.
Records of inservice inspections performed pursuant to these Technical Specifications; i.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59; j.
Records of meetings of the NSRB and reports required by Specification 6.5.1.10; k.
Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.8 including the date at which the service life commences and associated installation and maintenance records; 1.
Records of secondary water sampling and water quality; m.
Records of analyses required by the Radiological Environmental Monitoring Program that would permit evaluation of the accuracy of the analysis at a later date.
This should include procedures effective at specified times and QA records showing that these procedures were followed; and n.
Records of reviews performed for changes made to Section 16.11 (Radiological Effluent Controls) of the FSAR.
6.10.3 Records of quality assurance activities required by the Operational Quality Assursace Manual shall be retained for a period of time as recommended by ANSI N.45.2.9-1974.
6.11 RADIATION PROTECTION PROGRAM 6.11 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 AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20, each high radiation area, as defined in 10 CFR-Part 20, in which the intensity of radiation is equal to or less than 1000 mR/h at 45 cm (18.in.) from the radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto-shall be controlled by requiring issuance of a Radiation Work Permit (RWP).
Individuals qualified in radiation protection procedures (e.g., Radiation Protection Technician) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mR/h, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.
Any individual or grnup of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area; or CATAWBA - UNITS 1 & 2 6-21 Amendment No.103 (Unit 1)
Amendment No. 97 (Unit 2)
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ADMINISTRATIVE CONTROLS 6.15 MAJOR CHANGES TO LIQUID, GASEOUS, AND SOLID RADWASTE TREATMENT SYSTEMS (continued) 2)
Sufficient detailed inforreation to totally support the reason for the change without benefit of additional or supplemental information; 3)
A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems; 4)
An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously-predicted in the License application and amendments thereto; 5)
An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the License application and amendments.thereto; 6)
A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to-be made; 7)
An estimate of the exposure to plant operating personnel as a result of the change; and 8)
Documentation of the fact that the change was reviewed and found acceptable by the Station Manager or the Chemistry Manager.
b.
Shall become effective upon review and acceptance by a qualified individual / organization.
6.16 SECTION 16.11 (RADIOLOGICAL EFFLUENT CONTROLS) 0F THE FSAR 6.16.1 Section 16.11 (Radiological Effluent Controls) of the FSAR shall be approved by the Commission prior to implementation.
6.16.2 Licentee - initiated changes to Section 16.11 (Radiological Effluent Controls) of the FSAR a.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.n.
This documentation shall contain:
1)
SufM cient information to support the change together with the appropriate analyses or evaluations justifying the charige(s) and CATAWBA - ll NITS 1 & 2 6-24 Amendment No.103 (Unit 1)
Amendment No. 97 (Unit 2) w
ADMINISTRATIVE CONTROLS -
6.16 SECTION 16.11 (RADIOLOGICAL EFFLUENT CONTROLS) 0F THE FSAR (Continued) 2)
A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable-regulations or 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 upon review and ecceptance by the Station Manager and a qualified individual / organization per the Qualified Reviewer Program.
Shall be submitted to the Commission in the form of a complete, c.
legible copy of-the entire Section 16.11 of the FSAR as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any changes to Section 16.11 of the FSAR 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 CATAWBA - UNITS 1 & 2 6-25 Amendment No.103 (Unit'1)
Amendment No. 97 (Unit 2)