ML20065M584

Amends 81 & 75 to Licenses NPF-35 & NPF-52,respectively, Relocating Fire Protection Requirements from Tech Specs

ML20065M584
Person / Time
Site:	Catawba
Issue date:	11/30/1990
From:	Matthews D Office of Nuclear Reactor Regulation
To:
Shared Package
ML20065M588	List: ML20065M584 ML20065M589
References
NUDOCS 9012110109
Download: ML20065M584 (19)

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DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE, INC.

DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDNENT 70 FACILITY OPERATING LICENSE Amendment No. 81 License No. NPF-35 1.

The Nuclear Regulatory Comission (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 Nerbership) Corporation and Saluda River Electric Cooperative, Inc.

(licensees dated March 13, 1990, as supplemented May 4, 1990, 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 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) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.

Tht: issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

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

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- 9012110109 901130 PDR ADOCK 07'00 1?

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2 2.

Accordingly, the license is hereby emended by page changes to the Technical Specifications as indicated in the attachcents to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-35 is hereby amended to read as folicws:

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 81, ano 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.

FOR THE NUCLEAR REGULATORY COMMISSION

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bT Da d. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of Issuance:

November 30, 1990 l

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NUCLEAR REGULATORY COMMISSION p

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_ DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDPENT TO FACILITY OPERATING LICENSE Amendment No. 75 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 March 13, 1990, as supplemented May 4, 1990,_ 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; B.

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) that such 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 common defense and security or to the health and safety of the public; and E.

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

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2.

Accordingly, the license is hereby emended by page changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of facility Operating License No, NPF-52 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 75, 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.

FOR THE NUCLEAR REGULATORY COMMISSION f

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W1 Day d 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:

November 30. 1990

ATTACHMENT TO LICENSE AltENDMENT NO. 81 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET li0. 50-413 AND TO LICENSE AMEftDEENT NO. 75 FACILITY OPERATING LICENSE NO. 11PF-52 DOCKET NO. 50-414 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revisto pages are identified by Amendment number and contain vertical lines indicating the areas of change.

The correspor. ding over-leaf page is also provided to maintain document completeness.

Remove Pages Insert Pages VI VI IX IX X

X XIV XIV 3/4 3-71 thru 3/4 3-78.

3/4 3-71 3/4 7-27 thru 3/4 7-37 3/4 7-27 3/4 7-38 3/4 7-38*

B 3/4 3-5 B 3/4 3-5 B 3/4 3-6 B 3/4 3-6 B 3/4 7-6 8 3/4 7-6 8 3/4 7-7 B 3/4 7-7 B 3/4 7-8 6-2 6-2 6-8 6-8 6-13 6-13

• 0verleaf page.

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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION-PAGE 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 SHUTDOWN MONITORING INSTRUMENTATION............

3/4 3-63 TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................................

3/4 3-64 Accident Monitoring Instrumentation......................

3/4 3-65 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION..................

3/4 3-66 TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.............................................

3/4 3-68 Chlorine Detection Systems...............................

3/4 3-70 TABLE 3.3-11 (Deleted)

Loose-Part Detection System.................

3/4 3-79 Radioactive Liquid Effluent Monitoring Instrumentation...

3/4 3-80 TABLE 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3/4 3-81 TABLE 4.3-8 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................

3/4 3-83 Radioactive Gaseous Effluent Monitoring Instrumentation..

3/4 3-85 TABLE 3.3-13 RADIOACTIVE GASE0US EFFl.UENT MONITORING INSTRUMENTATION..........................................

3/4 3-86 TABLE 4.3-9 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................

3/4 3-90 Boron Dilution Mitigation System.........................

3/4 3-92a 3/4.3.4 TURBINE OVERSPEED PR0TECTION..............................

3/4 3-93 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power 0peration..............................

3/4 4-1 Hot Standby..............................................

3/4 4-2 Hot Shutdown.............................................

3/4 4-3 Col d Shutdown - Loops Fi11 ed.............................

3/4 4-5 Cold Shutdown - Loops Not Filled.........................

3/4 4-6 l

CATAWBA - UNITS 1 & 2 VI Amendment No. 81 (Unit 1)

Amendment No. 75 (Unit 2)

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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION

'PAGE Divider Barrier Personnel Access Doors and Equipment Hatches.......-...............................

3/4 6-47 Containment Air Return and Hydrogen Skimmer Systems......

3/4 6-48

-j Floor Drains....................'.........................

3/4 6-50 i

Refueling Canal D-aine...................................

3/4 6-51 Divider Barrier Seal.....................................

3/4 6-52 TABLE 3.6-3 DIVIDER BARRIER SEAL ACCEPTABLE PHYSICAL PROPERTIES...

3/4 6-53 3/4.6.6 CONTAINMENT VALVE INJECTION WATER SYSTEM................

3/4 6-54 i

3/4.7 PLANT SYSTEMS

-3/4.7.1

-TURBINE CYCLE Safety Valves............................................

3/4 7 TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH IN0PERABLE STEAM LINE SAFETY VALVES OURING FOUR LOOP 0PERATION......................................

3/4 7-2 i

TABLE 3.7 STEAM LINE SAFETY VALVES PER L00P.....................

3/4 7-3 Auxiliary Feedwater System...............................

3/4 7-4 Specific Activity.............-...........................

3/4 7-6:

TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE.

AND ANALYSIS PR0 GRAM.....................................

3/4 7-7 Main Steam Line Isolation Va1ves.........................

3/4 7-8 Condensate Storage System................................

3/4 7-9 Steam Generator Power Operated Relief Valves.............

3/4 7-9a 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..........

3/4 7-10 3/4.7.3 COMPONENT COOLING WATER SYSTEM...........................

3/4 7-11 L

3/4.7.4

' NUCLEAR SERVICE WATER SYSTEM.............................

3/4 7-12 3/4.7.5 STANDBY NUCLEAR SERVICE-WATER P0ND.......................

3/4 7-13 3/4.7.6 CONTROL. ROOM AREA VENTILATION SYSTEM.....................

3/4 7-14 3/4.'7.7 AUXILIARY BUILDING FILTERED EXHAUST SYSTEM...............

3/4 7-17 3/4.7.8 SNUBBERS.................................................

3/4 7-19 FIGURE 4.7-1 SAMPLE PLAN 2) FOR SNUBBER FUNCTIONAL TEST...........

3/4 7-24 3/4.7.9 SEALED SOURCE CONTAMINATION..............................

3/4'7-25 3/4.7.10--(DELETED)'

t-l CATAWBA - UNITS 1 & 2 IX Amendment No. 81(Unit 1)

Amendment No. 75(Unit 2)

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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7.11 (DELETED) 3/4.7.12 GROUNDWATER LEVEL.-.....-..................................

3/4 7-38 3/4.7.13 STANDBY SHUTDOWN SYSTEM..................................

3/4 7-40 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 0perating................................................

3/4 8-1 TABLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE........................

3/4 8-9 TABLE 4.8-2 LOAD SEQUENCING TIMES.................................

3/4 8-10 Shutdown.................................................

3/4 8-11 3/4.8.2 D.C, SOURCES 0perating................................................

3/4 8-12 TABLE 4.8-3 BATTERY SURVEILLANCE REQUIREMENTS.....................

3/4 8 Shutdown..................................................

3/4 8-16 3/4.8.3 ONSITE POWER DISTRIBUTION 0perating................................................

3/4 8-17 Shutdown.................................................

3/4 8-18 3/4.8.4 ELECTRICAL. EQUIPMENT PROTECTIVE DEVICES Containment Penetration Conductor Overcurrent Protective Devices.....................................

3/4 8-19 TABLE 3.8-1A UNIT 1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES.......................................

3/4 8-21 Table 3.8-1B UNIT 2 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT

-PROTECTIVE 0EVICES.......................................

3/418-44:

3/4.9 : REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION......................................

3/4 9-1 3/4.9.2 INSTRUMENTATION..........................................

3/4 9-2 3/4.9.3' DECAY TIME...............................................

-3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS........................

3/4 9-4 3/4.9.5 COMMUNICATIONS...........................................-

3/4 9-7 3/4.9.6 MAN I P U LATO R C RAN E........................................

3/4 9-8

. 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING..........

3/4 9-9 CATAWBA - UNITS 1 & 2 X

Amendment No. 81 (Unit L?

Amendment No. 75 (Unit 2)

1 BASES SECTION PAGE TABLE B 3/4.4-1 REACTOR VESSEL TOUGHNESS.........................

B 3/4 4-9 FIGURE B 3/4.4-1 FAST NEUTRON FLUENCE (E>1MeV) AS A FUNCTION OF FULL POWER SERVICE LIFE..................................

B 3/4 4-11 3/4.4.10 STRUCTURAL INTEGRITY.....................................

B 3/4 4-16 3/4.4.11 REACTOR COOLANT SYSTEM VENTS.............................

B 3/4 4-17 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS......................................

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

B 3/4 5-2 3/4.5.4 REFUELING WATER STORAGE TANK..............................

B 3/4 5-2 3/4.6 ' CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT.......................................

B 3/4 6-1 3/4.6.2 -DEPRESSURIZATION AND COOLING SYSTEMS.............

B 3/4 6-4 3/4.6.3 CONTAINMENT ISOLATION VALVES.........................

B 3/4 6-4 3/4.6.4-COMBUSTIBLE GAS CONTR0L...................................

B 3/4 6-4 3/4.6.5 ICE CONDENSER.............................................

B.3/4 6-5 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 7-2a 3/4.7,3 COMPONENT COOLING WATER SYSTEM............................

B 3/4 7-3 3/4.7.4' NUCLEAR SERVICE WATER SYSTEM..............................

B 3/4 7-3 3/4.7.5 STANDBY NUCLEAR SERVICE WATER P0ND........................

B 3/4 7-3a 3/4.7.6 CONTROL ROOM AREA VENTILATION SYSTEM......................

'B 3/4 7-3a 3/4.7.7 AUXILI ARY BUILDING FILTERED EXHAUST SYSTEM................

B 3/4 7-4 3/4.7.8 _ SNUBBERS..................................................

B 3/4 7-4 3/4.7.9 SEALED SOURCE CONTAMINATION...............................

B 3/4 7-6 3/4.7.10~.(DELETED) 3/4.7.11 (DELETED) 3/4.7.12 GROUNDWATER LEVEL.........................................

B 3/4 7-7 3/4.7.13 STANDBY SHUTDOWN SYSTEM...................................

B 3/4 7-7 CATAWBA - UNITS 1 & 2 XIV Amendment No. 81 (Unit 1)

Amendment No. 75 (Unit 2)

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Pages 3/4 3-71 through 3/4 3-78 deleted, CATAWBA - UNITS 1 & 2 3/4 3-71 Amendment No 81 (Unit 1)

Amendment No. 75 (Unit 2)

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4 Pages 3/4 7-27 through 3/4 7-37 deleted.

CATAWBA - UNITS 1 & 2 3/4 7-27 Amendment No. 31 (Unit 1)

Amendmer,t No. '/5 (Unit 2)

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PLANT SYSTEMS 3/4.7.12 GROUNDWATER LEVEL 1

LlhlTING CONDITION FOR OPERATION l

3.7.12.'The groundwater level shall be maintained at or below the top of the adjacent floor slabs of the Reactor Containment Building and the Auxiliary Building.

APPLICABILITY:

At all times.

ACTION,:

a.

With'the groundwater level above the top of the adjacent floor slab by less than or equal to 5 feet, reduce the groundwater level to or below the top of the affected adjacent floor slab within 7 days or be in at letst HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, b.

With the grot.ndwater level above the top of the adjacent floor slab 1

by greater than 5 feet but less than 15 feet, reduce the groundwater level.to less than or equal to 5 feet above-the top of the affected adjacent floor slab within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />'and to or below the top of the affected adjacent floor slab wi. thin 7 days of initially exceeding the above limits or be in at.least HOT STANDEY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTOOWN within the following-30 hours, With the groundwater level above the top of the adjacent floor slab c.

by greater than or equal to 15 feet, be in at'least HOT STANDBY-within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Perform an engineering evaluation to determine the effects of this higher groundwater level on the affected building (s)~and submit the results of this evaluation and any corrective action determined necessary to the Commission _as a Special Report pursuant to Specifi-cation 6.9.2 prior to increasing T above 200'F.

avg d.

Determine the rate of rise of groundwater when the levc! raaches the top of.the floor slab.

If the rate of rise of the groundwater level-is greater than or equal to 0.3 foot per hour, determine the rate of rise at least once per 30_. minutes, If the rate of rise-exceeds-0.5 foot per hour for more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, be in at least HOT STANDBY-within 1 hour-and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

If the rate of rise is less than 0.5 feet per hcur, comply _with the requirements of-ACTIONS a,,

b.,

and c above, i

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l CATAWBA - UNITS 1 & 2 3/4 7-38

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-INSTRUMENTATION BASES

.i REMOTE SHUTDOWN SYSTEM (Continued) l control and power circuits and transfer switches necessaay to eliminate effects of the fire and allow osetation of instrumentation, control and power circuits required to achieve and maintain a safe shutdown condition are independent of areas where a fire could of. mage systems normally used to shutdown the reactor.

This capability is consistent with General Design Criterion 3 and Appendix R to 10 CFR Part 50.

i 3/4.3.3.6 ACCIDENT MONITOPING INSTPUMENTATION The OPERABILITY nf t;ie accident monitoring instrumentation ensures that sufficient.infnetire is available on selected plant parameters to monitor and assess these variables following an accident.

This capability is consis-tent with the recommendations of Regulatory Guide 1.97, Revision 3, "Instrumenta-tion for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions Dur-ing and Fol'owing.an Accident," May 1983 and NUREG 0737, " Clarification of TMI-i Action Plan. Requirements," November 1980.

3/4.3.3.7 ' CHL'IRINE_ DETECTION SYSTEMS The OPERABILITY of the Chlorine Detection Systems ensures that sufficient capability is available to promptly detect and initiate protective action in the event of an accidental chlorine release.. This capability is required to

. protect control room personnel and is consistent with the recommendations of Regulatory Guide 1.95, Revision 1, " Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release," January 1977.

3/4.3.3.8 (Deleted)

-CATAWBA - UNITS 1 & 2 B 3/4 3-5 Amendment No. 81(Unit 1)

Amendment No. 75(Unit 2)

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INSTRUMENTATION BASES 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 consistent 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 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in-liquid effluents during actual or potential releases of liquid effluents.

The-Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the 00CM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. "The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

3/A.'3.3.11 RADIOACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous.

effluents during actual or potential releases of gaseous effluents.

The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior.to exceeding the limits of 10 CFR Part 20.

This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the WASTE GAS HOLDUP SYSTEM.

The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

The sensitivity of any noble gas activity monitor used to

. show compliance with the gaseous effluent release requirements of Specifica-tion 3.11.2.2 shall be such that concentrations as low as 1 x 10-6 mci /cc are measurable,

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Amendment No. 81 Unit 1)

CATAWBA - UNITS 1 & 2 B 3/4 3-6 Amendment No. 75(Unit 2)

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n PLANT SYSTEMS BASES SNUBBERS (Continued)-

The service life of a snubber is established via manufacturer-input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubbers, seal replaced, spring replaced,-in high radiation area, in high temperature area, etc.).

The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions.

These records will provide statistical bases for future consideration of snubber service life.

l 3/4.7.9 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(a)(3) limits for plutonium.

This limitation will ensure that leakage from Byproduct, Source, and Special Nuclear Material sources will not exceed allowable intake values.

Scaled sources are classified into three groups according to their use, with Surveillance Requirements commensurate with the probability of damage to a source in that group.

Those sources which are frequently handled are required

~to be tested more often than those which are not.

Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring.or boron measuring devices) are considered to be stored and need.not be tested unless they are removed.from the shielded mechanism.

3/4.7.10 (Deleted) 3/4.7.11 (Deleted) 3/4.7.12 GROUNDWATER LEVEL inin specification is provided to ensure that groundwater levels will be monitored and prevented from rising to unacceptable levels.

High ground-

- water levels could result in unacceptable structural stresses in the Contain-ment and/or Auxiliary Building due-to uplift and hydrostatic forces during design basis events.

Although these buildings have been statically analyzed to withstand soil pressure along with the uplift and hydrostatic forces resulting from groundwater rebound to yard elevation (593'6"), this. analysis did not include any other loadings and was not a design condition for these buildings.

CATAh8A - UNITS 1 & 2 8 3/4 7-6 Amendment No. 81(Unit 1)

Amendment No. 75 (Unit 2)

PLANT SYSTEMS BASES i

3/4.7.13 STANDBY SHUTDOWN SYSTEM The Standby Shutdown System (SSS) is designed to itigate the consequences of certain postulated fire incidents by providing capability to maintain HOT STANDBY conditions and by controlling and monitoring vital systems from loca-tions external to the main control room, Thir capability is consistent with the requirements of 10 CFR Part 50, Appendix .

The Surveillance Requirements ensure that the SSS systems and components are capable of performing their intended functions.

The required level in the SSS diesel generator feel storage tank ensures sufficient fuel for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> uninterrupted operation It is assumed that, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, either offsite power can be restored or additional fuel can be added to the storage tank.

Although the Standby Makeup Pump is not nuclear safety-related and was not designed according to ASME code requirements, it is tested quarterly to ensure its OPERABILITY.

The Surveillance Requirement concerning the Standby Makeup Pump water supply ensures that an adequate water volume is available to supply the pump continuously for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

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1 CATAWBA - UNITS 1 & 2 8 3/4 7-7 Amendment No. 81 (Unit 1) l f

Amendment No. 75 (Unit 2)

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ADMINISTRATIVE CONTROL UNIT STAFF (Continued)

A Health Physics Technician

• shall be on site when fuel is in either c.

reactor; d.

All CORE ALTERATIONS shall be-observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities ciuring this operation; and e.

(Deleted) f.

Administrative procedures shall be developed and-implemented to limit the working hours of unit staff who perform safety-related functions (e.g.,. licensed Senior Operators, licensed. Operators, health physicists, auxiliary operators, and key maintenance personnel).

Adequate shift coverage shall be maintained without routine heavy use of. overtime.

The objective shall be to have operating personnel work a nominal 40-hour week while the unit is operating.

However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for re-fueling, major maintenance, or major plant modification, on a tempo-rary basis the following guidelines shall be followed:

1)

-An individual should not be permitted to. work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.

2)

An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more-than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all excluding shift turnover time.

3)

A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work periods, including shift turnover time.

4)

Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the Station Manager or his designee, or higher levels of management, in accordance with established procedures and with. documentation of the basis for= granting the. deviation.. Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Station Manager or his designee to assure that-excessive hours have not been assigned.

Routine deviation from the above guidelines.is not authorized.

• The Health Physics Technician may be less than the minimum requirements for a l

period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected absence, provided immediate action is taken to fill the required positions.

CATAWBA - UNITS 1 & 2 6-2 Amendment No. 81(Unit 1)

Amendment No. 75(Unit 2)

.V ADMINISTRATIVE CONTROLS TECHNICAL REVIEW AND CONTROL ACTIVITIES (Continued)

6. 5.1. 6 All REPORTABLE EVENTS and all violations of Technical Specifications shall be investigated and a report prepared which evaluates the occurrence and which provides recommendations to prevent recurrence.

Such reports shall be approved by the Station Manager and transmitted to the Vice President, Nuclear Production, and.to the Nuclear Safety Review Board, 6.5.1.7 The Station Manager shall assure t'te performance of special reviews and investigations, and the preparation and submittal of reports thereon, as requested by the Vice President, Nuclear Production.

6.5.1.8 The station security program, and implementing procedures shall be reviewed at least once per 12 months.

Recommended changes shall be approved by the Superintendent of Station Services and transmitted to the Vice President, Nuclear Production, and to the Nuclear Safety Review Board.

6.5.1.9 The station emergency plan, and implementing procedures, shall be reviewed at least once per 12 months.

Recommended changes shall be approved by the Station Manager and transmitted to the Vice President, Nuclear Production, and to the Nuclear Safety Rcview Board.

6.5.1.10 The Station Manager shall assure tne performance of a review by a t

qualified individual / organization of every unplanned onsite release of radio-active material to the environs including the preparation and forwarding of reports covering evaluation, recommentiations, and disposition of the corrective ACTION to prevent recurrence to the Vice President, Nuclear Production and to the Nuclear Safety Review Board.

6.5.1.11 The Station Manager shall assure the performance of a review'by a qualifed individual / organization of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and Radwaste Treatment Systems.

6.5.1.12 The Station Manager shall assure the performance of a review by a qualified individual / organization of the Fire Protection Program and implementing procedures and the submittal of recommended changes to the Nuclear Safety Review Board.

6.5.1.13 Reports documenting each of the activities performed under Specifications 6.5.1.1 through 6.5.1.11 shall be maintained.

Copies shall be provided to the Vice President, Nuclear Production, and the Nuclear Safety Review Board.

6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB)

FUNCTION 6.5.2.1 The NSRB shall function to provide independent review and audit of designated activities in the areas of:

a.

Nuclear power plant operations, b.

Nuclear engineering, c.

Chemistry and radiochemistry, CATAWBA - UNITS 1 & 2 6-8 Amendment No. 81 (Unit 1)

Amendment No. 75 (Unit 2)

~.

.o

.V ADMINISTRAT13,CpN,T,Rp 6.8 _PROCEDU,RES AND PROGRA,M_S.

6.8.1 Written procedures shall be established, implemented, and maintained-covering the activities referenced below; a.

The applicable procecures reconcended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978; b.

The emergency operating procedures required to implement the require-ments of NUREG-0737.1d Supplement No. I to NUREG-0737 as stated in

'eneric Letter No. 82-33; c.

Security Plan implementation;*

d.

Emergency Plan implementation; c.

PROCESS CONTROL PROGRAM implementation; f.

OFFSITE DOSE CALCULATION MANUAL implementation; I

g.

Quality Assurance Program implementation for effluent and environmental monitoring; h.

Fire Protection Program implementation; i.

Commitments contained in FSAR Chapter 16.0 6.8.2 Each procedure of Specification 6.8.1, and changes thereto, shall be revieweo and approved by the Station Manager; or by:

(1) Operating Superin-tendent, (2) Technical Services Superintendent, W Maintenance Superintendent, or (4) Superintendent of Integrated Scheduling, c. previously designated by the Station Manager; prior to irrplementation and shall be revicwed periodically as set forth in administrative procedures.

6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made pro-vided:

a.

The intent of the original procedure is not altered; b.

The change is approved by two members of the plant management staff, at least one of whom holds a Senior Operator license on the unit affected; and c.

The change is documented, reviewed, and approved by the Station Manager; or by:

(1) Operating Superintendent, (2) Technical Services Superintendent, (3) Maintenance Superintendent, or (4) Superintendent of Integrated Scheduling, as previously designated by the Station Manager; within 14 days of implementation.

6.8.4 The following programs shall be established, implemented, and maintained:

a.

Primary Coo _lant Sources Ou_tside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.

The systems include the containment spray, Safety Injection, chemical

• Review and approval may be performed by the Superintendent af Station Services.

CATAWBA - UNITS 1 & 2 6-13 Amendment No. 81 (Unit 1)

Amendment No. 75 (Unit 2)