Text

Amends 37 & 29 to Licenses NPF-35 & NPF-52,respectively, Modifying Tech Specs to Eliminate Typos,To Provide Addl Clarification & to Improve Consistency
	ML20237C799
Person / Time
Site:	Catawba
Issue date:	12/14/1987
From:	Jabbour K; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20237C802	List: ML20237C799; ML20237C804;
References
	NUDOCS 8712220193
	Download: ML20237C799 (57)
	v • d • e

_ _ _ _ _ _ - _ - _.

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NUCLEAR REGULATORY COMMISSION

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DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION 1

SALUDA RIVER ELECTRIC C0_0 PERATIVE, INC.

DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 37 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 Membership Corporation and Saluda River Electric Cooperative, Inc., (licensees) dated March 7,1986, and supplemented June 12 and July 1,1987, com-plies 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, as amended, 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 i

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 Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is hereby amended 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-35 is hereby amended to read as follows:

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2).TechnicalSpecifications

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

37, are hereby incorporated into the-license.

The licensee 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 PEGULATORY COMMISSION k

Kahtan N.' Jab'oour, Acting PD Project Directorate.II-3 Division of Reactor Projects I/II

Attachment:

Technical Specification Changes Date of. Issuance: December 14, 1987 I

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DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY N0. I

_ PIEDMONT MUNICIPAL' POWER AGENCY DOCKET NO. 50-414 s

CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE s

j Amendment No.

29 License.No. NPF-52 j

1.

The Nuclear Regulatory Comission (the'Comission) has found'that:

1 A.

The application for amendment to the Catawba Nuclear Station, Unit 2 i

(the facility) Facility Operating License No. NPF-52 filed by the Duke.

Power Company acting fcr itself, North Carolina Municipal Power Agency No. I and Piedmont Municipal Power Agency. (licensees) dated March 7, 1986, and supplemented June 12 and July 1,1987,' complies with the standards and requirements of the Atcmic 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, as amended, the provisions of the Act, and the rules and regulations of, the Comission;

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C.

There is reasonable assurance (i) 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 comon defense and security or to the health aisd safety of the public; and E.

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

2.

Accordingly, the license is hereby amended 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:

-2.;

(2)' Technical Specifications

.The Technical Specifications contained'in Appendix A, a's revised through Amendment No. 29, are hereby incorporated _ into the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license anendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY 'C0ft11SSION

\\

Kahtan N. Jabbour, Acting Director Project Directorate 11-3

' Division of Reactor Projects.I/II

Attachment:

Technical Specification

-Changes Date of Issuance:

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4-A'TTACHMENT TO LICENSE AMENDMENT NO. 37 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND TO LICENSE AMENDMENT NO. 29 FACILITY OPERATING LICENSE NO. NPF-52 i

DOCKET NO. 50-414 Replace the following pages of the Appendix "A". Technical Specifications with.

the' enclosed pages. The revised pages.are identified by Amendment number and -

contain vertical lines indicating the areas of change. The corresponding over-leaf pages.are also provided to maintain document completeness.

Amended Overleaf -

Page Page 1-6 1-5

'l 2-6 A

- 3/4 1-14 3/4 1-13

.3/4 3-24 3/4 3-23 3/4 3-26 3/4 3-25 3/4 3-53 3/4 3-70 3/4 4-20 3/4 4-21 3/4 4-22 3/4 6-14 3/4 6-13 3/4 6-15 3/4 6-16 3/4 6-17 3/4 6-18 3/4 6-28 3/4 6-27 3/4 6-36' 3/4 6-35 3/4 7-14 3/4 7-13 3/4 7-15

~

.3/4 7-16 3/4 7-17 3/4 7-18 3/4 9-4 3/4 9-3 3/4 9-5 1

3/4 9-6 3/4 9-14 3/4 9-13 3/4 9-15 3/4 11-3 3/4 11-4 3/4 11-8 3/4 11-7 i

3/4 11-11 3/4 11-12 3/4 12-2 3/4 12-1 3/4 12-11 3/4 12-12 B3/4 6-3 B3/4 6-4 83/4 9-1 83/4 9-3 6-5

DEFINITIONS l

4 RATED THERMAL POWER 1.25 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3411 MWt.

REACTOR BUILDING INTEGRITY 1.26 REACTOR BUILDING INTEGRITY shall exist when:

Each door in each access opening is closed except when the access a.

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 l

The sealing mechanism associated with each penetration (e.g., welds, c.

bellows, or 0-rings) is OPERABLE.

REACTOR TRIP SYSTEM RESPONSE TIME 1.27 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 1.28 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR Part 50.

r SHUT 00WN MARGIN

.4 5

1.29 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subtritical 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 1.30 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by licensee.

SLAVE RELAY TEST 1.31 A SLAVE RELAY TEST shall be the energization of each slave relay and verification of OPERABILITY of each relay.

The SLAVE RELAY TEST shall include a continuity check, as a minimum, of associated testable actuation devices.

SOLIDIFICATION 1.32 SOLIDIFICATION shall be the conversion of wet wastes into a form that meets shipping and burial ground requirements.

CATAWBA - UNITS 1 & 2 1-5

L DEFINITIONS SOURCE CHECK 1.33 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a sodrce of increased radioactivity.

STAGGERED TEST BASIS

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1.34 A STAGGERED TEST BASIS shall consist of:

A test schedule for n systems, subsystems, trains, or other designated a.

components obtained by dividing the specified test interval into n equal subintervals, and b.

The testing of one system, subsystem, train, or other designated j

component at the beginning of each subinterval.

f THERMAL POWER 1.35 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TRIP ACTUATING DEVICE OPERATIONAL TEST 1.36 A TRIP ACTUATING DEVICE OPERATIONAL TEST shall consist of operating the Trip Actuating Device and verifying OPERABILITY of alarm, interlock and/or trip functions.

The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include adjustment, as necessary, of the Trip Actuating Device such that it actuates at the required Setpoint within the required accuracy.

UNIDENTIFIED LEAKAGE 1.37 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.

UNRESTRICTED AREA 1.38 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

VENTILATION EXHAUST TREATMENT SYSTEM 1.39 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through activated carbon adsorbers and/or HEPA filters for the purpose of removing todines or particulate from the gaseous exhaust stream prior to the release to the envi-ronment.

Such a system is not considered to have any effect on noble gas effluents.

Engineered Safety Features (ESF) Atmospheric Cleanup Systems cra not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

CATAWBA - UNITS 1 & 2 1-6 Amendment No. 37 (Unit 1)

Amendment No. 29 (Unit 2)

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-REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS 4.1 2.6 Each borated water source shall be demonstrated OPERABLE:

a.

At least once per 7 days by:

t 1)

Verifying the boron concentration in the water, i

2)

Verifying the contained borated water volume of the water source, and 3)

Verifying the Boric Acid Storage System solution temperature r

when-it is the source of borated water.

1

..i b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the refueling water stcragej <

tank temperature when the outside air temperature is either less than

.a 70 F or greater than'100*F.

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CATAWBA - UNITS 1 & 2 3/4 1-13

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REACTIVITY CONTROL SYSTENS s

3/4.1.) MOVABLE CONTROL ASSEMBLIES GROUQHEIGHT en Q

LIMITINGCONDITIONFOROPERhTION

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3.1.3.1 All full-length shutdnwn and control rods shall be OPERABLE ind positioned within 112 steps (indicated pisition) of their group step counter l

der:std position.

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APPLICABILITY: MODES 1* and {.

a i L AClION-

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t With one or more ful blength. cods inoperable due is being irmovabl4 a.

t' as a result of excessive fridiont )r mechanical ildecfererae or known to be untrippable, determine that the SHUTDOWN MMGIb reouire-J ment of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months anu be in r

HOTSTANDBYwithin6fhrup.

b.

With more than one fdil_-length roc misaligned frp, t a group step counter demand position' by more than 12 steps (indicated po.sition),

f' be in HOT STAN0by Wfthin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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c.

With one full-lengthfrod trippable but iroperable due to causes other than 'Mdressed oy ACTION a., above, or misMigned from ?ts group step cstinter demand height by more than 112 iteps (indikated positior0j POWER OPERATION may continue provided that within 1 hour:

l'.

The rod is restored to OPERABLE status withfr. the above alignmant

,. requirements, or 1

i 2.

)1N rod is declared inoperable and the remainder of the rods in t

m grour' with the inoperable rod are aligned to within i 12 steps D

of the inoperabirf rod while n:aintaining the rod sequence and insertion limf H 'of Figure 3.1-la or Figure 3.1.lb, as applicable.

s The THERMAL POWErl luel s' tall be re:tricted pursuant to Specifi-l cation 3.1.3.6 Caring subseiuent operation, or l

s 3.

The rod is declared inoperable end the SHUTOOWN MARGIN require-s i s ment of Specificathn 3.1.1.1 is satisfied.

POWER OPERATION

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'nay then continue'previded that:

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a)

A reevaluation of each accident analysis tf Table 3.1-1 19 performed within 5 days; this reevaluat$3n shall confirm that the previously analyzed results of thee accidents remain valid for the d:. ration of operetion 1;Mer these conditions; t

b)

The SHUTDOWN MARGIN requbement of Specification 3.1.1.1 is determined at least nnce per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ;

See Special Test Exceptions Specification.s 3.10.2 and 3.10.3.

CATAVy'- UNITS 1 & 2 f./4 1-M Anendment No. 37 (Uni t,1)

Amendment No - 29 (Urt't O '

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TABLE 3.3-3 (Continued)

TABLE NOTATIONS

Trip function may be blocked in this MODE below the P-11 (Pressurizer Pressure Interlock) setpoint.

1. Trip function automatically blocked above P-11 and may be blocked below P-11 when Safety Injection on low steam line pressure is not blocked.

The provisions of Specification 3.0.4 are not applicable.

ACTION STATEMENTS ACTION 14 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the folluwing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; however,' one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE.

ACTION 15 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 16 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met.

One additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1.

i ACTION 17 - With less than the Minimum Channels OPERABLE requirement, operation may continue provided the containment purge supply and exhaust valves are maintained closed.

ACTION 18 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 19 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and b.

The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for sur-veillance testing of other channels per Specification 4.3.2.1.

CATAWBA - UNITS 1 & 2 3/4 3-25 4

l TABLE 3.3-3 (Continued) l ACTION STATEMENTS (Continued)

ACTION 20 - With less than the Minimum Channels OPERABLE, within I hour determine by observation of the associated permissive status light (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

i ACTION 21 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least H0T SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

ACTION 22 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least H0T SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 23 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the associated valve inoperable and take the ACTION required by Specification 3.7.1.4.

ACTION 24 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , or initiate and maintain operation of the Control Room Area Ventilation System with flow through the HEPA filters and activated carbon adsorbers.

l ACTION 25 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 26 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 27 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

CATAWBA - UNITS 1 & 2 3/4 3-26 Amendment No. 37 (Unit 1)

Amendment No. 29 (Unit 2)

TABLE'3.3-6 (Continued)

TABLE NOTATIONS With fuel in the fuel storage pool areas.

With irradiated fuel in the fuel storage pool areas.

When venting or purging from containment to the atmosphere, the trip set-point shall not exceed the equivalent limits of Specification 3.11.2.1 in accordance with the methodology and parameters in the ODCM.

When not vent-ing or purging in Modes 5 or 6, the alarm setpoint concentration (pCi/ml) shall be such that the actual _ submersion dose rate would not exceed 5mR/hr without alarm.

When not venting or purging in Modes 1 through 4 the alarm setpoint shall be no more than 3 times the containment atmosphere activity as indicated by the radiation monitor.

i ACTION STATEMENTS ACTION 30 - With less than the Minimum Channels OPERABLE requirement, operation may continue provided the containment purge and exhaust valves are maintained closed.

ACTION 31 - With the number of operable channels one less than the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months isolate the affected Control Room Ventilation System intake from outside air with flow through the HEPA filters and activated carbon adsorbers.

l ACTION 32 - With less than the Minimum Channels OPERABLE requirement, opera-tion may continue for up to 30 days provided an appropriate portable continuous monitor with the same Alarm Setpoint is provided in the fuel storage pool area.

Restore the inoperable monitors to OPERABLE status within 30 days or suspend all operations involving fuel movement in the fuel building.

ACTION 33 - Must satisfy the ACTION requirement for Specification 3.4.6.1.

ACTION 34 - With the number of OPERABLE channels less than the Minimum

~

Channels OPERABLE requirement, operation may continue provided the Fuel Handling Ventilation Exhaust System is operating and discharging through the HEPA filters and activated carbon adsorbers.

l Otherwise, suspend all operations involving fuel movement in the fuel building.

ACTION 35 - With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, operation may continue provided the Auxiliary Building Filtered Exhaust System is operating and discharging through the HEPA filter and activated carbon adsorbers.

l ACTION 36 - With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, operation may continue for up to 30 days provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed for radioactivity (gross gamma) at a lower limit of detection of no more than 10 7 pCi/ml.

CATAWBA - UNITS 1 & 2 3/4 3-53 Amendment No. 37 (Unit 1)

Amendment No. 29 (Unit 2)

4 INSTRUMENTATION CHLORINE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.3.3.7 'Two independent Chlorine Detection Systems, with their Alarm / Trip Setpoints adjusted to actuate at a ' chlorine concentration of less than or equal to 5 ppm, shall be OPERABLE.

APPLICABILITY:

All MODES.

ACTION:

With one Chlorine Detection System inoperable, restore the inoperable a.

system to OPERABLE status within 7 days or within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months initiate and maintain operation of the Control Room Area Ventilation System with flow through the HEPA filters and activated l

carbon adsorbers.

b.

With both Chlorine Detection Systems inoperable, within I hour initiate and maintain operation of the Control Room Area Ventilation System with flow through the HEPA filters and activated

[

carbon adsorbers.

The provisions of Specification 3.0.4 are not applicable.

c.

SURVEILLANCE REQUIREMENTS

~

4.3.3.7 Each Chlorine Detection System shall be demonstrated OPERABLE by performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an ANALOG CHANNEL OPERATIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.

CATAWBA - UNIT 1 & 2 3/4 3-70 Amendment No. 37 (Unit 1)

Amendment No. 29 (Unit 2)

i REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE 1

LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKAGE, i

b.

1 gpm UNIDENTIFIED LEAKAGE, l

I gpm total reactor-to-secondary leakage through all steam generators c.

and 500 gallons per day through any one steam generator, d.

10 gpm IDENTIFIED LEAKAGE from the Reactor Coolant System, 40 gpm CONTROLLED LEAKAGE at a Reactor Coolant System pressure of e.

2235 1 20 psig, and f.

1 gpm leakage at a Reactor Coolant System pressure of 2235 1 20 psig from any Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY a.

within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE B0UNDARY LEAKAGE and leakage from Reactor Coolant System Pressure Isolation Valves, reduce the leakage rate to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

l With any Reactor Coolant System Pressure Isolation Valve leakage c.

greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least two closed manual or deactivated automatic valves, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

CATAWBA - UNITS 1 & 2 3/4 4-20 Amendment No. 37(Unit 1)

Amendment No. 29(Unit 2)

REACTOR COOLANT SYSTEM-SURVEILLANCE REQUIREMENTS 4.4;6.2.1 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:

Monitoring the containment atmosphere gaseous or particulate radio-l a.

>^

activity monitor at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; b.

Monitoring the containment floor and equipment sumps inventory and discharge at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; Measurement of the CONTROLLED LEAKAGE to the reactor coolant pump c.

i seals when the Reactor Coolant System pressure is 2235 1 20 psig at least once per 31 days.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4; d.

Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; and Monitoring the. reactor head flange leakoff at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , l

e.

4.4.6.2.2 Each Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1 shall be demonstrated OPERABLE by verifying leakage to be within its limit:

a.

At least once per 18 months, b.

Prior to entering MODE 2 whenever the plant has been in COLD

. SHUTDOWN for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or more and if leakage testing has not been-performed in the previous 9 months, Prior to returning the valve to service following maintenance, c.

repair or replacement work on the valve, and d.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation due to automatic or manual action or flow through the valve.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.

1 i

CATAWBA - UNITS 1 & 2 3/4 4-21 Amendment No. 37(Unit 1)

Amendment No. 29(Unit 2)

~

ie TABLE 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES r

VALVE NUMBER FUNCTION NI59 Accumulator Discharge NI60 Accumulator Discharge NI70 Accumulator Discharge NI71 Accumulator Discharge NI81 Accumualtor Discharge NI82 Accumulator Discharge-NI93 Accumulator Discharge NI94 Accumulator Discharge N1124 Safety Injection (Hot Leg)

N1125 Residual Heat Removal (Hot Leg)

NI126 Safety Injection (Hot Leg)

NI128 Safety Injection (Hot Leg)

NI129 Residual Heat Removal (Hot Leg)

NI134 Safety Injection (Hot Leg)

NI156 Safety Injection (Hot Leg)

NI157 Safety Injection (Hot Leg)

NI159 Safety Injection (Hot Leg)

NI160 Safety Injection (Hot Leg)

NI165

. Safety Injection / Residual Heat Removal (Cold Leg)

N1167 Safety Injection / Residual Heat Removal (Cold Leg)

NI169 Safety' Injection / Residual Heat Removal (Cold Leg)-

NI171 Safety Injection / Residual Heat Removal (Cold Leg)

NI175 Safety Injection / Residual Heat Removal (Cold Leg)

NI176 Safety Injection / Residual Heat Removal (Cold Leg)

NI180 Safety Injection / Residual Heat Removal (Cold Leg)

NI181 Safety Injection / Residual Heat Removal (Cold Leg)

~NI248 Upper Head Injection NI249 Upper Head Injection N1250 Upper Head Injection NI251 Upper Head Injection NI252 Upper Head Injection NI253 Upper Head Injection i

k CATAWBA - UNITS 1 & 2 3/4 4-22

CONTAINMENT SYSTEMS REACTOR BUILDING STRUCTURAL INTEGRITY l

LIMITING CONDITION FOR OPERATION 3.6.1.7 The structural integrity of the reactor building shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.7.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With the structural integrity of the reactor building not conforming to the above requirements, restore the structural integrity to within the limits prior to i'ncreasing the Reactor Coolant System temperature above 200 F.

SURVEILLANCE REQUIREMENTS 4.6.1.7 The structural integrity of the reactor building shall be determined during the shutdown for each Type A containment leakage rate test (reference Specification 4.6.1.2) by a visual inspection of the exposed accessible interior and exterior surfaces of the reactor building and verifying no apparent changes in appearance of the concrete surfaces or other abnormal degradation.

Any abnormal degradation of the reactor building detected during the above required inspections shall be reported to the Commission within 15 days as a Special 4,

i Report pursuant to Specification 6.9.2.

m CATAWBA - UNITS 1 & 2 3/4 6-13

CONTAINMENT SYSTEMS ANNULUS VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION I

1 3.6.1.8 Two independent Annulus Ventilation Systems shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With one Annulus Ventilation System inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.1.8 Each Annulus Ventilation System shall be demonstrated OPERABLE:

At least once per 31 days on a STAGGERED TEST BASIS by initiating, a.

from the control room, flow through the HEPA filters and activated l

carbon adsorbers and verifying that the system operates for at least 10 continuous hours with the pre-heaters operating; b.

At least once per 18 months or (1) after any structural maintenance on the HEPA filter or activated carbon adsorber housings, or (2) fol-l lowing painting, fire, or chemical release in any ventilation zone communicating with the system by:

1)

Verifying that the cleanup system satisfies the in place pene-tration and bypass leakage testing acceptance criteria of less than 1% (Unit-1), 0.05% (Unit 2) and uses the test procedure

~

guidance in Regulatory Positions C.5.a, C.5.c and C.5.d* of j

Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 9000 cfm i 10%;

4 2)

Verifying, within 31 days after removal, that a laboratory analysis of a representative activated carbon sample obtained l

in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 1%; and 3)

Verifying a sys hm flow rate of 9000 cfm i 10% during system operation when tested in accordance with ANSI N510-1980.

I

The requirement for reducing refrigerant concentration to 0.01 ppm may be satisfied by operating the system for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with heaters on and operating.

CATAWBA - UNITS 1 & 2 3/4 6-14 Amendment No. 37 (Unit 1)

Amendment No. 29 (Unit 2)

-___.__n_____.-___

_m_

CONTAINMENT SYSTEMS i

SURVEILLANCE REQUIREMENTS (Continued)

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of activated carbon adsorber operation, by l

c.

verifying, within 31 days after removal, that a laboratory analysis of a representative activated carbon sample obtained in accordance

[

with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Posi-tion C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 1%;

d.

At least once per 18 months by:

1)

Verifying that the pressure drop across the combined HEPA fil-ters, activated carbon adsorber banks, and moisture separators l

is less than 8 inches Water Gauge while operating the system at a flow rate of 9000 cfm i 10%;

2)

Verifying that the system starts automatically on any Phase "A" Isolation test signal,**

3)

Verifying that the filter cooling electric motor-operated bypass valves can be manually opened, 4)

Verifying that each system produces a negative pressure of greater than or equal to 0.5 inch Water Gauge in the annulus within 1 minute after a start signal, and 5)

Verifying that the pre-heaters dissipate 45 1 6.7 kW.

After each complete or partial replacement of a HEPA filter bank, by e.

verifying that the cleanup system satisfies the in place penetra-tion and bypass leakage testing acceptance criteria of less than 1%

(Unit 1), 0.05% (Unit 2) in accordance with ANSI N510-1980 for a D0P test aerosol while operating the system at a flow rate of 9000 cfm i 10%; and-f.

After each complete or partial replacement of an activated carbon l-adsorber bank, by verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria i

of less than 1% (Unit 1), 0.05% (Unit 2) in accordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of 9000 cfm i 10%.

- This surveillance need not be performed until prior to entering HOT SHUTDOWN following the Unit 1 first refueling.

CATAWBA - UNITS 1 & 2 3/4 6-15 Amendment No.37(Unit 1)

Amendment No.29(Unit 2)

I l

l j

1 CONTAINMENT SYSTEMS CONTAINMENT PURGE SYSTEMS g

LIMITING CONDITION FOR OPERATION 3.6.1.9 Each containment purge supply and exhaust isolation valve shall be OPERABLE and:

a.

Each containment purge supply and/or exhaust isolation valve for the lower compartment and the upper compartment (24-inch), instrument room (12-inch), and the Hydrogen Purge System (4-inch) shall be sealed closed, and b.

The Containment Air Release and Addition System (4-inch) isolation valve (s) may be open for up to 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months during a calendar year.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a.

With any containment purge supply and/or exhaust isolation valve for the lower compartment and the upper compartment, or instrument room, or Hydrogen Purge System open or not sealed closed, close and/or seal closed that valve or isolate the penetrations (s) within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , otherwise be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With the Containment Air Release and Addition System isolation valve (s) open for more than 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months during a calendar year, close j

the open valve (s) or isolate the penetration (s) within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , j

otherwise be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

~

c.

With a containment purge supply and/or exhaust isolation valve (s) having a measured leakage rate in excess of the limits of Specifi-cations 4.6.1.9.3 and/or 4.6.1.9.4, restore the inoperable valve (s) to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , otherwise be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.1.9.1 Each containment purge supply and/or exhaust isolation valves for the lower compartment and the upper containment, or instrument room, or Hydrogen Purge System shall be verified to be sealed closed at least once per 31 days.

4.6.1.9.2 The cumulative time that the Containment Air Release and Addition A

System has been open during a calendar year shall be determined at least once per 7 days.

CATAWBA - UNITS 1 & 2 3/4 6-16 L _

I.

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.1.9.3 At least once per 6 months on a STAGGERED TEST BASIS, the inboard and outboard valves with resilient material seals in each sealed closed contain-l l

ment purge supply and exhaust penetration for the lower compartment and the upper compartment, or instrument room, or Hydrogen Purge System shall be demon-strated OPERABLE by verifying that the measured leakage rate is less than 0.05 L when pressurized to P.

a 3

4.6.1.9.4 At least once per 3 months the Containment Air Release and Addition System valves with resilient material seals shall be demonstrated OPERABLE by-verifying that the measured leakage rate is less than 0.01 L when pressurized to P.

a 3

i l

CATAWBA - UNITS 1 & 2 3/4 6-17 Amendment No. 37 (Unit 1)'

Amendment No. 29 (Unit 2) m I

CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS r

. CONTAINMENT' SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2 Two independent Containment Spray Systems shall be OPERABLE with each Spray System capable of taking suction from the refueling water storage tank and transferring suction to the containment sump.

)

APPLICABILITY: MODES 1, 2, 3, and 4.

i ACTION:

1

{

With~one Containment Spray System inoperable, restore the inoperable Spray System to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within l

the next 6. hours; restore the inoperable Spray System to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

' SURVEILLANCE REQUIREMENTS 4.6.2 Each Containment Spray System shall be demonstrated OPERABLE:

)

At laast once per 31 days by verifying that each valve (manual, a.

power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position; b.

By verifying,.that on recirculation flow, each pump develops a differential pressure of greater than or equal to 185 psid when tested pursuant to Specification 4.0.5; At least once per 18 months during shutdown,** by:

c.

1)

Verifying that each automatic valve in the flow path actuates to its correct position on a Phase "B" Isolation test signal, and 2)

Verifying that each spray pump starts automatically on a Phase "B" Isolation test signal.

3)

Verifying that each spray pump is prevented from starting by the Containment Pressure Control System when the containment atmosphere pressure is less than or equal to 0.25 psid, and is allowed to start at greater than or equal to 0.45 psid relative to the outside atmosphere, h

a:This surveillance need not be performed until prior to entering HOT SHUTDOWN following the Unit 1 first refueling.

CATAWBA - UNITS 1 & 2 3/4 6-18 f

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PLANT SYSTEMS' 3/4.7.5 STANDBY NUCLEAR SERVICE WATER POND LIMITING CONDITION FOR OPERATION 3.7.5 The standby nuclear service water pond (SNSWP) shall be OPERABLE with:

a.

A minimum water level at or above elevation 570 feet Mean Sea Level, USGS datum, and b.

An average water temperature of less than or. equal to 86.5 F at elevation 540 feet in the SNSWP intake structure.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

(Units 1 and 2)

With the requirements of the above specification not satisfied, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.7.5 The SNSWP shall be determined OPERABLE:

-a.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the water level to be within its limit, b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during the months of July, August, and September by verifying the water temperature to be within its limit, and c.

At least once per 12 months by visually inspecting the SNSWP dam and verifying no abnormal degradation, erosion, or excessive seepage.

CATAWBA - UNITS 1 & 2 3/4 7-13

PLANT SYSTEMS 3/4.7.6 CONTROL ROOM AREA VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.6 Two independent Control Room Area Ventilation Systems shall be-OPERABLE.

APPLICABILITY: ALL MODES ACTION:

(Units 1 and 2)

MODES 1, 2, 3 and 4:

With one Control Room Area Ventilation System inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

MODES 5 and 6:

With one Control Room Area Ventilation System inoperable, restore a.

the. inoperable system to OPERABLE status within 7 days or initiate and maintain operation of the remaining 0PERABLE Control Room Area Ventilation System with flow through the HEPA filters and activated l

carbon adsorbers.

b.

With both Control Room Area Ventilation Systems inoperable, or with the OPERABLE Control Room Area Ventilation System, required to be operating by ACTION a., not capable of.being powered by an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

The provisions of Specification 3.0.4 are not applicable.

c.

SURVEILLANCE REQUIREMENTS 4.7.6 Each Control Room Area Ventilation System shall be demonstrated OPERABLE:

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the control room a.

air temperature is less than or equal to 90 F; b.

At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and activated j

carbon adsorbers and verifying that the system operates for at least 10 continuous hours with the heaters operating; CATAWBA - UNITS 1 & 2 3/4 7-14 Amendment No. 37 (Unit 1)

Amendment No. 29 (Unit 2)

~-

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

At least once per 18 months or (1) after any structural maintenance c.

on the HEPA filter or activated carbon adsorber housings, or l

(2) following painting, fire, or chemical release in any ventilation zone communicating with the system by:

1)

Verifying that the' cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% (Unit 1), 0.05% (Unit 2) and uses the test pro-cedure guidance in Regulatory Position C.5.a. C.S.c, and C.S.d*

of Regulatory Guide 1.52, Revisions 2, March 1978, and the system flow rate is 6000 cfm i 10%;

2)

Verifying, within 31 days after removal, that a laboratory analysis of a representative activated carbon sample obtained j

in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 1%; and 3)

Verifying a system flow rate of 6000 cfm + 10% during system operation when tested in accordance with XNSI N510-1980.

d.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of activated carbon adsorber operation, by l

verifying, within 31 days after removal, that a laboratory analysis of'a representative activated carbon sample obtained in accordance l

with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Posi-tion C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 1%;

At least once per 18 months by:

e.

1)

Verifying that the pressure drop across the combined HEPA filters, activated carbon adsorber banks, and moisture separators is j,

less than 8 inches Water Gauge while operating the system at a flow rate of 6000 cfm + 10%;

2)

Verifying that on a High Radition-Air Intake, or Smoke Density-High test signal, the system automatically isolates the affected intake from outside air with recirculating flow through the HEPA filters and activated carbon adsorber banks; l

3)

Verifying that the system maintains the control room at a posi-tive pressure of greater than or equal to 1/8 inch Water Gauge relative to adjacent areas at less than or equal to pressuriza-tion flow of 4000 cfm to the control room during system operation; 4)

Verifying that the heaters dissipate 25 1 2.5 kW, and

The requirement for reducing refrigerant concentration to 0.01 ppm may be satisfied by operating the system for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with heaters on and operating.

CATAWBA - UNITS 1 & 2 3/4 7-15 Amendment No. 37 (Unit 1)

Amendment No. 29 (Unit 2)

~

______________[____

i PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 5)

Verifying that on a High Chlorine / Toxic Gas test signal, the system automatically isolates the affected intake from outside air with recirculating flow through the HEPA filters and acti-i vated carbon adsorbers banks within 10 seconds (plus air travel

. time between.the detectors and the. isolation dampers).

f.

After each complete or partial replacement of a HEPA filter bank, by verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% (Unit 1),

0.05% (Unit 2) in accordance with ANSI N510-1980 for a DOP test aero-sol while operating the system at a flow rate of 6000 cfm i 10%; and g.

After each complete or partial replacement of'an activated carbon l

adsorber bank, by verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% (Unit 1), 0.05% (Unit 2) in accordance with ANSI H510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of 6000 cfm i 10%.

l CATAWBA - UNITS 1 & 2 3/4 7-16 Amendment No. 37 (Unit 1)

Amendment No. 29 (Unit 2)

"a

PLANT SYSTEMS 3/4.7.7 AUXILIARY BUILDING FILTERED EXHAUST SYSTEM l

LIMITING CONDITION FOR OPERATION 3.7.7 Two independent trains of the Auxiliary Building Filtered Exhaust System shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With one train of the Auxiliary Building Filtered Exhaust System inoperable, restore the inoperable train to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.7.7 Each train of the Auxiliary Building Filtered Exhaust System shall be demonstrated OPERABLE:

At least once per 31 days by initiating, from the control room, flow a.

through the HEPA filters and activated carbon adsorbers and verifying l

that the system operates for at least 10 continuous hours with the heaters operating; b.

At least once per 18 months or (1) after any structural maintenance on the HEPA filter or activated carbon adsorber housings, or (2) fol-j lowing painting, fire, or chemical release in any ventilation zone communicating with the same by:

1)

Verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% (Unit 1), 0.05% (Unit 2) and uses the test proce-dure guidance in Regulatory Positions C.S.a, C.5.c, and C.S.d*

of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 30,000 cfm i 10%;

2)

Verifying, within 31 days after removal, that a laboratory analysis of a representative activated carbon sample obtained l

in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory test-ing criteria of Regulatory Position C.6 a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetra-tion of less than 1%; and I

The requirement for reducing refrigerant concentration to 0.01 ppm may be i

satisfied by operating the system for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with heaters on and operating.

I CATAWBA - UNITS 1 & 2 3/4 7-17 Amendment No. 37 (Unit 1)

Amendment No. 29 (Unit 2) a

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 3)

Verifying a system flow rate of-30,000 cfm i 10% during system operation when tested in accordance with ANSI N510-1980.

After every 720 bcurs of activated carbon adsorber operation, by j'

c.

verifying, within 31 days after removal, that a laboratory analysis of a representative activated carbon sample obtained in accordance l

with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Posi-tion C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 1%;

d.

At least once per 18 months by:

1)

Verifying that the pressure drop across the combined HEPA filters, activated carbon adsorber banks, and moisture separa-l tors of less than 8 inches Water Gauge while operating the system at a flow rate of 30,000 cfm i 10%,

2)

Verifying that the system starts on a Safety Injection test signal, and directs its exhaust flow through the HEPA filters and activated carbon adsorbers,**

3)

Verifying that the system maintains the ECCS pump room at a negative pressure relative to adjacent areas, 4)

Verifying that the filter cooling bypass valves can be manually opened, and i

5)

Verifying that the heaters dissipate 40 1 4 kW.

I After each complete or partial replacement of a HEPA filter bank, e.

by verifying that the cleanup system satisfies the in place pene-tration and bypass leakage testing acceptance criteria of less than 1% (Unit 1), 0.05% (Unit 2) in accordance with ANSI N510-1980 for a DOP test aerosol while operating the system at a flow rate of 30,000 cfm i 10%; and f.

After each complete or partial replacement of an activated carbon l

adsorber bank, by verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% (Unit 1), 0.05% (Unit 2) in accordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of 50,000 cfm i 10%.

- This surveillance need not be performed until prior to entering HOT SHUTDOWN following the Unit 1 first refueling.

CATAWBA - UNITS l'& 2 3/4 7-18 Amendment No. 37 (Unit 1)

Amendment No. 29 (Unit 2)

19-REFUELING OPERATIONS 3/4.9.3 DECAY TIME LIMITING CONDITION FOR OPERATION 3.9.3 The reactor shall be-subcritical for at least 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

APPLICABILITY: During movement of irradiated fuel in the reactor vessel.

ACTION:

With the reactor subcritical for less than.72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , suspend all operations involving movement of irradiated fuel in the reactor vessel.

C SURVEILLANCE REQUIREMENTS-4.9.3.The react'or shall be' determined to have been subtritical for at least 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months by verification of the date and time of subtriticality prior to movement of irradiated fuel in the reactor vessel.

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

.t.

REFUELING OPERATIONS 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS LIMITING CONDITION FOR OPERATION 3.9.4 The containment building penetrations shall be in the following status:

The equipment hatch closed and held in place by a minimum of four a.

bolts, b.

A minimum of one door in each airlock is closed, and Each penetration providing direct access from the containment c.

atmosphere to the outside atmosphere shall be either:

1)

Closed by an isolation valve, blind flange, or manual valve, or 2)

Exhausting through an OPERABLE Reactor Building Containment Purge System HEPA filters and activated carbon adsorbers.

l APPLICABILITY:

During CORE ALTERATIONS or movement of irradiated fuel within the containment.

ACTION:

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment building.

SURVEILLANCE REQUIREMENTS 4.9.4.1 Each of the above required containment building penetrations shall be determined to be either in its closed / isolated condition or exhausting through an OPERABLE Reactor Building Containment Purge System with the capability of being automatically isolated upon heater failure within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to the start of and at least once per 7 days during CORE ALTERATIONS or movement of irradiated fuel in the containment building by:

Verifying the penetrations are in their closed / isolated condition, a.

or i

b.

Verifying the upper and lower containment purge supply and exhaust valves close upon a High Relative Humidity test signal.

CATAWBA - UNITS 1 & 2 3/4 9-4 Amendment No37 (Unit 1)

Amendment No29 (Unit 2)

z REkJELINGOPERATIONS SURVEILLANT, REQUIREMENTS (Continued)

,1 4.9.4.2 The Reactor Building Containment Purge Syst& shall be demonstrated OPERABLE-

\\

At least once per 31 days by initiating flow through the HEPA filte s a.

and activated carbon adsorbers and veritying that the system operates

'i l

for at least 10' continuous hours with the henters operating;

]

b.

At least once per 18 months or (1) sfter any structural maint.fmte on thel IEPA filter or activated carbon adsorber housings, or l

(2) following painting, fire, or c?.enical release in any venthatb zone communicating with the system by 1)

Verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% and uses the test procedures guidance in Regula-g tory Positions C.S.a, C.S.c, and C.F.d* of Regulatory Guide 1.52, Revision 2, Marct; 1978, and the system flow rate is 26,000 cfm m

i 10% (both exhaust fans operating);

2)

Verifying within 31 days afttr rucha, tLat a laboratory v

analysis of a representative activald carbon sample obtaned

[

in accordance yith Regulatory Por/ tion C.6.b of Regulatory Guide 1.52, Redision 2, March 1976, ceets the laboratory testing criteria of Regulatory Position C.6.

of frgulatory Guide '1.."2, Revision 2, March 1978, for a methyl m dide penetratim of,i ni than 6%; and 3)

Verifying a system flow r m of 25,000 cfm i 10% (both exhaust fans operating) during system operation when tested in accordaace with ANSI N510-1980.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of activated carbon adsorber operation, by j

c.

verifying, within 31 days after removal, that1.' laboratory analysj s

..[

J

~

of a representative activated carbon sample ob W ned in accordanct with Regulatory Position C.6.b of Regulator.r GuMe 1.52, Revision i March 1978, meets the laborator, testing criteria of Regulatory Post tion C.6.a of Regulatery Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration 0: less than 6%;

d.

At least once per 18 months by:

1)

Verifying that the pressure drop across tu combined hEPA f'l-ters, activated carbon adsorber barks, and prefilters is less I

than 8 inches Water Gauge while operating tLe systet n a fl w rate of 25,000 cfm i 10% (both exhaJst f6n5FJperatinQ); SDd

The requirement fcr reducing refrigerant concentration to 0.01 ppm may be wtir;fied by operating the system for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months w'th heaters on and operating.

CATAWBA UNITS 1 & 2 3/4 9-5 Amendment No.37 (Unit 1)

Amendment No.29(Unit 2) s

_ _ _ _. _ _ _ _ _ _. _ _ _ _ _ _ _ _ - - - - - - - - - - - - - - - - - - - - - - - ' - ' - - - - ~ - ' - - ' ' - ^ ^ - - ^ - - ^ -

- ~ ' - ' -

5; nc o,

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.g) y:(.

s

? Q-

,I/

i t

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,]'

~

REFUELING CPERATIONS SURVEILLANCE REQUIREMENTS (Continued) 2)-

Verifying that.the filter train duct-heater dissipates 120 i 12 kW.

AftereachcompIeteOEpartialreplacementofaREPAfilterbank,by e.-

verifying that.the cleanup system satisfies-the in p?aca penetration and bypass leakage testing acceptance criteria of less than 1% in accordance with ANSI N510-1980 for a DOP. test. aerosol-while operating

',,[b, the system at a flow rate ofi25,000,cfm i 10% (beth, exhaust fans

-operating); and 4

e a'

y.

+

f.

After each complete or partial: replacement oflan actisated carbon

'l adsorber bank, by verifying that the cleanap sr.: tem bank satisfies the in place penetration and bypass leakags f.esting acceptance cri-

.teria of less than 1%'in accordance with ANSI N510-1980 for a halo-genated hydrocarbon refrigerant test gas while operating the system atafloyrateof25,000cfm1.10%(bothexhaustfansoperating),

t,

)

s g

P

n..V 3

i t

CATAWBA - UNITS 1 & 2 3/4 9-6 Amercent No. 37(Unit V Amendment No. 29(Unit f)

REFUELING OPERATIO'NS 3/4.9.10 WATER LEVEL-STORAGE POOL j

LIMITING CONDITION FOR OPERATION 3.9.10 'At least 23 feet.of water shall.be maintained over the top of irradiated fuel assemblies seated in the storage racks.

APPLICABILITY:

Whenever irradiated fuel assemblies are in the storage pocl.

ACTION:

With the requirements of the above specification not satisfied, a.

suspend all movement of fuel assemblies and crane operations with loads in the fuel storage areas and restore the water' level to within its limit within 4 hoors, b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

L SURVEILLANCE REQUIREMENTS i ;-

4.9.10 The water level in the storage pool. shall be determined to be at least its minimun, required depth at least once per 7 days when irradiated fuel 5

assemblies are in the fuel storage pool.

l CATAWBA - UNITS 1 & 2 3/4 9-13

^

REFUELING OPERATIONS 3/4.9.11 FUEL HANDLING VENTILATION EXHAUST SYSTEM LIMITING CONDITION FOR OPERATION 3.9.11 At least one train of the Fuel Handling Ventilation Exhaust System i

shall be OPERABLE.

APPLICABILITY:

Whenever irradiated fuel is in the storage pool.

ACTION:

With both trains of the Fuel Handling Ventilation Exhaust System a.

inoperable, suspend all operations involving movement of fuel within the storage pool or crane operation with loads over the storage pool until the Fuel Handling Ventilation Exhaust System is restored to OPERABLE status.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.11.1 One train of the Fuel Handling Ventilation Exhaust System shall be determined to be operating and discharging through the HEPA filter and acti-vated carbon adsorbers at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months whenever irradiated fuel is being moved in the storage pool and during crane operation with loads over the storage pool.

4.9.11.2 Both trains of the Fuel Handling Ventilation Exhaust System shall be demonstrated OPERABLE:

At least once per 31 days by initiating, from the control room, a.

flow through the HEPA filters and activated carbon adsorbers and l

verifying that the system operates for at least 10 continuous hours with the heaters operating; b.

At least once per 18 months or (1) af ter any structural maintenance on the HEPA filter or activated carbon adsorber housings, or (2) fol-l lowing painting, fire, or chemical release in any ventilation zone communicating with the system by:

1)

Verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% (Unit 1), 0.05% (Unit 2) and uses the test procedure guidance in Regulatory Positions C.5.a. C.5.c, and C.S.d* of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 16,565 cfm i Il%;

The requirement for reducing refrigerant concentration to 0.01 ppm may be satisfied by operating the system for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with heaters on and operating.

CATAWBA - UNITS 1 & 2 3/4 9-13 Amendment No.37(Unit 1)

Amendment No.2o(Unit 2) o

REFUELING ODERATIONS SURVEILLANCE REQUIREMENTS (Continued) 2)

Verifying, within 31 days after removal, that a laboratory analysis of a representative activated carbon sample obtained l

in accordance with Regulatory Positions C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 1%; and 3)

Verifying a system flow rate of 16,565 cfm i 10% during system operation when tested in accordance with ANSI N510-1980.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of activated carbon adsorber operation in any l

c.

train by verifying, within 31 days after removal, that a laboratory analysis of a representative activated carbon sample obtained in l

accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 1%.

d.

At least once per 18 months for each train by:

1)

Verifying that the pressure drop across the combined HEPA filters, activated carbon adsorber banks, and moisture separators is less l

than 8 inches Water Gauge while operating the system at a flow rate of 16,565 cfm i 10%.

2)

Verifying that the system maintains the spent fuel storage pool area at a negative pressure of greater than or equal to % inch Water Gauge relative to the outside amosphere during system operation, 3)

Verifying that the filter cooling bypass valves can be manually opened, and 4)

Verifying that the heaters dissipate 80 1 8 kW.

e.

After each complete or partial replacement of a HEPA f1 ster bank in any train, by verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% (Unit 1), 0.05% (Unit 2) in accordance with ANSI N510-1980 for a D0P test aerosol while operating the system at a flow rate of 16,565 cfm i 10%; and f.

After each complete or partial replacement of an activated carbon l

adsorber bank in any train, by verifying that the cleanup system satisfies the in place penetration and bypass leakage testing accept-ance criteria of less than 1% (Unit 1), 0.05% (Unit 2) in accordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of 16,565 cfm i 10%.

CATAWBA - UNITS 1 & 2 3/4 9-15 Amendment No.37(Unit 1)

Amendment No.29(Unit 2)

(

TABLE 4jl-1(Continued)

TABLE NOTATIONS (1)The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

4. 6 s LLD =

b E

V 2.22 x 106 Y

exp (-Aat) l Where:

LLD = the "a priori" lower' limit of detection (microcurie per unit mass or volume),

p = the standard deviation of the background counting rate or of s

the counting rate of a blank sample as appropriate (counts per minute),.

E = the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

2.22 x 108 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclides (sec 1), and

-f At = the elapsed time between the midpoint of sample collection and the time of counting (sec).

l Typical values of E, V, Y, and at should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

(2)A batch release is the discharge of liquid wastes of a discrete volume.

Prior to sampling for analyses, each batch shall be isolated, and then' thoroughly mixed to assure representative sampling.

CATAWBA - UNITS 1 & 2 3/4 11-3 Amendment No. 37 (Unit 1)

Amendment No 29 (Unit 2)

i TABLE 4.11-1 (Continued)

TABLE NOTATIONS (Continued)

F

.(3)The principal gamma emitters for which the LLD specification applies include the following radionuclides: Mn-54, Fe-59,.Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137 and Ce-141 The LLD for Ce 144 is 5 x 10 6 pCi/ml.

This list does not mean that only these nuclides are to be considered.

Other gamma peaks that are identifiable, together with those of the above nuc-lides, shall also be analyzed and reported in the Semiannual Radioactive

~ Effluent Release Report pursuant to Specification 6.9.1.7 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1,' June 1974.

(4)A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which_the method of sampling employed results in a specimen that is representative of the liquids released.

(5)A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.

(6)To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream.

Prior to analyses',

all samples taken for the composite shall be~ thoroughly mixed in order for the composite sample to be representative of the effluent release.

r l i r

k j i

l CATAWBA - UNITS 1 &'2 3/4 11-4

~

e

(

l.

RADI0ACTfVE EFFLUENTS L

LIQUID HOLDUP TANKS

. LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each t'emporary 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.

A_CTION:

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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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 Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.4 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 CATAWBA - UNITS 1 & 2 3/4 11-7

RADI0 ACTIVE EFFLUENTS CHEMICAL TREATMENT PONDS LIMITING CONDITION FOR OPERATION 3.11.1.5 The quantity of radioactive material contained in each chemical treatment pond shall be limited by the following expression:

A 264

< 1.0 excluding tritium and dissolved or entrained noble gases, Where:

Aj = pond inventory limit for single radionuclides "j", in Curies; C. = 10 CFR Part 20, Appendix B, Table II, Column 2, concentration for 3

single radionuclides "j", microCuries/ml; V

= design volume of liquid and slurry in the pond, in gallons; and 264 = conversion unit, microCuries/ Curie per milliliter / gallon.

APPLICABILITY:

At all times.

ACTION:

With the quantity of radioactive material in any of the above listed a.

ponds exceeding the above limit, immediately suspend all additions i

of radioactive material to the pond and initiate corrective action to reduce the contents to within the limit.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS

.l 4.11.1.5 The quantity of radioactive material contained in each batch of resin / water slurry to be transferred to the chemical treatment ponds shall be determined to be within the above limit by analyzing a representative sample of the batch to be transferred to the chemical treatment ponds and shall be l

limited by the expression:

l

)

c.

i I J<

0.006 j C 3

Where:

c) = radioactive resin / water slurry concentration for radionuclides "j" entering the UNRESTRICTED AREA chemical treatment ponds, in microcuries/ milliliter; and

)

C. = 10 CFR Part 20, Appendix B, Table II, Column 2, concentration for 3

single radionuclides "j", in microcuries/ milliliter.

CATAWBA - UNITS 1 & 2 3/4 11-8 Amendment No. 37 (Unit 1)

Amendment No. 29 (Unit 2)

E-________

i

L TABLE 4.11-2 (Continued)

TABLE NOTATIONS (1). The,LLD-is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation

)

represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

4' LLD =

b E

V' 2.22 x 106 Y

exp (-AAt)

Where:

I LLD = the "a priori" lower limit of detection (microcurie per unit l

mass or volume),

i b = the standard deviation of the background counting rate or of s

the counting rate of a blank sample as appropriate.

(counts per minute),

E ': the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

2.22 x 108 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclides (sec 1), and l'

At = the elapsed time between the midpoint of sample collection and the time of counting (sec).

l Typical values of E, V, Y, and At should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

CATAWBA - UNITS 1 & 2 3/4 11-11 Amendment No. 37 (Unit 1)

Amendment No. 29 (Unit 2)

TABLE 4.11-2 (Continued)

TABLE NOTATIONS (Continued) p (2) The principal gamma emitters for which the LLD specification applies include the following radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58','Co-60, 2n-65, Mo-99, I-131, Cs-134, Cs-137, and Ce-141 in Iodine and particulate releases. The LLD for Ce-144 is 5x10 8 pCi/ml.

This list does not mean that only these nuclides are to be considered.

Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be anal-yzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.7 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

(3) Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER stabilization (power level constant at desired power level) after a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period, for at.least one of the three gaseous release types with this notation.

1 (4) Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.

(5) Required sampling and analysis frequency during effluent release via this i

pathway.

l (6) The ratio of the sample flow volume to the sampled stream flow volume shall

[

l I

be known for the time period covered by each dose or dose rate calculation V

made in'accordance with Specifications 3.11.2.1, 3.11.2.2, and 3.11.2.3.

f (7) Samples shall_be changed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and analyses shall be completed within 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months after changing, or after removal from sampler.

(8) The composite filter (s) will be analyzed for alpha activity by analyzing one filter per week to ensure that at least four filters are analyzed per collection period.

I i

1 k

CATAWBA - UNITS 1 & 2 3/4 11-12 L_____--_____-_

-3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The Radiological Environmental Monitoring Program shall be conducted as specified in Table 3.12-1.

APPLICABILITY:

At all times.

ACTION:

With the Radiological Environmental Monitoring Program not being a.

conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Specification 6.9.1.6, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence, b.

With the level of radioactivity as the result of plant effluents in an environneental sampling medium at a specified location exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual t.

dose

to a MEMBER OF THE PUBLIC is less than the calendar year limits of Specification 3.11.1.2, 3.11.2.2, or 3.11.2.3.

When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) concentration (2)

+

...), 1. 0 reporting level (1), reporting level (2) 5 When radionuclides other than those in Table 3.12-2 are detected and' are the result of plant effluents, this report shall be submitted if the potential annual dose

to A MEMBER OF THE PUBLIC from all radio-nuclides is equal to or greater than the calendar year limits of Specification 3.11.1.2, 3.11.2.2, or 3.11.2.3.

Tnic report is not required if the measured level of radioactivity was not the result of plant effluents;.however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Specification 6.9.1.6.

l

The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

CATAWBA - UNITS 1 & 2 3/4 12-1 L __

_-_-_ L _

RADIOLOGICAL ENVIRONMENTAL MONITORING LIMITING CONDITION FOR OPERATION ACTION' (Continued)

With milk or fresh leafy vegetation sample's unavailable from one or l.

c.

more of the sample locations required by Table 3.12-1, identify specific locations for: obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitor.ing Program.

given'in the ODCM.

The specific locations from which samples werei unavailable may then be deleted from the monitoring program.

Pursuant to Specification 6.14, submit in the next Semiannual Radioactive Effluent Release Re a revised figure (s) port documentation for a change in the ODCM including and table for the ODCM reflecting the new loca-

. tion (s) with supporting information identifying the'cause'of the unavailability of samples and justifying the selection of the new location (s) for obtaining samples, d.

-The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE-REQUIREMENTS 4.12.1 The radiological environmental monitoring. samples shall be collected pursuant to Table 3.12-1 from the specific locations given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilities required by Table 4.12-1.

CATAWBA - UNITS 1 & 2 3/4 12-2 Amendment No. 37 (Unit 1)

Amendment No. 29 (Unit 2)

CL1__ _1-

g..

TABLE 4.12-1 (Continued)

TABLE NOTATIONS (1) This list does not mean that only these nuclides are to be considered.

Other peaks that are identifiable, together with those.of the above nuclides, shall also be analyzed and reported in the Annual Radiol.ogical Environmental Operating Report pursuant to Specification 6.9.1.6.

(2) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommenda-tions of Regulatory Guide 4.13.

(3) The LLD is defined, for purposes of these specifications, as the smallest concentrations of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

4*

b LLD =

E V

2.22 Y

exp(- AAt)

Where:

LLD = the "a priori" lower limit of detection (picoCuries per unit mass or volume),

l b

= the standard deviation of the background counting rate or of the s

counting rate of a blank sample as appropriate (counts per minute),

E

= the counting efficiency (counts per disintegration),

V

= the sample size (units of mass or volume),

2.22 = the number of disintegrations per minute per picocurie, Y

= the fractional radiochemical yield, when applicable, A

=.the radioactive decay constant for the particular radionuclides (sec 1), and l

At the elapsed time between environmental collection, or end of the sample collection period, and time of counting (sec).

l Typical values of E, V, Y and at should be used in the calculation.

CATAWBA - UNITS 1 & 2 3/4 12-11 Amendment No. 37 (Unit 1)

Amendment No. 29 (Unit 2)

_:__ :_=_ _ __2 _ _ _

I TABLE 4.12-1 (Continued)

F TABLE NOTATIONS (Continued).

It should be recognized'that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement' system and not as

-an a posteriori-(after the fact) limit for a particular measurement.

Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions.. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable..

In such cases, the contributing factors shall.be identified and described in the Annual-Radiological Environmental Operating Report pursuant to.

Specification 6.9.1.6.

(4) 'LLD for drinking water samples.

If no drinking water pathway exists, the LLD of gamma isotopic analysi's may be used.

I

{

i I

CATAWBA - UNITS 1 & 2 3/4 12-12

CONTAINMENT SYSTEMS BASES 3/4.6.1.8 ANNULUS VENTILATION SYSTEM The OPERABILITY of the Annulus Ventilation System ensures that during LOCA conditions, containment. vessel leakage into the annulus will be filtered through the HEPA filters and activated carbon adsorber trains prior to discharge to the l

atmosphere.

Operation of the system with the heaters operating to maintain low humidity using automatic. control for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.

This requirement is necessary to meet the assumptions used in the safety analyses and limit the SITE BOUNDARY radiation doses to within the dose guide-1 line values of 10 CFR Part 100 during LOCA conditions.

ANSI N510-1980 will be used as a procedural guide for surveillance testing.

3/4.6.1.9 CONTAINMENT PURGE SYSTEMS The containment purge supply and exhaust isolation valves for the lower compartment and the upper compartment (24-inch), and instrument room (12-inch),

and the Hydrogen Purge System (4-inch) are required to be sealed closed during plant operation since these valves have not been demonstrated capable of closing during a LOCA.

Maintaining these valves sealed closed during plant operations ensures that excessive quantities of radioactive materials will not be released via the Containment Purge System.

To provide assurance that these containment valves cannot he inadvertently opened, the valves are sealed closed in accord-ance with Standard Review Plan 6.2.4 which includes mechanical devices to seal or lock the valve closed, or prevents power from being supplied to the valve operator.

The use of the containment purge lines is restricted to the 4-inch Con-tainment Air Release and Addition System valves since, unlike the lower compart-ment and the upper compartment, instrument room, and the Hydrogen Purge System

~

valves, these 4-inch valves are capable of closing during a LOCA.

Therefore, the SITE BOUNDARY dose guideline values of 10 CFR Part 100 would not be exceeded in the event of an accident during containment purging operation.

Operation with the line open will be limited to 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months during a calendar year for the 4-inch valves.

The total time the containment purge (vent) system isolation valves may be open during MODES 1, 2, 3, and 4 in a calendar year is a function of anticipated need and operating experience.

Only safety-related reasons; e.g., containment pressure control or the reduction of airborne radioactivity to facilitate personnel access for surveillance and maintenance activities, may be used to support the additional time requests.

i Leakage integrity tests with a maximum allowable leakage rate for contain-4 ment purge supply and exhaust valves will provide early indication of resilient material seal degradation and will allow opportunity for repair before gross leakage failures could develop. The 0.60 L, leakage limit of Specification 3.6.1.2b. shall not be exceeded when the leakage rates determined by the leakage integrity tests of these valves are added to the previously determined total for all valves and penetrations subject to Type B and C tests.

CATAWBA - UNITS 1 & 2 B 3/4 6-3 Amendment No. 37 (Unit 1)

Amendment No. 29 (Unit 2)

CONTAINMENT SYSTEMS BASES-l 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS j

The OPERABILITY of the Containment Spray System ensures that containment depressurization and cooling capability will be available in the event of a LOCA.

The pressure reduction and resultant lower containment leakage rate are consistent with the. assumptions used in the safety analyses.

However, the Containment Spray System also provides a mechanism for removing iodine from the containment atmosphere, and therefore the time requirements for restoring an inoperable Spray System to OPERABLE status have been maintained consistent with those assigned other inoperable ESF equipment.

[

3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment and is consistent with the requirements of GDC 54 throu'gh 57 of Appendix A to 10 CFR Part 50.

Containment isolation within the time limits specified for those isolation valves designed to close auto-matically ensures.that the release of radioactive material to the environ-ment will be consistent with the assumptions used in the analyses for a LOCA.

3/4.6.4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the equipment and systems required for the detection f

and control of hydrogen gas ensures that this equipment will be available to r

I maintein the hydrogen concentration within containment below its flammable l

limit during post-LOCA conditions.

Either recombiner unit is capable of

_ controlling the expected hydrogen generation associated with:

(1) zirconium-water reactions, (2) radiolytic decomposition of water, and (3) corrosion of metals within containment.

These Hydrogen Control Systems are consistent with the recommendations of Regulatory Guide 1.7, " Control of Combustible Gas Concentrations Following a LOCA," March 1971.

The OPERABILITY of at least 35 to 36 igniters per t.in (70 of 72 for both trains) ensures that the Distributed Ignition System wil aaintain an effective coverage throughout the containment provided the two inoperable ignitors are not on corresponding redundant circuits which provide coverage for the same region.

This system of igniters will initiate combustion of any significant amount of hydrogen released after a degraded core accident.

This system is to ensure burning in a controlled manner as the hydrogen is released instead of allowing it to be ignited at high concentrations by a random ignition source.

s CATAWBA - UNITS 1 & 2 B 3/4 6-4

3/4.9 REFUELING OPERATIONS o

BASES 3/4.9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that:

(1) the reactor will remain subcritical during CORE ALTERATIONS, and (2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel.

These limitations are consistent with the initial conditions assumed for the boron dilution incident in the safety analyses.

The value of 0.95 or less for K includes a eff 1% ok/k conservative allowance for uncertainties.

Similarly, the boron concentration value of 2000 ppm or greater includes a conservative uncertainty allowance of 50 ppm boron.

The locking closed of the required valves during refueling operation precludes the possibility of uncontrolled boron dilution of the filled portion of the Reactor Coolant System.

This action prevents flow to the Reactor Coolant System of unborated water by closing flow paths from sources of unborated water.

3/4.9.2 INSTRUMENTATION The OPERABILITY of the Source Range Neutron Flux Monitors and/or the Boron D11ution Mitigation System ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.

3/4.9.3 DECAY TIME The minimum requirement for reactor suberiticality prior to movement of irradiated fuel assemblies in the reactor vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short-lived fission products.

This decay time is consistent with the assumptions used in the safety analyses.

~

3/4.9.4 CONTAINMENT BUILDING PENETRATIONS The requirements on containment building penetration closure and OPERABILITY of the Reactor Building Containment Purge System ensure that a release of radioactive material within containment will be restricted from leakage to the environment or filtered through the HEPA filters and activated carbon adsorbers l

prior to release to the atmosphere.

The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE.

Operation of the Reactor Building Containment Purge System and the resulting iodine removal capacity are consistent with the assumption of the safety analysis.

Operation of the system with the heaters operating to maintain low humidity using automatic control for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.

ANSI N510-1980 will be used as a procedural guide for surveillance testing.

CATAWBA - UNITS 1 & 2 B 3/4~9-1 Amendment No.37 (Unit 1)

Amendment No.29 (Unit 2)

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REFUELING OPERATIONS BASES 3/4.9.9 and 3/4.9.10 WATER LEVEL - REACTOR VESSEL and STORAGE POOL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly.

The minimum water depth is consistent with the assumptions of the safety analysis.

3/4.9.11 FUEL HANDLING VENTILATION EXHAUST SYSTEM The limitations on the Fuel Handling Ventilation Exhaust System ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and activated carbon adsorber prior to l

discharge to the atmosphere.

Operation of the system with the heaters operat-ing to maintain low humidity using automatic control for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.

The OPERABILITY of this system and the result-ing iodine removal capacity are consistent with the assumptions of the safety analyses.

ANSI N510-1980 will be used as a procedural guide for surveillance testing.

CATAWBA - UNITS 1 & 2 B 3/4 9-3 Amendment No. 37 (Unit 1)

Amendment No. 29 (Unit 2)

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TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION POSITION NUMBER OF INDIVIDUALS REQUIRED T0. FILL POSITION Both Units in One Unit in Mode 1, 2, 3 or 4 Both Units in Mode 5 or 6 and Mode 1, 2, 3 or 4 or Defueled One Unit in Mode 5 or 6 Defueled SS

'l 1

1 SR0 1

None##

1 R0 3#

2#

3#

NE0 3#

3#

STA 1

None 1

SS Shift Supervisor with a Senior Operator license SRO Individual with a Senior Operator license RO Individual with an Operator license NEO Nuclear Equipment Operator STA Shift Technical Advisor The Shift Crew Composition may be one less than the minimum requirements of Table 6.2-1 for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table-6.2-1.

This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.

During any absence of the Shift Supervisor from the control room while the unit is in MODE 1, 2, 3, or 4, an individual (other than the Shift Technical Advisor *) with a valid Senior Operator license shall be designated to assume

.the control room command function.

During any absence of the Shift Supervisor from the control room while the unit is in MODE 5 or 6, an individual with a valid Senior Operator license or Operator license shall be designated to assume the control room command function.

0n occasion when there is a need for both the Shift Supervisor and the SR0 to be absent from the control room, the STA shall be allowed to assume the control room command function and serve as the SR0 in the control room

_ provided that:

(1) the Shift Supervisor is available to return to the control room within 10 minutes, (2) the assumption of SRO duties by the STA be limited to periods not in excess of 15 minutes duration and a total time not to exceed I hour during any shift, and (3) the STA has a Senior Operator l

license on the unit.

At least one of the required individuals must be assigned to the designated position for each unit.

1. At least one licensed Senior Operator or licensed Senior Ope'rator Limited to Fuel Handling must be present during CORE ALTERATIONS on either unit, who has no other concurrent responsibilities.

CATAWBA - UNITS 1 & 2 6-5 Amendment No. 37 Amendment No. 29 (Unit 1)

(Unit 2)

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ML20237C799

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