ML20154R455

Amends 45 & 38 to Licenses NPF-35 & NPF-52,respectively, Modifying Tech Specs to Cover Operation of Sys & Components Associated W/Monitor Tank Bldg

ML20154R455
Person / Time
Site:	Catawba
Issue date:	05/27/1988
From:	Matthews D Office of Nuclear Reactor Regulation
To:
Shared Package
ML20154R461	List: ML20154R455 ML20197D533
References
NUDOCS 8806070308
Download: ML20154R455 (17)

Text

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8 UNITED STATES 8"

NUCLEAR REGULATORY COMMISSION n

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WASHINGTON, D. C. 20555 i

%, * *...,o DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CCPPORATION SALUDA RIVER ELECTRIC COOPERATIVE, INC.

DOCKET NO. 50-413

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CATAWBA NUCLEAR STATION, UNIT 1 AMENDHENT TO FACILITY OPERATING LICENSE Amendment No. 45 1

License No. NPT-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 Corrpany acting for itself, North Carolina Electric Membership) Corporation and Saluda River Electric Cooperative, Inc.,

(licensees dated March 23, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission's rules and regulations as set forth in 10 CFP.

Chapter I; B.

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

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimic61 to the comon 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 1

of the Comission's regulations and all applicable requirements have been satisfied, i

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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 L

amended to read as follows:

(2) Technical Specifications The Technical Specifications contair,ed in Appendix A, as revised through Amendment No. 45, are hereby incorporated into the license.

The licencee shall operate the facility in accordance with the Technica.,,pecifications and the Environmental Protection Plan.

3.

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

4 FOR THE NUCLEAR REGULATORY COMMISSION j

Original signed by:

David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-I/II

Attachment:

Technical Specification Changes i

Date of Issuance: May 27, 1988

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UN11 ED STATES NUCLEAR REGULATORY COMMISSION e

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DUKE POWER COMPANY NORTH CAROLINA NUNICIPAL POWER AGENCY NO. 1 PIEDMONT NUNICIPAL POWER AGENCY DOCKET NO. 50-414 i

CATAWBA NUCLEAR STATION, UNIT 2 APJNDMENTTOFACILITYOPERATINGLICENSE l

i Amendment No. 38 License No. NPF-52 1.

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

A.

The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-52 filed by the i

Duke Power Company acting for itself, North Carolina Municipal Power Tgency No. I and Piedmont Municipal Power Agency, (licensees) dated March 23, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations as set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (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 and safety of the public; and E.

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

2.

Accordingly, the license is 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 Lt. cense No. NPF-52 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 38, 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 REGULATORY COMMISSION Original signed by:

David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-I/II

Attachment:

Technical Specification Changes Date of Issuance: May 27, 1988 0FFICIAL RECORD COPY f1 I/h JJii Mk60Y{'LA:fpI-3PM:PDIT-3 OpgN-. D:PDII-3 t

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ATTACHMENT TO LICENSE AMENDMENT NO. 45 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET N0. 50-413 AND TO LICENSE AMENDHENT N0. 38 FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO. 50-414

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Replace tne 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 Page Overleaf Page 3/4 3-81 3/4 3-82 3/4 3-83 3/4 3-84 3/4 3-87 3/4 3-88 3/4 3-91 3/4 3-92 3/4 11-2 3/4 11-1 3/4 11-10a (new page) 5-5

TABLE 3.3-12 n>

RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS E

OPERABLE ACTION

-4 INSTRUMENT w

1.

Radioactivity Monitors Providing Alarm and Automatic Termination of Release a.

Waste Liquid Discharge Monitor (Low Range - EMF-49) 1 per station 40 b.

Turbine Building Sump Monitor (Low Range - EMF-31) 1 42 c.

Steam Generator Water Sample Monitor (Low Rai.ge - EMF-34) 1 43 R

d.

Monitor Tank Building Liquid Discharge Monitor (EMF-57) 1 per station 40 l T

2.

Continuous Composite Samplers and Sampler Flow Monitor Conventional Waste Water Treatment Line 1 per station 42 3.

Flow Rate Measurement Devices a.

Waste Liquid Effluent Line 1 per station 41 "N

$e b.

Conventional Waste Water Treatment Line 1 per station 41 EE 55 c.

Low Pressure Service Water Minimum Flow Interlock 1 per station 41 55 zz d.

Monitor Tank Building Waste Liquid Effluent Line 1 per station 41 l 1

G2 Ah j

00

TABLE 3.3-12 (Continued)

ACTION STATEMENTS ACTION 40 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 14 days provided that prior to initiating a release:

a.

At least two independent samples are analyzed in ~ cordance with Specification 4.11.1.1.1, and b.

At least two technically qualified members of the facility staff independently verify:

1.

The discharge line valving, and 2.

The manual portion of the computer input for the release rate calculations performed on the computer, or the entire release rate calculations if such calculations are performed manually.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 41 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.

Pump performance curves generated in place may be used to estimate flow.

ACTION 42 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathvay may continue for up to 30 days provided grab samples are analyzed for radioactivity at a lower limit of detection of no more than 10 7 microcurie /ml:

a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcurie / gram DOSE EQUIVALENT I-131, or

b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie / gram DOSE EQUIVALENT I-131.

ACTION 43 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, gaseous effluent releases via the atmospheric vent valves (off-normal mode) may continue pro-vided grab samples of steam generator water are analyzed for radio-activity for up to 30 days at a lower limit of detection of no more than 10 7 microcurie /ml:

a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcurie / gram DOSE EQUIVALENT I-131, or

b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie / gram 00SE EQUIVALENT I-131.

CATAWBA - UNITS 1 & 2 3/4 3-82

TABLE 4.3-8 n3$

RADI0 ACTIVE LIQtjID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

ANALOG CHANNEL c

5 CHANNEL SOURCE CHANNEL OPERATIONAL g

INSTRUMENT CHECK CHECK CALIBRATION TEST w

1.

Radioactivity Monitors Providing 3

Alarm and Automatic Termination m

of Release a.

Waste Liquid Discharge Monitor (Low Range -

D P

R(2)

Q(1).

EMF-49) b.

Turbine Building Sump Monitor (Low Range -

D M

R(2)

Q(1)

EMF-31) m A

c.

Steam Generator Water Sample Monitor D

M R(2)

Q(1) m4 (Low Range - EMF-34) w d.

Monitor Tank Building Liquid Discharge D

P R(2)

Q(1)

Monitor (EMF-57) 2.

Continuous Composite Samplers and Sampler Flow Monitor NN gg Conventional Waste Water Treatment Line 0(3)

N.A.

R N.A.

55 gg 3.

Flow Rate Measurement Devices on a.

Waste Liquid Effluent Line D(3)

N.A.

R N.A.

pp M 6; b.

Conventional Waste Water Treatment Line D(3)

N.A.

R N.A.

i c.

Low Pressure Service Water Minimum Flow D(3)

N.A.

R Q-pp Interlock OU d.

Monitor Tank Building Waste Liquid Effluent D(3)

N.A.

R Q

Line

TABLE 4.3-8 (Continued)

TABLE NOTATIONS (1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exist:

a.

Instrument indicates measured levels above the Alarm / Trip Setpoint, or b.

Circuit failure (Alarm only), or c.

Instrument indicates a downscale failure (Alarm only).

(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (dBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.

These standards shall permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.

CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.

CATAWBA - UNITS 1 & 2 3/4 3-84

TABLE 3.3-13 (Continued) n>{

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 5

MINIMUM CHANNELS E

INSTRUMENT OPERABLE APPLICABILITY ACTION Z

[

5.

Containment Purge System Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release 1

48 (Low Range - EMF-39) 6.

Containment Air Release and Addition System Noble Gas Activity Monitor - Providing 1

45

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Alarm (Low Range - EMF-39) 7.

Monitor Tank Building HVAC T

j a.

Noble Gas Activity Monitor - Providing 1 per station 47 Alarm (EMF-58) b.

Monitor Tank Building Effluent Flow Rate 1 per station 46

+

Measuring Device EE 28 at 28 en 22 bh 55

TABLE 3.3-13 (Contir.ued)

TABLE NOTATIONS At all times except when the isolation valve is closed and locked.

Ouring WASTE GAS HOLDUP SYSTEM operation.

• • • At all times.

ACTION STATEMENTS ACTION 45 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment for up to 14 days provided that prior to initiating the release either:

a.

Vent system noble gas activity monitor providing alarm and automatic termination of release (Low Range - EMF-36) has at least one channel OPERABLE, or b.

At least two independent samples of the tank's contents are analyzed, and at least two technically qualified members of the facility staff independently verify:

1.

The discharge valve lineup, and 2.

The manual portion of the computer input for the release rate calculations performed on the computer, or the entire release rate calcula-tions if such calculations are performed manually.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 46 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 47 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERA 8LE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 48 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway.

1 CATAWBA - UNITS 1 & 2 3/4 3-88

TABLE 4.3-9 (Continued) c3 D

jg RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG CHANNEL MODES FOR WHICH c:

55

, CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE g;

INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED,

[^

4.

Vent System (Continued) m

c..' articulate Sampler (EMF-35)

W N.A.

N.A.

N.A.

d. Flow Rate Monitor D

N.A.

R N.A.

e. Sampler Flow Rate Monitor D

N.A.

R N.A.

5.

Containment Purge System 1

Noble Gas Activity Monitor -

,,j, Providing Alarm and Automatic s'

Termination of Release D

P R(3)

Q(1)

(Low Range - EMF-39) 6.

Containment Air Release and Addition System gf jp Noble Gas Activity Monitor-D P

R(3)

Q(1) gg Providing Alarm pyg (Low Range - EMF-39) r* r+

7.

Monitor Tank Building HVAC zz

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a.

Noble Gas Activity Monitor -

D M

R(3)

Q(2)

M$

Providing Alarm (EMF-58) jfjf b.

Discharge Flow Instrumentation D

N.A.

R N.A.

SC

TABLE 4.3-9 (Continued)

TABLE NOTATIONS At all times except when the solation valve is closed and locked.

During WASTE GAS HOLOUP SYSTEF operation.

At all times.

(1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:

a.

Instrument indicates measured levels above the Alarm / Trip Setpoint, or b.

Circuit failure (Alarm only), or c.

Instrument indicates a downscale failure (Alarm only).

(2) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annuciation occurs if any of the following conditions exists:

j a.

Instrument indicates measured levels above the Alarm Setpoint, or b.

Circuit failure, or c.

Instrument indicates a downscale failurt.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.

These standards shall permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(4) The CHANNEL CALIBRATION shall include the use of standard gas samples in accordance with the manufacturer's recommendations.

In addition, a standard gas sample of nominal four volume percent hydrogen, balance nitrogen, shall be used in the calibration to check linearity of the hydrogen analyzer.

(5) The CHANNEL CALIBRATION shall include the use of standard gas samples in accordance with the manufacturer's recommendations.

In addition, a standard gas sample of nominal four percent oxygen, balance nitrogen, shall be used in the calibration to check linearity of the oxygen analyzer.

CATAWBA - UNITS 1 & 2 3/4 3-92

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3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Fioure 5.1-3) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides

-other than dissolved or entrained noble gases.

For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10 4 microcurie /ml total activity.

APPLICABILITY:

At all times.

ACTION:

With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concen-tration to within the above limits.

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-1.

4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the 00CM to assure that the concentrations at the point of release are maintained within the limits of Specification 3.11.1.1.

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

j TABLE 4.11-1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT MINIMUM 0F DETECTION LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)(1)

TYPE FREQUENCY FREQUENCY ANALYSIS (pCi/ml) 1.

Batch Waste P

P Release Each Batch Each Batch Principal Gamma 5x10 7 Tanks (2)

Emitters (3)

I-131 1x10 6 Any tank which discharges P

M Dissolved and 1x10

• liquid wastes One Batch /M Entrained Gases by either liquid (Gamma Emitters) effluent moni-tor, EMF-49 or P

M H-3 1x10 6 EMF-58 Each Batch Composite (4)

Gross Alpha 1x10 7 i

P Q

Sr-89, Sr-90 5x10 8 Each Batch Composite (4)

Fe-55 1x10 8 2.

Continuous W

Principal Gamma 5x10 7 Releases (5)

ontinuous(6)

Composite (6)

Emitters (3)

I-131 1x10 8 Conventional Waste Water M

M Dissolved and 1x10 6 Treatment Grab Sample Entrained Gases Line (Gamma Emitters)

M H-3 1x10 5 Continuous (6) Composite (6)

Gross Alpha 1x10 7 9

Sr-89, Sr-90 5x10 8 Continuous (6) Composite (6) j Fe-55 1x10.s CATAWBA - UNITS 1 & 2 3/4 11-2 Amendment No. 45 (Unit 1)

Amendment No. 38 (Unit 2)

Table 4.11-2 (Continued)

O RADIOACTIVE CASEOUS WASTE SMfPLING AND ANALYSIS PROGRAM g>

MINIMUM DETECTION (LLO){1)

LOWER LIMIT 0 SAMPLING ANALYSIS TYPE OF GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS

.(pCi/ml) g Principal Gamma Emitters (2) 1 x 10 4 h

6.

Waste Monitor W

W Tank Building Grab Sample g

Ventilation H-3 (oxide) 1 x 10 8 p.

Exhaust m

W I-131 1 x 10 11 Continuous (6)

Charcoal Sample I-133 1 x 10 9 W

Continuous (6)

Particulate Principal Gamma Emitters (2) 1 x 10 10 w

Sample 1

I 1

4 Continuous (6)

Composite Par-Gross Alpha 1 x 10 11 g

ticulate Sample Continuous (6)

Com osite Par-Sr-89, Sr-90 1 x 10 11 ticulate Sample EE ei en U. O 22 Ah SC

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SITE BOUNDARY /

'I PERIMETER FENCE NSW

'OAM L

NUCLEAR SERVICE WATER POND

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EXCLUSION 2500 FT. R.

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BOUNDARY tu INTAKE STRUCTURE MONITOR TANK BUILDING (GASE0US RELEASE POINT)

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REACTOR STATION VENTS BLOGS.

(GASE0US RELEASE POINTS EL. 718.75)

SWITCH 4

y YARD BLDG.

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TRAINING

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TOWER

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YAR DISCHARG STRUCTURE (LIQUID RELEASE POINT)

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l FIGURE 5-1-4 UNRESTRICTED AREA AND SITE BOUNDARY FOR RADI0 ACTIVE GASEOUS EFFLUENTS CATAWBA - UNITS 1 AND 2 5-5 Amendment No. 45 (Unit 1)

Amendment No. 38 (Unit 2)

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