Text

Amends 105 & 86 to Licenses DPR-53 & DPR-69,respectively, Issuing Final Part of Radiological Effluent Tech Specs & Deleting ETS
	ML20129E769
Person / Time
Site:	Calvert Cliffs
Issue date:	07/01/1985
From:	Butcher E; Office of Nuclear Reactor Regulation
To:	;
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ML20129E776	List: ML20129E769;
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	NUDOCS 8507170067
	Download: ML20129E769 (146)
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UNITED STATES

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NUCLEAR REGULATORY COMMISSION 5

j WASHINGTON, D C. 20555

/

BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.105 License No. DPR-53 1.

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

A.

The application for amendment by Baltimore Gas & Electric Company (the licensee) dated October 11, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

8507170067 850701 DR ADOCK 050 7

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-53 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.105, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective July 1, 1985.

FOR THE NUCLEAR REGULATORY COMMISSION 3

~c Edward J. Batcher, Acting Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

July 1, 1985

ATTACHMENT TO LICENSE AMENDMENT NO.105 FACILTIY OPERATING LICENSE NO. DPR-53 DOCKET N0. 50-317 Replace the following pages of the 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. overleaf pages are provided to maintain document completeness.

Appendix A Remove Pages Insert Pages IV IV VIIIa VIIIa XIII XIII XV XV XVI XVI 3/4 3-48 through 3/4 3-57 3/4 11-1 through 3/4 11-17 3/4 12-1 3/4 12-1 3/4 12-2 3/4 12-2 3/4 12-6 3/4 12-6 3/4 12-10 3/4 12-10 3/4 12-11 3/4 12-11 3/4 12-12 3/4 12-12 3/4 12-13 3/4 12-13 B 3/4 3-4 B 3/4 11-1 through B 3/4 11-6 6-7 6-7 6-11 6-11 6-12 (no change-repositioned) 6-12 (no change-repositioned) 6-13 6-13 6-16 6-16 6-17 6-17 6-18 6-18 6-18a 6-23 6-23 6-24 6-24 Appendix B Remove Appendix B in its entirety.

Insert the title page attached herewith.

~1NDE X LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLI C AB I L ITY...........................................,3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL Shutdown Margin - T,yg > 200*F.......................

3/4 1-1 3/4 1-3 Shutdown Margin - T,yg < 200*F.......................

B o ron D i l u t i o n...................................... 3/4 1-4 Moderator Temperature Coefficient................... 3/41-5 Minimum Temperature for Criticality..................

3/4 1-7 3/4.1.2 B0 RATION SYSTEMS Flow Paths - Shutdown................................

3/4 1-8 Flow Paths - Operating...............................

3/4 1-9 Charging Pump - Shutdown.............................

3/4 1-10 C ha rg i ng Pu mp s - Opera t i n g........................... 3/4 1-11 Boric Acid Pumps - Shutdown..........................

3/4 1-12 Boric Acid Pumps - Operating.........................

3/41-139 Borated Water Sources - Shutdown..................... 3/4 1-14 Borated Water Sources - Operating....................

3/4 1-16

.p.

3/4.1.3 MOVABLE CONTROL ASSEMBLIES Full Length CEA Position.............................

3/4 1-17 Position Indicator Channels..........................

3/4 1-21 CEA Drop Time........................................

3/4 1-23 Shutdown CEA Insertion Limits........................

3/4 1-24 Regul ating CEA Insertion Limits...................... 3/4 1-25 CALVERT CLIFFS - UNIT 1 III Amendment No. 32 O

__y

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 L I N EA R H EAT RAT E...................................... 3/ 4 2 - 1

~

3/4.2.2 TOTAL PLANAR RADI AL PEAKING FACT 0R...................

3/4 2-6 3/4.2.3 TOTAL INTEGRATED RADIAL PEAKING FACT 0R................ 3/4 2-9 3/4.2.4 AZIMUTHAL POWER TILT.................................. 3/4 2-12 3/4.2.5 DNB PARAMETERS........................................

3/4 2-13 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTFCTIVE INSTRUMENTATION.................... 3/4 3-1 3

3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.....................................

3/4 3-10 3/4.3.3 FONITORING INSTRUMENTATION Radiation Monitoring Instrumentation..................

3/4 3-25 Incore Detectors......................................

3/4 3-29 '

Seismic Instrumentation............................... 3/4 3-31 Meteorological Instrumentation........................

3/4 3-34 Remote Shutdown Instrumentation.......................

3/4 3-37 Post Accident Instrumentation.........................

3/4 3-40 Fire Detection Instrumentation........................

3/4 3-43 4

Radioactive Gaseous Effluent Monitoring Instrumentation.....................................

3/4 3-47 Radioactive Liquid Effluent Monitoring Instrumentation.....................................

3/4 3-53 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION................. 3/4 4-1 Sta rtup and Powe r..................................... 3/4 4-1 l

Hot Standby...........................................

3/4 4-2 i

Shutdown..............................................

3/4 4-2a 3/4.4.2 SAFETY VALVES.........................................

3/4 4-3 l

3/4.4.3 RELIEF VALVES.........................................

3/4 4-4 l

CALVERT CLIFFS - UNIT 1 IV Amendment No. 39,53,55,99,105

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS l

PAGE SECTION 3/4.11 RADIOACTIVE EFFLUENTS

~

3/4.11.1 LIQUID EFFLUENTS Con cen tration.................................

3/4 11-1 Dose........................................

3/4 11-3 3/4 11-6 Liquid Radwaste Treatment System 3/4.11.2 GASEOUS EFFLUENTS Do se Ra t e....................................

3/4 11-7 Dose-Noble Gases..............................

3/411-11 Dose-lodine-131, and Radionuclides in Particulate Form 3/4 11-12 Gaseous Radwaste Treatment......................

3/4 11-13 Explosive Gas Mixture...........................

3/411-14 Gas S torage Tank s..............................

3/4 11-13 3/4.11.3 SOLID RADIOACTIVE WASTE.....................

3/4 11-16 3/4.11.4 TOT A L D OS E.................................

3/4 11-17 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGR AM........................

3/4 12-1 3/4 12-12 3/4.12.2 LAND USE CENSUS............................

3/4.12.3 INTERLABORATORY COMPARISON PROGRAM.......

3/4 12-13 CALVERT CLIFFS UNIT 1 VIIIa Amendment No. J00,105

INDEX BASES i

SECTION PAGE 3/4.9.5 COMMUNICATIONS........................................

B 3/4 9-1 3/4.9.6 REFUELING MACHINE OPERABILITY......................... B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING............ B 3/4 9-2 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRC'JLATION.............. B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM.............. B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND SPENT FUEL POOL WATER LEVEL......................... B 3/4 9-3 3/4.9.12 SPENT FUEL P0OL VENTILATION SYSTEM.................... B 3/4 9-3 3/4.9.13 SPENT FUEL CASK HANDLING CRANE........................ B 3/4 9-3 CONTAINMENT VENT ISOLATION VALVES..................... B 3/4 9-3 3/4.9.14 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 S H UT DOWN MARGI N....................................... B 3 / 4 10- 1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION L I M I TS.............................................. B 3 / 4 10-1 3/4.10.3 NO FLOW TESTS......................................... B 3/4 10-1 3/4.10.4 CENTER CEA MISALIGNMENT............................... B 3/4 10-1 3/4.10.5 COOLANT CI RCULATION................................... B 3/4 10-1

.p-3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS...................................... B 3/4 11-1 3/4.11.2 GASE0US EFFLUENTS..................................... B 3/4 11-2 3/4.11.3 SOLID RADI0 ACTIVE WASTE............................... B 3/4 11-5 3/4.11.4 TOTAL D0SE............................................ B 3/4 11-5 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MO N I TO R I N G P R0G RAM............................'........ B 3 / 4 12 - 1 3/4.12.2 LAND USE CENSUS....................................... B 3/4 12-1 3/4.12.3 INTERLABORATORY COMPARISON PR0 GRAM.................... B 3/4 12-2 CALVERT CLIFFS - UNIT 1 XIII Amendment No. 26,55,88,Jeg, 105

~.

INDEX e

DESIGN FEATURES PAGE SECTION t

5.1 SITE 8 ~

Map Defining the Site Boundary and Effluent Release Points..............................................

5-1 Low Population Zone...........................................

5-1 5.2 CONTAINMENT Configuration.................................................

5-1 Design Pressure and Temperature...............................

5-4.

5.3 REACTOR CORE Fu el As s embl i e s...............................................

5-4 Control Element Assemblies....................................

5-4

~

5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature...............................

5-4 Vo1ume........................................................

5-5 METEOROLOGICAL TOWER L0 CATION.................................

5-5 5.5 5.6 FUEL STORAGE Criticality...................................................

5-5

~+-

Drainage......................................................

5-5 Capacity.......................................................

5-5 i

COMPONENT CYCLIC OR TRANSIENT LIMITS.......................... 5-5 5.7 t

I i

I l

CALVERT CLIFFS - UNIT 1 XIV Amendment No. 100 s

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 2

6.1 R E S PO N S I B I L I T Y............................................., 6-1 62 ORGANIZATION 0ffsite...................................................

6-1 Fa c i l i ty S ta f f.............................................

6-1 6.3 FACILITY STAFF QUAL IFICATIONS............................. 6-6 1

6.4 TRAINING..................................................

6-6 6.5 REVIEW AND AUDIT s

6.5.1 PLANT OPERATIONS AND SAFETY REVIEW COMMITTEE (POSRC)

Function................................................

6-6 l

Com po s i t i o n.............................................

6-6

-s Al t e rn a t e s..............................................

6-6 4

Meeting Frequency.......................................

6-7 Quorum..................................................

6-7 Re s po n s i b 111 t i e s........................................

6-7 Authority...............................................

6-8 R e co rd s.................................................

6-8 6.5.2 0FF SITE SAFETY REVIEW COMMITTEE (OSSRC)

.p -

Function................................................

6-8 Com po s i t i o n.............................................

6-9 Al t e rna t e s..............................................

6-9 Consultants.............................................

6-9 Meeting Frequency.......................................

6-9 Quorum..................................................

6-9 R e v i ew..................................................

6-1 0 Audits..................................................

6-11 Authority...............................................

6-12 l

Records.................................................

6-12 I

CALVERT CLIFFS - UNIT 1 XV Amendment No. JJ, 105

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---,n,

_.------,w-nw.,---,-e----_w,-w, w-w v-

-, -..., - - -, -, -,-,-------m--,-t---

---, - - - - - -, + -,,, - -,

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.6 REPORTABLE EVENT ACTI0N.................................

.. 6-12 6.7 SAFETY LIMIT VIOLATION.....................................

6-13 6.8 P RO C E DU R E S................................................. 6 - 13 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REP 0RtS..........................................

6-14 6.9.2 S P EC I AL R E P0 RTS..........................................

6-18 m

6.10 R ECO RD R ET ENT IO N..........................................

6-19 6.11 RADI ATION PROTECTION PR0G RAM.............................. 6-20 6.12 H I GN RADI AT I ON A REA.......................................

6-20 6.13 ENVIRONMENTAL QUALIFICATION...............................

6-21 6.14 SYSTEM INTEGRITY..........................................

6-21 6.15 IODINE M0NITORING.........................................

6-22 6.16 PROCESS CONTROL PR0 GRAM...................................

6-23 6.17 0FFSITE DOSE CALCULATION MANUAL...........................

6-23 6.18 MAJOR CHANGES TO RADI0 ACTIVE LIQUID GASEOUS AND SOLID WASTE TREATMENT SYSTEMS...........................

6-24 i

l CALVERT CLIFFS - UNIT 1 XVI Amendment No. 27, 53, $A,105 1

i

INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION r

LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

APPLICABILITY: As shown in Table 3.3-12 ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Specification, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in 4

l Table 3.3-12 Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS

+

4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-1L i

i CALVERT CLIFFS UNIT 1 3/4 3-48 Amendment No.105

4 TABLE 3.3-12 g

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION o

E*:

Q MINIMUM CHANNELS I

INSTRUMENT OPERABLE APPLICABILITY ACTION u

G 1.

WASTE GAS HOLDUP SYSTEM k

e a.

Noble Gas Activity monitor -

}

Providing Alarm and Automatic 35 Termination of Release (1) b.

Effluent System Flow Rate 36 Measuring Device (1) 2.

MAIN VENT SYSTEM 37 l

a.

Noble Gas Activity Monitor (1) y 38 x-b.

lodine Sampler (1) y 38 c.

Particulate Sampler (1) i

]

i i

k a

n E.

un

..-~.-g

TABLE 3.3-12 (Centinued)'

i TABLE NOTATION At all times.

i With the number of channels OPERABLE less than required by the ACTION 35 -

Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment:

Using the main vent monitor as a backup and recording RMS a

a.

readings every 15 minutes during the release, or b.

Provided that prior to initiating the release, at least two 1

independent samples of the tank's contents are analyzed, and at least two technically qualified members of the Facility Staff independently verify the release rate calculations and two qualified operators verify the discharge valve lineup.

Otherwise, suspend release of radioactive effluents via this pathway.

With the number of channels OPERABLE less than required by the ACTION 36 -

Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

With the number of channels OPERABLE less than required by the ACTION 37 -

Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided either (1) grab samples are taken and analyzed for gross activity at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or (2) an equivalent monitor is provided.

With the number of channels OPERABLE less than required by the I

ACTION 38 -

Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided samples are continuously collected as required in Table 4.11-2 with auxiliary samp!!ng equipment.

+

l.

i Amendment No.105 CALVERT CLIFFS UNIT 1 3/4 3-30

=.

.. ~.

\\

o TABLE 4.3-11 r

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE i

INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED G

l b

1.

WASTE GAS HOLDUP SYSTEM H

=

a.

Noble Gas Activity Monitor -

Providing Alarm and Automatic Termination of Release P

P R(3)

SA(1) 1 b.

Effluent System Flow Rate

]

Measuring Device D(4)

N.A.

R N.A.

T 2-2.

MAIN VENT SYSTEM di a.

Noble Gas Activity Monitor D

M R(3)

SA(2) b.

Iodine Sampler W

N.A.

c.

Particulate Sampler W

N.A.

i I

DI i

EF b

w m

l i

TABLE 4.3-11 (Centinued)

TABLE NOTATION At all times other than when the line is valved out and locked.

(1)

The CHANNEL FUNCTIONAL TEST shall also demonstrate the automatic isolation of this pathway and/or control room alarm annunciation occurs if the appropriate following condition (s) exists:

1.

Instrument indicates measure levels above the alarm / trip setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

(2)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

1.

Instrument indicates measured levels above the alarm setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

m (3)

The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards traceable to the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system within its intended range of energy and measurement range.

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

(4)

The CHANNEL CHECK shall consist of verifying indication of flow during periods of release and shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which effluent releases are made.

4- -

CALVERT CLIFFS UNIT 1 3/4 3-52 Amendment No.105

INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive liquid effluent monitoring instrumentation cha6nels shown in Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: At all times.

ACTION:

a.

With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel Inoperable, or change the setpoint so it is acceptably conservative.

b.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-

13. Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS

+

4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-12.

CALVERT CLIFFS UNIT 1 3/4 3-53 Amendment No. 105

k TABLE 3,3-13

\\

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION g

se oCg MINIMUM tl CHANNELS INSTRUMENT OPERABLE ACTION 1.

GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND g

AUTOMATIC TERMINATION OF RELEASE a.

Liquid Radwaste Effluent Line (1) 28 b.

Steam Generator Blowdown Effluent Line (1) 29 2.

FLOW RATE MEASUREMENT DEVICES W

a.

Liquid Radwaste Effluent Line (1) 30 b.

Steam Generator Blowdown Ef fluent Line (1) 30 g

m a

s 8

TABLE 3.3-13 (Centinued)

TABLE NOTATION ACTION 28 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release:

a.

At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1, and

~

b.

At least two technically qualified members of the Facility Staff independently verify the release rate calculations and two qualified operators verify the discharge valve line up.

ACTION 29 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross radioactivity (beta or gamma) at the lower limit of detection defined in Table 4.11-1:

a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is greater than 0.01 microcurie / gram DOSE

~

EQUIVALENT l-131.

~

b.

At least once per 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months when the specific activity of the secondary coolant is less than or equal to 0.01 microcurle/ gram DOSE EQUIVALENT l-131.

ACTION 30 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump performance curves may be used to estimate flow.

4*

l

(

CALVERT CLIFFS UNIT 1 3/4 3-55 Amendment No.105 I

L

_ _._._ _ __..~,_,

4 TABLE 4,3-12

\\

o RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS e

zu.

h CHANNEL SOURCE CHANNEL FUNCTIONAL 8

INSTRUMENT CHECK CHECK CALIBRATION TEST v

1.

GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a.

Liquid Radwaste Effluent Line D

P R(2)

SA(1) b.

Steam Generator Blowdown Effluent Line D

P R(2)

SA(1) y 2.

FLOW RATE MEASUREMENT DEVICES Y

a.

Liquid Radwaste Effluent Line D(3)

N.A.

R N.A.

'S b.

Steam Generator Blowdown Effluent Line D(3)

N.A.

R N.A.

g Ia s

_ _ _ _ _.~ _

TABLE 4.3-12 (Continued)

TABLE NOTATION t

(1)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and/or control room alarm annunciation occur if the appropriate following condition (s) exists:

1.

Instrument indicates measured levels above the alarm / trip setpol.nt.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

(2)

The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards traceable to the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system within its intended range of energy and measurement range.

For subsequent l

CHANNEL CALIBRATION, sources that have been related to the initial calibration j

can be used.

i (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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which effluent releases are made.

4 Y

a d'

i t

f CALVERT CLIFFS UNIT 1 3/4 3-57 Amendment No.105

3/4.11 R ADIOACTIVE EFFLUENTS LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS 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.

APPLICABILITY: At all times.

ACTION:

a.

With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, without delay restore the concentration to within the above limits.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILL ANCE 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 4-methodology and parameters in the ODCM to assure that the concentrations at the point

- ' of release are maintained within the litnits of Specification 3.11.1.1.

l l

CALVERT CLIFFS UNIT 1 3/411-1 Amendment No.

105 l

/

I TABLE 4.11-1 RADIOACTIVE LIQUID WASTE SAMPldNG AND ANALYSIS PROGRAM Minimum --

Lower Limit of Detection Liquid Release Sampling Analysis Type of Activit'y (LLD)a Type Frequency' Fiequency Analysis (uCi/ml)

A, Batch Wgste P

P Releases Each Batch Each Batch Principal Gamma 5x10-7 Emitterse 4

I-131 lx10 4

Mo-99, Ce-14L 2x10 P

M H-3 lx10-5 d

~

Each Batch Composite Gross Alpha lx10-7 d

Sr-89, Sr-90 3x10-8 Each Batch Com site B,

Turbine Building M

M Principal Gamma 5x10-7 Sump Emittersc I-131 lx10-6

+-

Mo-99, Ce-144 2x10-6 f

CALVERT CLIFF 5 UNIT 1 3/411-7 Amendment No.105 s-~

TABLE 4.11-1 (Continued)

TABLE NOTATION j.

a 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 j

background, that will be detected with 95% probability with only 5% probability of 4

falsely concluding that a blank observation represents a "real" signal.

~

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

LLD =

4.66sb 6

E-V 2.22 x 10 y

exp (- Aat)

Where:

LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, i

sb s the standard deviation of the background counting rate or of the counting rate j

of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yleid, when applicable, A is the radioactive decay constant for the particular radionuclide, and l

A t is the elapsed time between sample collection, or end of the sample collection 4

period, and time of counting.

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(af ter the fact) limit for a particular measurement.

b Prior to sampling Reactor Coolant Waste and Miscellaneous Waste for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.

l 4

CALVERT CLIFFS UNIT 1 3/4 11-3 Amendment No. 105

TABLE 4.11-1 (Continued)

TABLE NOTATION C The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-65, Cs-134, Cs-137 and Ce-141. 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 analyzed and reported in the Semlannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.8.

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

4-CALVERT CLIFFS UNIT 1 3/4 11-4 Amendment No.105

RADIOACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid ef fluents released to UNRESTRICTED AREAS shall be limited:

During any calendar quarter to less than or equal to 3.0 mrems to the total a.

body and to less than or equal to 10 mrems to any organ, and b.

During any calendar year to less than or equal to 6 mrems to the total body and to less than or equal to 20 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

With the calculated dose from the release of radioactive materials in liquid a.

effluents exceeding any of the above limits, 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 that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not app!! cable.

SURVEILLANCE REQUIREMENTS 4*

~~

4.11.1.2 Monthly cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 60 days.

CALVERT CLIFFS UNIT 1 3/411-5 Amendment No.105

. ~ _

4 RADIOACTIVE EFFLUENTS LIQUID RADWASTE TREATMENT SYSTEM i

LIMITING CONDITION FOR OPERATION i

3.11.1.3 The liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the calculated doses due to the liquid effluent to UNRESTRICTED AREAS exceeds 0.36 mrem to the total body or 1.20 mrem to any organ in a 92 day period.

l APPLICABILITY: At all times.

ACTION:

With radioactih liquid waste being discharged without treatment and in a.

excess of the above limits, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report that includes the following information:

m 1.

Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems,,

and the reason for the inoperability, 2.

Action (s) taken to restore the Inoperable equipment to OPERABLE status, and i

3.

Summary description of action (s) taken to prevent a recurrence.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

+

SURVEILLANCE REQUIREMENTS 4.11.1.3 Monthly doses due to liquid releases to UNRESTRICTED AREAS shall be calculated at least once per 60 days in accordance with the methodology and parameters in the ODCM.

CALVERT CLIFFS UNIT 1 3/4 11-6 Amendment No.105

RADIOACTIVE EFFLUENTS

+

GASEOUS EFFLUENTS DOSE RATE LIMITING CONDITION FOR OPERATION 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) shall be limited to the following:

a.

For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and b.

For iodine-131 and for all radionuclides in particulate form with half l'ives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.

i APPLICABILITY: At all times.

I ACTION:

With the dose rate (s) exceeding the above limits, without delay restore the a.

release rate to within the above limit (s).

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS i-4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the

+

ODCM.

4.11.2.1.2 The dose rate due to lodine-131 and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents shall be determined to be within the 4

above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2.

CALVERT CLIFFS UNIT 1 3/4 11-7 Amendment No.105

r:

4 TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM o

q Minimum Lower Limit of e

Sampling Analysis Type of Detection (LLD)a g

Gaseous Release Type Frequency Frequency Activity Analysis (uCi/ml)

P P

f h

lx10-"

E A.

Waste Gas Storage '8 Each Tank Each Tank Principal Gamma Emitters g

Tank Grab Sample (Gaseous Emissions Only)

Q P

P B.

Containment Purge Each Batchc Each Batchc Principal Gamma Emittersb 1x10-"

g and Vent Grab Sample (Gaseous Emissions Only) b 1x10-"

C.

Main Vent M

Mc Principal Gamma Emitters c

Grab Sample (Gaseous Emissions Only) d 4

Continuous M

H-3 lx10 M

x-d w

Continuous W

I-131 1x10-12 "g

Charcoal Sample' Continuousd b

lx10-II W

Principal Gamma Emitters Particulate (1-131, others)

Sample

d Continuous M

Gross Alpha Ix10-II Composite Particulate Sample d

Continuous Q

Sr-89, Sr-90 1x10-II Composite p

Particulate Sample d

4 Continuous Noble Gas Noble Gases Ix10 Monitor Gross Beta or Gamma D.

Incine,atee eii~

e e

m _,

m,,

_ -y U1

TABLE 4.11-2 (Continued)

TABLE NOTATION a 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 "reai" signal.

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

LLD =

4.66sb E-V 2.22 x 106 y

exp ( lot)

Where:

LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, i

sh s the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 6

2.22 x 10 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and a t for plant effluents is the elapsed time between sample collection or end of the sample collection period, and time of counting.

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.

CALVERT CLIFFS UNIT 1 3/4 11-9 Amendment No.105

TABLE 4.11-2 (Continued)

TABLE NOTATION l

b The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60,2n-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. 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 analyzed and reported in the Seminannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.8.

c Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within l

one hour unless (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 5, and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 5.

d The ratio of the sample flow rate to the sampled stream flow rate shall be known for i

the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.

Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months af ter changing, or after removal from sampler.

When sample collection time is less than seven days, the corresponding LLDs may be increased by a l

proportional factor. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 5, and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 5.

I Waste Gas Decay Tank samples shall be collected and analyzed for oxygen a ner week on the in-service tank and following tank isolation. Waste Gas Surge.:.~

samples shall be collected and analyzed daily during power escalation from MODE 6 through MODE 3, and once per week at all other times.

8 Collect sample and analyze daily for total Curie content per Specification 3.11.2.6 when the Reactor Coolant System specific activity of Xe-133 is greater than 150 uCi/ml.

h Incinerated oil may be discharged via points other than the main vent (e.g., Auxiliary Boiler). Releases shall be accounted for based on pre-release grab sample data.

i Samples for incinerated oil releases shall be collected from and representative of filtered oilin liquid form.

I l

t l

t I

l CALVERT CLIFFS UNIT 1 3/4 11-10 Amendment No.105

RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) shall be limited to the following:

During any calendar quarter: Less. than or equal to 10 mrads for gamma a.

radiation and less than or equal to 20 mrads for beta radiation and, b.

During any calendar year:

Less than or equal to 20 mrads for gamma radiation and less than or equal to 40 mrads for beta radiation.

APPLICABILITY: At all times.

ACTION:

With the calculated air dose from radioactive noble gases in gaseous a.

effluents exceeding any of the above limits, 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 that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4-4.11.2.2 Monthly cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 60 days.

CALVERT CLIFFS UNIT 1 3/4 11-11 Amendment No.105

RADIOACTIVE EFFLUENTS DOSE -IODINE-131 AND RADIONUCLIDES IN PARTICULATE FORM LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from iodine-131 and ail radionuclides in particulate form with half lives greater than 8 days in gaseous effluents released to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) shall be limited to the following:

l a.

During any calendar quarter: Less than or equal to 15 mrems to any organ

and, b.

During any calendar year: Less than or equal to 30 mrems to any organ.

Less than 0.196 of the limits of 3.ll.2.3(a) and (b) as a result of burning c.

i contaminated oil.

~

s APPLICABILITY: At all times.

~

ACTION:

a.

With the calculated dose from the release of iodine-131 and radionuclides in j

particulate form with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, 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 and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

+

l l

SURVEILLANCE REQUIREMENTS 4.11.2.3 Monthly cumulative dose contributions for the current calendar quarter and current calendar year for lodine-131 and radionuclides in particulate form with half lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 60 days.

l CALVERT CLIFFS UNIT 1 3/4 11-12 Amendment No.105 l.

RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EAHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gar,eous waste prior to their discharge when the gaseous effluent air doses due to gaseous effluent releases, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) exceeds 1.20 mrad for gamma radiation and 2.4 mrad for beta radiation in a 92 day period. The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the calculated doses due to gaseous effluent releases, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) exceeds 1.8 mrem to any organ in a 92 day period.

APPLICABILITY: At all times.

ACTION:

a.

With gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:

1.

Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability, 2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, and 4-3.

Summary description of action (s) taken to prevent a recurrence.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4.

Monthly doses due to gaseous releases shall be calculated at least once per 60 days in accordance with the methodology and parameters in the ODCM.

\\

CALVERT CLIFFS UNIT 1 3/4 11-13 Amendment No.

105

A RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE (Hydrogen ried systems not designed to withstand a hydrogen explosion)

LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 4% by volume.

APPLICABILITY: At all times ACTION:

With the concentration of oxygen in a waste gas decay tank greater than 4%

a.

by volume immediately suspend all additions of waste gases to that tank and reduce the concentration of oxygen to less than or equal to 4% by volume

~

without delay.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

b.

~

SURVEILLANCE REOUIREMENTS 4

4.11.2.5-The concentrations of oxygen in the waste gas holdup system shall be determined to be within the above limits by the sampling program described in Table 4.11-2.

Y

]

I

{

CALVERT CLIFFS UNIT 1 3/4 11-14 Amendment No. 105

RADIOACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 58,500 curies noble gases (considered as Xe-133). -

APPLICABILITY: At all times.

ACTION:

With the quantity of radioactive material in any gas storage tank exceeding a.

the above limit, immediately suspend all additions of radioactive material to that tank and 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.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in the in-service gas storage tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the Reactor Coolant System specific activity of Xe-133 is greater than 150 uCi/ml.

~f '. -

l l

l CALVERT CLIFFS UNIT 1 3/4 11-15 Amendment No. 105

RADIOACTIVE EFFLUENTS SOLID RADIOACTIVE WASTE t

LIMITING CONDITION FOR OPERATION t

3.11.3 The solid radwaste program shall be used in accordance with a PROCESS t

CONTROL PROGRAM to process wet radioactive wastes to meet shipping and buria!

ground requirements.

APPLICABILITY: At all times.

ACTION:

a.

With the provisions of the PROCESS CONTROL PROGRAM not satisfied, suspend shipments of defectively processed or defectively packaged solid radioactive wastes from the site.

b.

The provision of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.3 THE PROCESS CONTROL PROGRAM shall be used to verify the SOLIDIFICATION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive waste (e.g., filter sludges, spent resins, evaporator bottoms, boric acid solutions, and sodium sulfate solutions).

4-l l

l l

CALVERT CLIFFS UNIT 1 3/4 11-16 Amendment No. 105 L

~

i RADIOACTIVE EFFLUENTS TOTAL Dt $_E, E

LIMITING CONDITION FOR OPERATION 3.11.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

APPLICABILITY: At all times.

j ACTION:

With the calculated doses from the release of radioactive materials in liquid a.

or gaseous effluents exceeding twice the limits of Specification 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.ll.2.3.a, or 3.11.2.3.b, calculations shat!

be made including direct radiation contributions from the reactor units and outside storage tanks to determine whether the above limits of Specification 3.11.4 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases

}

to prevent recurrence of exceeding the above limits and includes the

~

schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report.

It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in

+

accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the ODCM.

4.11.4.2 Cumulative dose contributions from direct radiation from the reactor units and outside storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in Specification 3.11.4.a.

CALVERT CLIFFS UNIT 1 3/4 11-17 Amendment No.105

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 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 conducted a.

as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Specification 6.9.1.7, a description of the reasons for not conducting.t,he program as required and the plans for preventing a recurrence.

s b.

With the level of radioactivity as the result of plant effluents in an environmental sample at a specified location exceeding the reporting levels of Table 3.12-2, prepare and submit to the Commissirn within 30 days after

~

receiving the sample analysis, p)ursuant 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 dose

to a MEMBER OF THE PUBLIC is less than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2, and 3.11.2.3. When more than one of the radionuclides in Table 3.12-2 are detected in the sample this report shall be submitted ifs concentration (1) + concentration (2) +..> 1.0 reporting level (1) reporting level (2)

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 is equal to or greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3. This 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.

CALVERT CLIFFS UNIT 1 3/4 12-1 Amendment No. 700, 105 J

.,,v.,,

--.c=-

-,.~,.m-

.m-

-m

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING ACTION: (Continued)

With fresh leafy vegetable samples unavailable from one or more of the c.

sample locations required by Table 3.12-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days.

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

Pursuant to Specification 6.9.1.7, identify the cause of the l

unavailability of samples and identify the new location (s) for obtaining the replacement samples in the next Annual Radiological Environmental Operating Report.

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.

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

l l

w-i l

CALVERT CLIFFS UNIT 1 3/4 12-2 Amendment No. JSD, 105 i

I

t TABLE 3.12-1 (Continued)

[2=

RADIOLOGICAL ENVIRONENTAL MONITORING PROGRAM l

3 Exposure Pathway Number of Representative Sampling and Type and Frequency and/or Sample Samp es and Sample Locations, Collection Frequency of Analysis i

n i

r-d

b. Food Products Samples of 3 different kinds of Monthly during growing Gamma isotopic and broad leaf vegetation grown near season.

I-131 analysis.

l the site boundary at 2 different g

locations of highest predicted 1-q annual average groundlevel D/Q (Ibl-Ib6).

m d

1 sarple of each of the similar Monthly during growing Gamma isotopic and broad leaf vegetation grown 15-season.

1-131 analysis.

30 km distant in the least prevalent wind direction (Ib7-R Ib9).

i A

l E

i I

1 ig F.

O r

i l

I

f TABLE 3.12-1 (Continued) o

\\

]

h TABLE NOTATION Rs a

a The code in parenthesis, e.g. DR1, Al, defines generic sample locations in this specification that can be used to 4

h identify the specific locations in the map (s) and table in the ODCM. Specific parameters of distance and direction y

sector from the central point between the two containment buildings and additional description where pertinent, is g

provided for each sample location in Table 3.12-1, and in a table and figure (s) in the ODCM. Refer to NUREG-0133, q

" Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, October 1978", and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the a

P required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction of automatic sampling equipment. If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling i

period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental i

i Operating Report pursuant to Specification 6.9.1.7.

It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. Pursuant to Specification 6.9.1.7, identify the cause of the unavailability of samples for that pathway and identify the new location (s) for t

obtaining samp)les in the next Annual Radiological Environmental Operating Report and also include in the report a wb revised figure (s and table for the ODCM reflecting the new location (s).

b j

y One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may m

be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The frequency of analysis or t

readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading. Due to the geographical limitations,9 sectors are monitored F

around the Calvert Cliffs Nuclear Power Plant.

gc Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to I

allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times

[

the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

O 4

NP i

o i

w

TABLE 4,12-1 o

\\

h DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSISa,b R

g LOWER LIMIT OF DETECTION (LLD)c A

Airborne Particulg)te Fish & Invertebrates Milk Food Products Sediment Water Analysis (pCi/l) or Gases (pCi/m (pCi/kg, wet)

(pCi/l)

(pCi/kg, wet)

(pCi/kg, dry)

P Gross Beta 4

0.01 H-3 2000*

Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 d

i 1-131 i

0.07 1

60 Cs-134 15 0.05 130 15 60 150 4

Cs-137 18 0.%

150 18 80 180 Ba-La-140 15 15

?r i

E I

f

If no drinking water pathway exists, a value of 3000 pCi/l may be used.

it 1

o 1

i

TABLE 4.12-1 (Continued)

TABLE NOTATION a

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 Radiological Environmental Operating Report pursuant to Specification 6.9.1.7.

b Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.

c 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:

4.66sb E-V 2.22 Y

exp (- Aa t)

Where:

LLD is the "A priori" lower limit of detection as defined above, as picocuries per unit mass or volume, sb s the standard deviation of the background counting rate or of the counting i

rate of a blank sample as appropriate, as counts per minute, 4-E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and a t for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting Typical values of E, V, Y and at should be used in the calculation.

CALVERT CLIFFS UNIT 1 3/4 12-10 Amendment No. JPD,105

TABLE 4.12-1 (Continued)

TABLE NOTATION 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 6.9.1.7 d

LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.

s

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CALVERT CLIFFS UNIT 1 3/4 12-11 Amendment No. 100, 105

3/4.12, RAD,1,0,L,0GICAL ENVIRONMENTAL MONITORING LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 9 meteorological sectors of ty(nearesj) milk anim nearest residence and the nearest garden

of greater than 50 m 500 ft producing broad leaf vegetation. (For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify within a distance of 5 km (3 miles) the locations in each of the 9 meteorological sectors of all milk animals and all gardens of 2

greater than 50 m producing broad leaf vegetation).

APPLICABILITY: At all times.

1 ACTION:

1 a.

With a land use census identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, identify the new location (s) in the next Annual Radiological Environmental Operating Report, pursuant to Specification 6.9.1.7.

b.

With a land use census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the new location (s) to the radiolog(ical envionmen monitoring program within 30 days.

The sampling location s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this land use census I

was conducted. Pursuant to Specification 6.9.1.7, identify the new location (s) in the next Annual Radiological Environmental Operating Report and also include in a+

the report a revised figure (s) and table for the ODCM reflecting the new location (s).

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

c.

SURVEILLANCE REQUIREMENTS 4.12.2 The land census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census.

Specifications for broad leaf vegetation sampling in Table 3.12-1.4b shall be followed, including analysis of control samples.

CALVERT CLIFFS - UNIT 1 3/4 12-12 Amendment No. 190, 105

3/4.12 RADIOLOGICAL ENVIRONMENTAL NNITORING C

INTERLABORATORY COMPARISON PROGRAM d

LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission, that correspond to samples required by Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

a.

With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Specification l

6.9.1.7.

)

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in the ODCM. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7.

4*

CALVERT CLIFFS UNIT 1 3/4 12-13 Amendment No. J00,105

INSTRUMENTATION BASES 3/4.3.3.6 POST-ACCIDENT INSTRUMENTATION The OPERABILITY of the post-accident instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, "Instrumen-tation for Light-Water-Cooled Nuclear Plants to Assess Plant Conditions During and Following an Accident," December 1975, and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."

o 3/4.3.3.7 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that

~

adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages. Prompt detection of fires will reduce the poten-

~

tial for damage to safety related equipment and is an integral element in the overall facility fire protection program.

In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to operability.

3/4.3.3.8 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION I0 DINE AND PARTICULATE SAMPLER The OPERABILITY of the Iodine and Particulate Sampler ensures that

- ~

Iodine and Particulate Samples can be obtained for analysis during and following an accident. The surveillance requirements ensure a high degree of availability.

The sampler was installed to meet the requirements of NUREG-0737 Item II.F.1.

The sampler's operation was not assumed in any accident analysis.

CALVERT CLIFFS - UNIT 1 B 3/4 3-3 Amendment No. 26, 53, 99

INSTRUMENTATION BASES 3/4.3.3.9 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of Specifica-tion 3.11.2.1.a based on average annual X/Q.

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

3/4.3.3.10 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

~

The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

l

+

CALVERT CLIFFS - UNIT 1 B 3/4 3-4 Amendment No. 105

RADIOACTIVE EFFLUENTS i

BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design objectives of Appendix I,10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part 20.106(e) to the population.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300, Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination -

Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, 3. K.,

" Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

3/4.11.1.2 DOSE 1

This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I,10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix L The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable."

4-The dose calculation methodology and parameters in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977, Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977, i

and NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants".

i J

CALVERT CLIFFS UNIT 1 B 3/411-1 Amendment No.105 i

1

RADIOACTIVE EFFLUENTS BASES (Cont inued) 3/4.11.1.3 LIQUID RADWASTE TREATMENT SYSTEM

~

The requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable".'

This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part

50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I,10 CFR Part 30, for liquid effluents.

3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specification is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1.

These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, exceedin Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)g the limits specified in Appendix B,

). For MEMBERS OF THE PUBLIC who i

may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE J

PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.

l The required detection capabilities for radioactive materials in gaseous waste samples l

4-are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300, Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination -

Application to Radiochemistry," Anal. Chem. 40, 386-93 (1968), and Hartwell, 3.K.,

" Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

CALVERT CLIFFS UNIT 1 B 3/411-2 Amendment No.105

__r_-_<--.e.w,,-....-r----r.+-

RADIOACTIVE EFFLUENTS B ASES (Continued) 3/4.11.2.2 DOSE - NOBLE GASES This specification is provided to implement the requirements of Sections,II.B, III.A and IV.A of Appendix I,10 CFR Part 50. The Limiting Condition for Operation implements i

the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous ef fluents to UNRESTRICTED AREAS will be kept "as low as reasonably achievable." The 4

l Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents a're consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of J

Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion 1

of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977, and NUREG-0133 " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants".

The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical annual average atmospheric conditions.

4-4 i

i i

CALVERT CLIFFS UNIT I B 3/411-3 Amendment No.105

RADIOACTIVE EFFLUENTS BASES (Continued) 3/4.11.2.3 DOSE -IODINE 131 AND RADIONUCLIDES IN PARTICULATE FORM This specification is provided to implement the. requirements of Sections.II.C, Ill.A and IV.A of Appendix I,10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix 1 to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable."

The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109,

" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977, Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,"

Revision 1, July 1977, and NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants". These equations also provide for determining the actual doses based upon the historical annuai average atmospheric conditions.

The release rate specifications for iodine-131 and radionuclides M particulate form with half lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were:

1) individual inhalation of airborne radionuclides,2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

+

3/4.11.2.4 GASEOUS RADWASTE TREATMEN7dYSTEM The requirement that the appropriate portitM <# these systeru be used, when specified, provides reasonable assurance that t',e %evo of radioactive materials in gaseous effluents will be kept "as low as is reasmoly s.avable".

This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I,10 CFR Part 50, for gaseous effluents.

CALVERT CLIFFS UNIT 1 B 3/411-4 Amendment No.105

RADIOACTIVE EFFLUENTS BASES (Continued) 3/4.11.2.5 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potenbally explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limit of oxygen.

Maintaining the concentration of oxygen below its flammability limit provides assurance that the releases of radioactive materials will be controlled in conformar.ce with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

3/4.11.2.6 GAS STORAGE TANKS The tanks included in this specification are those tanks for which the quantity' of radioactivity contained is not limited directly or indirectly by another Technical Specification to a quantity that is less than the quantity that provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed 10 CFR 100 limits.

Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed accident guidelines.

3/4.11.3 SOLID RADIOACTIVE WASTE This specification implements the requirements of 10 CFR Part 50.36a and General design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters are included in the PROCESS CONTROL PROGRAM.

4-3/4.11.4 TOTAL DOSE This specification is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible.

CALVERT CLIFFS UNIT 1 B 3/411-5 Amendment No.105

RADIOACTIVE EFFLUENTS BASES (Continued)

If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been, corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part6 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Specifications 3.11.1.1 and 3.11.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

9 v-

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CALVERT CLIFFS UNIT 1 B 3/411-6 Amendment No. 105

I

\\

ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.1.4 The POSRC shall meet at least once per calendar month and as convened by the POSRC Chairman or his designated alternate.

j QUORUM 6.5.1.5 A quorum of the POSRC shall consist of the Chainnan or his designated alternate and four members including alternates.

RESPONSIBILITIES l

6.5.1.6 The POSRC shall be responsible for:

Review of 1) all procedures required by Specification 6.8 and changes a.

thereto, 2) any other proposed procedures or changes thereto as j

determined by the Plant Superintendent to affect nuclear safety.

b.

Review of all proposed tests and experiments that affect nuclear,

safety.

3 Review of all proposed changes to Appendix "A" Technical Specifications.

c.

d.

Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.

Investigation of all violations of the Technical Specifications includ-e.

ing the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrenct to the Manager - Nuclear Power Department and to the Chairman of the Off Site Safety Review Comittee.

f.

Review of all REPORTABLE EVENTS.

1 g.

Review of facility operations to detect potential safety hazards, h.

Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Off Site Safety Review Committee.

1.

Review of the Plant Security Plan and implementing procedures and shall 4

submit recommended changes to the Off Site Safety Review Comittee.

j.

Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Off Site Safety Review Committee.

k.

Review of any accidental, unplanned or uncontrolled radioactive release that exceeds 25% of the limits of Specification 3.11.1.2, 3.11.2.2 or 3.11.2.3, including the preparation of reports covering evaluation.

recommendations and disposition of the corrective action to prevent recurrence and for forwarding of these reports to the Plant Superinten-dent and the Off Site Safety Review Comittee.

1.

Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL.

CALVERT CLIFFS - UNIT 1 6-7 Amendment No. 26,3f),43,94, 105 i

)

ADMINISTRATIVE CONTROLS AUTHORITY

6. 5.1. 7 The Plant Operations and Safety Review Comittee shall:

a.

Recomend to the Plant Superintendent written approval or l

disapproval of items considered under 6.5.1.6(a) through (d)above.

b.

Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.

c.

Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Manager -

Nuclear Power Department and the Off Site Safety Review l

Committee of disagreement between the POSRC-and the Plant Superintendent; however, the Plant Superintendent shall have l

responsibility for resolution of such disagreements pursuant to 6.1.1 above.

RECORDS 6.5.1.8 The POSRC shall maintain written minutes of each meeting and copies shall be provided to the Manager - Nuclear Power Department and l

Chairman of the Off Site Safety Review Comittee.

6.5.2 0FF SITE SAFETY REVIEW COMMITTEE (OSSRC)

FUNCTION 6.5.2.1 The Off Site Safety Review Committee shall function to provide independent review and audit of designated activities in the areas of:

+

a.

nuclear power plant operations b.

nuclear engineering c.

chemistry and radiochemistry d.

metallurgy and non-destructive examination e.

instrumentation and control f.

radiological safety g.

mechanical and electrical engineering h.

quality assurance practices CALVERT CLIFFS - UNIT 1 6-8 Amendment No.43

ADMINISTRATIVE CONTROLS AUDITS i

6.5.2.8.1 Audits of facility activities shall be performed under the cog-nizance of the OSSRC. These audits shall encompass:

4 a.

The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.

b.

The performance, training and qualification of the entire facility staff at least once per 12 months.

c.

The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.

~

d.

The performance of activities required by the Quality Assurance Program to meet the criteria of Appendix "B",10 CFR Part 50, at least once per 24 months.

e.

Deleted.

I f.

The Safeguards Contingency Plan and implementing procedures at least once per 12 months in accordance with 10 CFR 73.40(d).

g.

Any other area of facility operation considered appropriate by the OSSRC or the Vice President-Supply.

h.

The Facility Fire Protection Program and implementing procedures at least once per 24 months.

i. An independent fire protection and loss prevention program inspection

+

and audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protection firm.

j. An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant at least once per 36 months.

i k.

The radiological environmental monitoring program and the results thereof at least once per 12 months.

1.

The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.

m.

The PROCESS CONTROL PROGRAM and implementing procedures for proces-sing and packaging of radioactive wastes at least once per 24 months.

The performance of activities required by the Quality Assurance n.

Program for effluent and environmental monitoring at least once per 12 months.

CALVERT CLIFFS - UNIT 1 6-11 Amendment No. 26, 82, 105

i ADMINISTRATIVE CONTROLS 6.5.2.8.2 Review of facility activities shall be performed under the cognizance of the OSSRC. These reviews shall encompass:

a.

The Facility Emergency Plan and implementing procedures ~at least once per 12 months in accordance with 10 CFR Part 50.54(t).

AUTHORITY 6.5.2.9 The OSSRC shall report to and advise the Vice President-Supply on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

RECORDS 6.5.2.10 Records of OSSRC activities shall be prepared, approved and distributed as indicated below:

a.

Minutes of each OSSRC meeting shall be prepared, approved and forwarded to the Vice President-Supply within 14 days following each meeting.

b.

Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Vice President-Supply within 14 days following completion of the review.

c.

Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Vice President-Supply and to the management positions responsible for the areas audited within 30 days after completion of the audit.

4',

6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a.

The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.

Each REPORTABLE EVENT shall be reviewed by the POSRC and the results of this review shall be submitted to the OSSRC and the Manager - Nuclear Power Department.

CALVERT CLIFFS - UNIT 1 6-12 Amendment No. AB, 82, 9A,105

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

The facility shall be placed in at least H0T STANDBY wifhin one hour.

a.

b.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases withir. one hour. The Manager - Nuclear Power Department and the OSSRC shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c.

A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the POSRC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

d.

The Safety Limit Violation Report shall be submitted to the Commission, the OSSRC and the Manager - Nuclear Power Department within 14 days of the violation.

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

a.

The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.

b.

Refueling operations.

c.

Surveillance and test activities of safety related equipment.

4-d.

Security Plan implementation.

e.

Emergency Plan implementation.

f.

Fire Protection Program implementation.

g.

The amount of overtime worked by plant staff members performing safety related functions must be limited in accordance with the NRC Policy Statement on working Hours (Generic Letter No. 82-12).

h.

PROCESS CONTROL PROGRAM implementation.

i. OFFSITE DOSE CALCULATION MANUAL implementation.

6.8.2 Each procedure and administrative policy of 6.8.1 above and changes thereto shall be reviewed by the POSRC and approved by the Plant Superinten-dent prior to imp 1.ementation and reviewed periodically as set forth in 1

administrative procedures.

)

CALVERT CLIFFS - UNIT 1 6-13 Amendment No. 26,4,75,82, 105 l

ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 6.8.1 above may be made pro-vided:

a.

The intent of the originial procedure is not altered.

b.

The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.

c.

The change is documented, reviewed by the'POSRC and approved by the Plant Superintendent within 14 days of implementation.

6.9 REPORTING REOUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforceme'1t unless otherwise noted.

STARTUP REPORT 6.9.1.1 A sumary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in oower level, (3) installation of fuel that has a different design or has been manu-factured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic perfor-l mance of the plant.

v-l 6.9.1.2 The startuo report shall address each of the tests identified in the FSAR and shall include a description of the measured values

(

of the operating conditions or characteristics obtained during the test program and a comparison of these values with design credictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other comitments shall be included in this report.

CALVERT CLIFFS - UNIT 1 6-14 Amendment No. $/, #1,52,94 l

\\

m

ADMINISTRATIVE CONTROLS 6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until al,1 three events have been completed.

M ANNUAL REPORTS 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.

6.9.1.5 Reports required on an annual basis shall include:

s a.

A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their agociated man rem exposure according to work and job functions,-

e.g., reactor operations and surveillance, inservice inspection, routine maintenance, w

special maintenance (describe maintenance), waste processing, and refueling.

The dose assignment to various duty functions may be, estimates based on pocket dosimeter, TLD, or film badge measure-ments.

Small exposures totalling less than 20% of the individual total dose need not be accounted for.

In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

b.

The complete results of steam generator tube inservice inspections performed during the report period (reference Specification 4.4.5.5.b).

c.

Documentation of all failures and challenges to the pressurizer PORVs or safety valves.

y A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

2] This tabulation supplements the requirements of $20.407 of 10 CFR Part 20.

CALVERT CLIFFS - UNIT 1 6-15 Amendment No. 29,6 8

_, _. _.. ~ _. _.

ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORT 6.9.1.6.

Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Inspection and Enforcement, U.S.

Nuclear Regulatory Commission, Washington, D.C.

20555, ATTN: Document Control Desk, with a copy to the Regional Administrator and to the NRC Resident' Inspector, no later than the 15th of each month following the calendar month covered by the report.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

6.9.1.7 Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

The Annur.1 Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, with operational controls as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Specification 3.12.2.

The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the Table and Figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the radiological environmental monitoring program; at least two legible maps ** covering all sampling locations keyed to a table giving distances and directions from the central point between the two containment buildings; the results of licensee participation in the Interlaboratory

~ Comparison Program, required by Specification 3.12.3; discussion of all deviations from the sampling schedule of Table 3.12-1; and discussion of all analyses in which the LLD required by Table 4.12-1 was not achievable.

A single submittal may be made.

- One map shall cover stations near the site boundary; a second shall include the more distant stations.

CALVERT CLIFFS UNIT 1 6-16 Amendment No. 29,68,94,105

=-

C ADMINISTRATIVE CONTROLS j

The Annual Radiological Environmental Operating Report will include the identification of the cause of unavailability of samples (if any), and will describe the locations used for the replacement samples. The report will also include any permanent changes in the sample locations which could appear in the monitoring program. It willinclude a revised figure (s) and table for the ODCM reflecting the new location (s).

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

6.9.1.8 Routine Radioactive Effluent Release Reports covering the operation of the unit i

during the previous 6 months of operation shall be submitted within 60 days after January I and July I of each year.**

The Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the plant as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data i

marized on a quarterly basis following the format of Appendix B thereof.

i The Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected 4

over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of,ggnt frequency distributions of wind speed, wind direction, and atmospheric stability.

This same report shall include an i

assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

A single submittal may be made for Calvert Cliffs, since the radwaste systems are common to both units.

l In lieu of submission with the Semi-Annual Reports, Sr89, Sr90 analyses results may I

be submitted in a supplementary report within 120 days after January I and July 1 of each year.

In lieu of submission with the first half year Radioactive Effluent Release Report, this summary of required meteorological data may be retained on site in a file that shall be provided to the NRC upon request.

4 CALVERT CLIFFS UNIT 1 6-17 Amendment No. 29,9A,105

i a

l ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued) i l

The Radioactive Effluent Release Report to be submitted 60 days after January I of 1

each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in l

Regulatory Guide 1.109, Rev.1, October 1977, and NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants".

The Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period:

1 a.

Container volume,

~

b.

Total curie quantity (specify whether determined by measurement or estimate),

4 c.

Principal radionuclides (specify whether determined by measurement or estimate),

d.

Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),

Solidification agent or absorbent (e.g., cement).

e.

The Radioactive Effluent Release Reports shall include a list and description of unplanned re!sases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations identified by the annual land use census pursuant to Specification 3.12.2.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the NRC Regional Office within the time period specified for each report. These i

reports shall be submitted covering the activities identified below pursuant l

to the requirements of the applicable reference specification:

CALVERT CLIFFS UNIT 1 6-18 Amendment No. 29, pf, 105

}

ADMINISTRATIVE CONTROLS a.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

b.

Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

c.

Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.

d.

Seismic event analysis, Specification 4.3.3.3.2.

e.

Core Barrel Movement, Specification 3.4.11.

f.

Fire Detection Instrumentation, Specification 3.3.3.7.

g.

Fire Suppression Systems, Specifications 3.7.11.1, 3.7.11.2, 3.7.11.3, 3.7.11.4 and 3.7.11.5.

h.

Penetration Fire Barriers, Specification 3.7.12.

1.

Steam Generator Tube Inspection Results, Specification 4.4.5.5.

J.

Specific Activity of Primary Coolant, Specification 3.4.8.

k.

Containment Structural Integrity, Specification 4.6.1.6.

1.

Radioactive Effluents - Calculated Dose and Total Dose, Specifications 3.11.1.2, 3.11.2.2, 3.11.2.3, and 3.11.4.

m.

Radioactive Effluents - Liquid Radwaste, Gaseous Radwaste and Ventilation Exhaust Treatment Systems Discharges, Specifications 3.11.1.2 and 3.11.2.4.

n.

Radiological Environmental Monitoring Program, Specification 3.12.1.

4-CALVERT CLIFFS UNIT 1 6-18a Amendment No. 29,94,105

ADMINISTRATIVE CONTROLS 6.16 PROCESS CONTROL PROGRAM (PCP) 6.16.1 The PCP shall be approved by the Commission prior to implementation.

6.16.2 Licensee initiated changes to the PCP:

1.

Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made.-

This submittal shall contain:

An evaluation supporting the premise that the change did not reduce a.

the overall conformance of the solidified waste product to existing criteria for solid wastes; and b.

A reference to the date and the POSRC meeting number in which the change (s) yere reviewed and found acceptable to the POSRC.

2.

Shall become effective upon review and approval by the responsible Nuclear Power Department unit and approval of Plant Superintendent.

~

6.17 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.17.1 The ODCM shall be approved by the Commission prior to implementation.

6.17.2 Licensee initiated changes to the ODCM:

1.

Shall be submitted to the Commission in the Semlannual Radioactive Effluent Release Report for the period in which the change (s) was made effective. This submittal shall contain:

a.

Sufficient information to support the rationale for the change.

4 Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with a change number and/or change date together with appropriate analyses or evaluations justifying the change (s);

b.

A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and Documentation of the fact that the change has been reviewed and c.

found acceptable by the POSRC.

2.

Shall become effective upon review by the POSRC and approval of the Plant Superintendent.

CALVERT CLIFFS UNIT 1 6-23 Amendment No. 105

ADMINISTRATIVE CONTROLS 6.18 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6.18.1 Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid) shall be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the modification to the waste system is completed. The discussion of each change shall contain:

a.

A description of the equipment, components and processes involved.

b.

Documentation of the fact that the change including the safety analysis was reviewed and found acceptable by the POSRC.

4-CALVERT CLIFFS UNIT 1 6-24 Amendment No.105

1 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NOS.1 AND 2 APPENDIX B PARTI ENVIRONMENTAL TECHNICAL SPECIFICATIONS l

FACILITY OPERATING LICENSE NOS. DPR-53 AND DPR-69 2

DELETED See Appendix A Technical Specifications Sections 3/4.11 and 3/4.12 4-i

}

ISSUED BY THE U. S. NUCLEAR REGULATORY COMMISSION CALVERT CLIFFS UNIT 1 Amendment No. 23,70.,J00, 105 CALVERT CLIFFS UNIT 2 Amendment No. 7, 53, 82, 105

UNITED STATES g

g NUCLEAR REGULATORY COMMISSION 5

ej WASHINGTON, D. C. 20555 l

BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE I

Amendment No.86 License No. DPR-69 1.

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

A.

The application for amendment by Baltimore Gas & Electric Company (the licensee) dated October 11, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations 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) thit such activities will be conducted in compliance with the Comission's regulations; 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.

1

_.,-.n--,

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2 of Facility Operating License No. DPR-69 is hereby amended to read as follows:

2.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 86, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective July 1,1985.

FOR THE NUCLEAR REGULATORY COMMISSION Edward J. Bu cher, Acting Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

ATTACHMENT TO LICENSE AMENDMENT N0.86 FACILTIY OPERATING LICENSE N0. DPR-69 DOCKET N0. 50-318 Replace the following pages of the 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 overleaf pages are provided to maintain document completeness.

Appendix A Remove Pages Insert Pages IV IV VIIIa VIIIa XIII XIII XV XV XVI XVI 3/4 3-48 through 3/4 3-57 3/4 11-1 through 3/4 11-17 3/4 12-1 3/4 12-1 3/4 12-2 3/4 12-2 3/4 12-6 3/4 12-6 3/4 12-10 3/4 I?-10 3/4 12-11 3/4 12-11 3/4 1?-12 3/4 12-12 3/4 12-13 3/4 12-13 8 3/4 3-4 B 3/4 11-1 through B 3/4 11-6 6-7 6-7 6-11 6-11 6-12(nochange-repositioned) 6-12 (no change-repositioned) 6-13 6-13 6-16 6-16 6-17 6-17 6-18 6-18 6-18a 6-23 6-23 6-24 6-24 Appendix B Remove Appendix B in its entirety.

Insert the title page attached herewith.

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPL ICAB I L ITY...........................................

3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL Shutdown Margin - T,yg > 200 F.......................

3/4 1-1 0

Shutdown Margi n - T,yg < 200 F....................... 3/4 1 -3 Boron Dilution.......................................

3/4 1-4 Moderator Temperature Coefficient....................

3/4 1-5 Minimum Temperature for Criticality..................

3/4 1-7 3/4.1.2 B0 RATION SYSTEMS Fl ow Pa ths - Shu tdown................................

3/4 1 -8 Fl ow Pa t hs - Ope ra t i n g...............................

3/4 1 -9 Charging Pump - Shutdown............................. 3/4 1-10 Chargi ng Pumps - Operating........................... 3/4 1-11 Boric Acid Pumps - Shutdown.......................... 3/4 1-12 Boric Acid Pumps - Operating.........................

3/4 1-13 Borated Water Sources - Shutdown.....................

3/4 1-14 Borated Water Sources - Operating....................

3/4 1-16 3/4.1.3 MOVABLE CONTROL ASSEMBLIES Full Length CEA Position.............................

3/4 1-17 Position Indicator Channels..........................

3/4 1-21 CEA Drop Time........................................

3/4 1-23 Shutdown CEA Insertion Limits........................

3/4 1-24 Regulating CEA Insertion Limits......................

3/4 1-25 CALVERT CLIFFS - UNIT 2 III Amendment No. JA,81

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4. 2.1 L I NEAR HEAT RATE.......................................- 3/4 2-1 3/4.2.2 TOTAL PLANAR RADIAL PEAKING FACT 0R....................

3/4 2-6 3/4.2.3 TOTAL INTEGRATED RADI AL PEAKING FACTOR................ 3/4 2-9 3/4.2.4 AZ I MUTHAL POWE R T I LT.................................. 3/ 4 2-12 3/4.2.5 DNB PARAMETERS........................................

3/4 2-13 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION....................

3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION..................................... 3/4 3-10 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation..................

3/4 3-25 Incore Detectors......................................

3/4 3-29 Seismic Instrumentation...............................

3/4 3-31 Meteorological Instrumentation........................

3/4 3-34 Remote Shutdown Instrumentation.......................

3/4 3-37 Post Accident Instrumentation.........................

3/4 3-40 Fire Detection Instrumentation........................

3/4 3-43 Radioactive Gaseous Effluent Monitoring Instrumentation.....................................

3/4 3-47 l

Radioactive Liquid Effluent Monitoring Instrumentation.....................................

3/4 3-53 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION................. 3/4 4-1 Startup and Power.....................................

3/4 4-1 l

Ho t S t a n d by........................................... 3/ 4 4 - 2 S h u t d own.............................................. 3/4 4 -2a 3/4.4.2 SAFETY 'ALVES.........................................

3/4 4-3 3/4.4.3 RELIEF VALVES.........................................

3/4 4-4 CALVERT CLIFFS - UNIT 2 IV Amendment No.JE,)E,)E EJ, 86 l

~ - - ~ ~

C INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration.................................

3/4 11-1 Dose........................................

3/4 11-5 Liquid Radwaste Treatment System 3/4 11-6 4

3/4.11.2 GASEOUS EFFLUENTS 1

Dose Rate....................................

3/4 11-7 Dose-Noble Gase s..............................

3/4 11-11 Dose-lodine-131, and Radionuclides in Particulate Form 3/4 11-12 Gaseous Radwaste Treatment......................

3/4 11-13 Explosive Gas Mixture...........................

3/4 11-14 Gas Storage Tanks..............................

3/4 11-15 3/4.11.3 SOLID RADIOACTIVE WASTE.....................

3/4 11-16 3/4.11.4 TOTA L DOSE.................................

3/4 11-17 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGR AM........................

3/4 12-1 3/4.12.2 LAND USE CENSUS 3/4 12-12 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM.......

3/4 12-13 4

CALVERT CLIFFS UNIT 2 VIIIa Amendment No. 82,86

INDEX BASES SECTION PAGE 3/4.9.5 COMMU N I CAT I ON S......................................... B 3/ 4 9 -1 3/4.9.6 REFUELING MACHINE OPERABILITY........................r B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING............ B 3/4 9-2 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION.............. B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM.............. B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND SPENT FUEL POOL WATER LEVEL......................... B 3/4 9-3 3/4.9.12 SPENT FUEL P90L VENTILATION SYSTEM.................... B 3/4 9-3 3/4.9.13 SPENT FUEL CASK HANDLING CRANE........................

B 3/4 9-3 3/4.9.14 CONTAINMENT VENT ISOLATION VALVES..................... B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN.......................................

B 3/4 10-l 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION L I MI T S.............................................. B 3/4 10-1 3/4.10.3 NO FLOW TESTS......................................... B 3/4 10-1 3/4.10.4 CENTER CEA MISALIGNMENT............................... B 3/4 10-1 i

l 3/4.10.5 COOLANT CIRCULATION................................... B 3/4 10-1 3/4.11 RADI0 ACTIVE EFFLUENTS 1

3/4.11.1 LIQUID EFFLUENTS...................................... B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS..................................... B 3/4 11-2 3/4.11.3 SOLID RADI0 ACTIVE WASTE............................... B 3/4 11-5 l

3/4.11.4 TOTAL 00SE............................................

B 3/4 11-5 I

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PR0 GRAM.................................... B 3/4 12-1 3/4.12.2 LAND USE CENSUS....................................... B 3/4 12-1 l

3/4.12.3 INTERLABORATORY COMPARISON PR0 GRAM.................... B 3/4 12-2 CALVERT CLIFFS - UNIT 2 XIII Amendment No. 6,11.38,82,86 l

1

INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE

/

Map Defining the Site Boundary and Effluent Release Points..............................................

5-1 Low Popul a ti on Zone...........................................

5-1 5.2 CONTAINMENT Configuration.................................................

5-i Desi gn Pressure and Temperature...............................

5-4 5.3 REACTOR CORE Fu el As s emb l i e s...............................................

5-4 Control El ement As s embl i es....................................

5-4 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature...............................

5-4 Vo1ume........................................................

5-5 5.5 METEOROLOGICAL TOWER L0 CATION.................................

5-5 5.6 FUEL STORAGE Criticality...................................................

5-5 l

Drainage......................................................

5-5 i

Capacity.......................................................

5-5 i

5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS..........................

5-5 CALVERT CLIFFS - UNIT 2 XIV Amendment No.

82 I

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY.............................................,6-1 6.2 ORGANIZATION 0ffsite...................................................6-1 Fa c i.l i ty S t a f f............................................

6-1 6.3 FACILITY STAFF QUALIFICATIONS.............................

6-6 6.4 TRAINING..................................................

6-6 6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS AND SAFETY REVIEW COMMITTEE (POSRC)

Function................................................

6-6 Com po s i t i o n.............................................

6 - 6 Al t e r n a t e s..............................................

6-6 Meeting Frequency.......................................

6-7 Q u o r um..................................................

6 - 7 Re s po n s i b 11 1 t i e s........................~................

6-7 Authority...............................................

6-8 R e c o rd s.................................................

6 - 8 6.5.2 0FF SITE SAFETY REVIEW COMMITTEE (OSSRC)

Function................................................

6-8 Composition.............................................

6-9 i

Al t e rn a t e s..............................................

6-9 Consultants.............................................

6-9 Meeting Frequency.......................................

6-9 Quorum..................................................6-9 Review..................................................6-10 Audits..................................................6-11 A u t h o r i ty...............................................

6-12 l

Records.................................................6-12 XV CALVERT CLIFFS - UNIT 2 Amendment No. AA/, 86

-,----.--...--n

~

e

s-t, INDEX ADMINISTRATIVE CONTROLS

~

SECTION PAGE

! 6,. 6 REPORTABLE EVENT ACTI0N..................................'..

6-12 N

(

' k, 5. 7SAFETY LIMIT VIOLATION.................................... 6-13 g

j

(

'6.8 PRO C E DU R E S................................................. 6 - 13 s

1 6.9 RL' PORTING REQUIREMENTS

6. 9. '1 RO UT I N E RE PO RT S......"...................................

6-14

~

./

A 6.9.2 S PEC I AL REP 0 RTS.. u......................................

6-18 l

x s:,

g 4

I 4

6.10. RECORD 1ETENTION................................. i.......... 6-19 N

'. l 1-b1 I

' 6.11 RADI ATI_0N PROTECTION PR0 GRAM.............................. 6-20 4! (L '

'(

O 2 ' H IGH 1 AD I AT I ON A RE A.......................................

6-20

+

i h

I 6.13 ENVIRONMEATAL QUALIFICATION.......;........................

6-21 6.14 SYSTEM INTEGRITY..'........'...............................

6-21

?,

l 6 15 1001 NI M0N ITORI M......................................... 6-22 1.:

L 62 6, PROCESS CONTROL _PR0 GRAM...................................

6-23 i.. ;

6:17 0FFSITE DOSE CALCULATION MANUAL...........................

6-23 t

6.18 MJOR CHANGES TO RADIOACTIVE LIQUID. GASEOUS AND SOLID WASTE TREATMENT SYSTEMS...........................

6-24 I

i

\\

CALVERT CLIFFS - UNIT 2 XVI Amendment No.H,36,75, t

I

\\. \\

i s

r INSTRUMENTATION R ADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 1

l 1

LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The alarm / trip se.tpoints of these channels shall be determined and adjusted in accordance with the meihodology and parameters in the ODCM.

APPLICABILITY: As shown in Table 3.3-12 i

ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Specification, without delay suspend the release of radioactive gaseous effluents monifored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in 5

Table 3.3-12 Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was noi corrected in a timely manner.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be l

demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the i

frequencies shown in Table 4.3-1L I

i i

CALVERT CLIFFS UNIT 2 3/4 3-48 Amendment No. 86 i

c p,

TABLE 3.3-12 RADIOACTIVE GASEOUS EFFhUENT MONITORING INSTRUMENTATION s

7 MINIMUM CHANNELS j

INSTRUMENT OPERABLE APPLICABILITY ACTION G

1.

WAS1E GAS HOLDUP SYSTEM h

N a.

Noble Gas Activity monitor -

Providing Alarm and Automatic Termination of Release (1) 33 b.

Effluent System Flow Rate Measuring Device (1) 36 2.

MAIN VENT SYSTEM a.

Noble Gas Activity Monitor (1) 37 b.

Iodine Sampler (1) 38 c.

Particulate Sampler (1) 38 4

El Es k

E

TABLE 3.3-12 (Centinued)

TABLE NOTATION 5

At all times.

ACTION 35 -

With the number of channels OPERABLE less than rekuired by the t

Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment:

~

Using the main vent monitor as a backup and recording RMS a.

readings every 15 minutes during the release, or b.

Provided that prior to initiating the release, 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 the release rate calculations and two qualified operators verify the discharge valve lineup.

Otherwise, suspend release of radioactive effluents via this pathway.

j ACTION 36 -

With the number of channels OPERABLE less than required by the i

Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 37 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided either (1) grab samples are taken and analyzed for gross activity at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or (2) an equivalent monitor is provided.

ACTION 38 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the aflected pathway may continue provided samples are continuously, collected as required in Table 4.11-2 with auxiliary samp!!ng equipment.

l l

CALVERT CLIFFS UNIT 2 3/4 3-30 Amendment No. 86 l

l

o TABLE 4.3-11 h

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS h

CHANNEL MODES IN WHICH 4

CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED G

b 1.

WASTE GAS HOLDUP SYSTEM m

a.

Noble Gas Activity Monitor -

Providing Alarm and Automatic Termination of Release P

P R(3)

SA(1) b.

Effluent System Flow Rate Measuring Device D(4)

N.A.

R N.A.

T e

2.

MAIN VENT SYSTEM 4's a.

Noble Gas Activity Monitor D

M R(3)

SA(2) b.

Iodine Sampler W

N.A.

c.

Particulate Sampler W

N.A.

$it a

A

TABLE 4.3-11 (Ccntinued) 4 TABLE NOTATION At all times other than when the line is valved out and locked.

(1)

The CHANNEL FUNCTIONAL TEST shall also demonstrate the autoriatic isolation of this pathway and/or control room alarm annunciation occurs if the appropriate following condition (s) exists:

1.

Instrument indicates measure levels above the alarm / trip setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

(2)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

1.

Instrument indicates measured levels above the alarm sety at.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

(3) iThe initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards traceable to the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system within its intended range of energy and measurement range.

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

(4)

The CHANNEL CHECK shall consist of verifying indication of flow during periods of release and shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which effluent releaws are made.

l l

l i

l CALVERT CLIFFS UNIT 2 3/4 3-52 Amendment No. 86 i

INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERAB1:E with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.

The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: At all times.

ACTION:

a.

With a radioac,tive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative, b.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-

13. Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

c.

SURVEILLANCE REQUI' EMENTS R

4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST cperations at the frequencies shown in Table 4.3-12.

8

+

l l

CALVERT CLIFFS UNIT 2 3/4 3-53 Amendment No.

86

TABLE 3.3-13 RADIOACTIVE LIQUlO EFFLUENT MONITORING INSTRUMENTATION g

h 5

9 5

MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION 1.

GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a.

Liquid Radwaste Effluent Line (1) 28 b.

Tieam Generator Blowdown Effluent Line (1) 29 2.

FLOW ;:fiTE MEASUREMENT DEVICES T

e a.

Liquid Radwaste Effluent Line (1) 33 b.

Steam Generator Blowdown Effluent Line (1) 30 g

n

.if

TABLE 3.3-13 (Centinued)

TABLE NOTATION

!(

ACTION 28 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release:

At least two independent samples are analyzed in accordance with a.

Specification 4.11.1.1.1, and b.

At least two technically qualified members of the Facility Staff independently verify the release rate calculations and two qualified operators verify the discharge valve line up.

ACTION 29 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross radioactivity (beta or gamma) at the lower limit of detection defined in Table 4.11-1:

a.

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

b.

At least once per 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie / gram DOSE EQUIVALENT l-131.

A-ACTION 30 -

With the number of channels OPERABLE less than required by th'e Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump performance curves may be used to estimate flow.

CALVERT CLIFFS UNIT 2 3/4 3-55 Amendment No. 86

_ TABLE 4 3-12 RADIOACTIVE LIQUID E' FLUENT MONITORING INSTRUMENTA F

9_

MENTS h

8 INSTRUMENT CHANNEL SOURCE CHANNEL FUNCTIONAL ro CHECK CHECK CAllBRATION 1.

GROSS RADIOACTIVITY MONITO'RS PROYlDING TEST ALARM AND AUTOMATIC TERMINATION OF RELEASE Liquid Radwaste Effluent Line a.

D P

R(2)

SA(1) b.

Steam Generator Blowdown Effluent Line D

P R(2)

SA(1)

}

2.

FLOW RATE MEASUREMENT DEVICES y

a.

Liquid Radwaste Effluent Line E

D(3)

N.A.

R b.

Steam Generator Blowdown Effluent Line N.A.

D(3)

N.A.

R N.A.

k i,-

et

.O

TABLE 4.312 (Continued)

TABLE NOTATION (1)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and/or control room alarm annunciation occur if the appropriate following condition (s) exists:

1.

Instrument indicates measured levels above the alarm / trip setpoir}t.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

(2)

The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards traceable to the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system within its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration can 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which effluent releases are made.

l CALVERT CLIFFS UNIT 2 3/4 3-57 Amendment No. 86 i

j

3/4.11 RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS 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.

r APPLICABILITY: At all times.

ACTION:

a With the concentration of radioactive material released in liquid effluents to a.

UNRESTRICTED AREAS exceeding the above limits, without delay restore the concentration to within the above limits.

y b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

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 ODCM to assure that the concentrations at the point of release are maintained within the limits of Specification 3.11.1.1.

l CALVERT CLIFFS UNIT 2 3/411-1 Amendment No.

86

TABLE 4.11-1 RADIOACTIVE L10U1D WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit of Detection Liquid Release Sampling Analysis Type of Activity (LLD)*

Type Frequency Frequency Analysis (uCi/ml)

A.

Batch Wgste P

P Releases Each Batch Each Batch Principal Gamma 5x10'7 Emitterse I-131 lx104 Mo-99, Ce-144 2x104 P

M H-3 lx10-5 d

Each Batch Composite Gross Alpha Ix10-7 Each Batch Com sited Sr-89, Sr-90 3x10-8 B.

Turbine Building M

M Principal Gamma 5x10-7 Sump EmittersC 1-131 lx1076 Mo-99, Ce-144 2x10-6 CALVERT CLIFFS UNIT 2 3/411-2 Amendment No. 86 l

q TABLE 4.11-1 (Continued)

TABLE NOTATION a 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.

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

LLD =

4.66sb 6

E*

V 2.22 x 10 y

exp (- Aat)

Where:

LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, i

sb s the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 6

2.22 x 10 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, Ais the radioactive decay constant for the particular radionuclide, and a t is the elapsed time between sample ecliection, or end of the sample collection period, and time of counting.

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.

b Prior to sampling Reactor Coolant Waste and Miscellaneous Waste for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.

4 CALVERT CLIFFS UNIT 2 3/411-3 Amendment No. 86

TABLE 4.11-1 (Continued)

TABLE NOTATION c The principal gamma emitters for which the LLD specification applies exclusive the following radionuclides:

Mn-54, Fe-59, Co-58, Co-60, 2n-65, Cs-134, Cs-137 and Ce-141. 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 6uclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Repo pursuant to Specification 6.9.1.8.

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

(

l CALVERT CLIFFS UNIT 2 3/411-4 Amendment No. 86 l

l

RADIOACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC frorn radioactive materials in liquid effluents released to UNRESTRICTED AREAS shall be limited:

During any calendar quarter to less than or equal to 3.0 mrems to the total a.

body and to less than or equal to 10 mrems to any organ, and b.

During any calendar year to less than or equal to 6 mrems to the total body and to less than or equal to 20 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

With the calculated dose from the release of radioactive materials in liquid a.

effluents exceeding any of the above limits, 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 that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits, b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Monthly cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 60 days.

CALVERT CLIFFS UNIT 2 3/4.!-5 Amendment No. 86

RADIOACTIVE EFFLUENTS LIQUID RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste treatment system shall be used to reduce't$e radioactive materials in liquid wastes prior to their discharge when the calculated doses due to the liquid effluent to UNRESTRICTED AREAS exceeds 0.36 mrem to the total body or 1.20 mrem to any organ in a 92 day period.

APPLICABILITY: At all times.

ACTION:

With radioactive 11guld waste being discharged without treatment and in a.

excess of the above limits, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report that includes the following information:

1.

Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the Inoperability, 2.

Action (s) taken to restore the Inoperable equipment to OPERABLE status, and 3.

Summary description of action (s) taken to prevent a recurrence.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.3 Monthly doses the to liquid releases to UNRESTRICTED AREAS shall be calculated at least once per 60 days in accordance with the methodology and parameters in the ODCM.

CALVERT CLIFFS UNIT 2 3/4 11-6 Amendment No. 86 i

l l

RADIOACTIVE EFFLUENTS GASEOUS EFFLUENTS DOSE RATE LIMITING CONDITION FOR OPERATION 3.11.2.1 The dose rate due to radioactive materials released in gaseous e fluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) shall be limited to the following:

a.

For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and b.

For iodine-131 and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.

s APPLICABILITY: At all times.

ACTION:

m With the dose rate (s) exceeding the above limits, without delay restore the a.

release rate to within the above limit (s).

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to' be within the above limits in accordance with the methodology and parameters in the ODCM.

4.11.2.1.2 The dose rate due to lodine-131 and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM by j

obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2.

l l

CALVERT CLIFFS UNIT 2 3/4 11-7 Amendment No. 86 l

TABLE 4.11-2 o

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM q

Minimum Lower Limit of h

Sampling Analysis Type of Detection (LLD)a g

Gaseous Release Type Frequency Frequency Activity Analysis (uCi/ml)

P P

d A. Waste Gas Storage *8 Each Tank Each Tank Principal Gamma Emittersb f

lxt0-4 g

Tank Grab Sample (Gaseous Emissions Only)

P P

B.

Containment Purge Each Batche Each Batche Principal Gamma Emittersb lx10-4 m

and Vent Grab Sample (Gaseous Emissions Only)

C.

Main Vent M

MC Principal Gamma Emittersh lx10-4 c

Grab Sample (Gaseous Emissions Only) l Continuousd M

H-3 Ix104 Y

s-w Continuousd W

1-131 1x10-12 "g

Charcoal Sample

Continuousd W

Principal Gamma Emittersb lx10-II Particulate (I-131, others)

Sample' Continuousd M

Gross Alpha Ix10-II Composite Particulate Sample Continuoosd Q

Sr-89, Sr-90 lx10-II Composite Particulate Sample p

A Continuousd Noble Gas Noble Gases lx104 Monitor Gross Beta or Gamma D., cine,a,ee olie e

e m _,

m _,

i TABLE 4.11-2 (Continued)

TABLE NOTATION l

=

a 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:

LLD =

4.66sb 2.22 x 106 E-V y

exp ( Aat)

Where:

LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, i

sh s the standard deviation of the background counting rate or of the counting rate i

of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, 1

V is the sample size in units of mass or volume, 6

2.22 x 10 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and At for plant effluents is the elapsed time between sample collection or end of the rample collection period, and time of counting.

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.

i CALVERT CLIFFS UNIT 2 3/4 11-9 Amendment No. 86 j

TABLE 4.11-2 (Continued)

TABLE NOTATION b The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60,2n-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be conMdered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Seminannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.8.

c Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour unless (1) analysis shows that the DOSE EQUIVALENT l-131 concentration in the primary coolant has not increased more than a factor of 5, and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 5.

d 1

The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1,3.11.2.2 and 3.11.2.3.

Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or after removal from sampler.

When sample

,- r ollection time is less than seven days, the corresponding LLDs may be increased by,a.

c proportional factor. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 5, and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 5.

I Waste Gas Decay Tank samples shall be collected and analyzed for oxygen once per week on the in-service tank and following tank isolation. Waste Gas Surge Tank-samples shall be collected and analyzed daily during power escalation frcm MODE 6 through MODE 3, and once per week at all other times.

8 Collect sample and analyze daily for total Curie content per Specification 3.11.2.6 when the Reactor Coolant System specific activity of Xe-133 is greater than 150 uCi/ml.

h Incinerated oil may be discharged via points other than the main vent (e.g., Auxiliary Boiler). Releases shall be accounted for based on pre-release grab sample data.

1 Samples for incinerated oil releases shall be collected from and representative of filtered oil in liquid form.

CALVERT CLIFFS UNIT 2 3/4 11-10 Amendment No. 86

RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION l'

3.11.2.2 The air dose due to noble gases released in gaseous effluents to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) shall be limited to the following:

During any calendar quarter: Less than or equal to 10 mrads for gamma a.

radiation and less than or equal to 20 mrads for beta radiation and, b.

During any calendar year:

Less than or equal to 20 mrads for gamma radiation and less than or equal to 40 mrads for beta radiation.

APPLICABILITY: At all times.

ACTION:

With the calculated air dose from radioactive noble gases in gaseous a.

effluents exceeding any of the above limits, 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 that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

1 b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.2 Monthly cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 60 days.

CALVERT CLIFFS UNIT 2 3/4 11-11 Amendment No. 86

C RADIOACTIVE EFFLUENTS DOSE -IODINE-131 AND RADIONUCLIDES IN PARTICULATE FORM LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from lodine-131 and "al ra in particulate form with half lives greater than 8 days in gaseous effluents released to areas at and beyond the SITE BOUNDARY (see Figure 3.1 1) shall be limited to the following During any calendar quarter:

a.

and, Less than or equal to 15 mrems to any organ b.

During any calendar years Less than or equal to 30 mrems to any organ,

Less than 0.1% of the limits of 3.II.2.3(a) and (b) as a result of burning c.

contaminated oil.

APPLICABILITY: At all times.

4

_ ACTION:

i With the calculated dose from the release of lodine-131 and radionuclides in a.

particulate form with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, 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 and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in comp!!ance with the above limits.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Monthly cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131 and radionuclides in particulate form with half lives t

greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 60 days.

I J

CALVERT CLIFFS UNIT 2 3/411-12 Amendment No. 86 1

\\

1 1

RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPER ATION 3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM and the. VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the gaseous effluent air doses due to gaseous effluent releases, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1) exceeds 1.20 mrad for gamma radiation and 2.4 mrad for beta radiation in a 92 day period.

The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the calculated doses due to gaseous effluent releases, to areas at and beyond the SITE BOUNDARY (see Figure 3.1-1) exceeds 1.8 mrem to any organ in a 92 day period.

i APPLICABILITY: At all times.

ACTION:

With gaseous waste being discharged without treatment and in excess of the a.

above limits, prepare and submit to the Commission within 30 days, pursuant Specification 6.9.2, a Special Report that includes the following to information:

1 1.

Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability, 2.

Action (s) taken to restore the incperable equipment to OPERABLE status, and 4

l 3.

Summary description of action (s) taken to prevent a recurrence.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4.

Monthly doses due to gaseous releases shall be calculated at least once per 60 days in accordance with the methodology and parameters in the ODCM.

CALVERT CLIFFS UNIT 2 3/4 11-13 Amendment No. 86

r-RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE (Hydrogen rich systems not designed to withstand a hydrogen explosion)

LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 4% by volume.

APPLICABILITY: At all times ACTION:

With the concentration of oxygen in a waste gas decay tank greater than 4%

a.

by volume immediately suspend all additions of waste gases to that tank and reduce the concentration of oxygen to less than or equal to 4% by volume without delay.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS l

4.11.2.5 The concentrations of oxygen in the waste gas holdup system shall be determined to be within the above limits by the sampling program described in Table 4.11-2.

l i

CALVERT CLIFFS UNIT 2 3/4 11-14 Amendment No. 86

RADIOACTIVE EFFLUENTS GAS STOR AGE TANKS LIMITING CONDITION FOR OPER ATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank s,hil be limited to less than or equal to 58,500 curies noble gases (considered as Xe-133).

APPLICABILITY: At all times.

ACTION:

With the quantity of radioactive rnaterial in any gas storage tank exceeding a.

the above limit, immediately suspend all additions of radioactive material to that tank and 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.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

_ SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in the in-service gas storage tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the Reactor Coolant System specific activity of Xe-133 is greater than 150 uCi/ml.

w e

CALVERT CLIFFS UNIT 2 3/4 11-15 Amendment No. 86

RADIOACTIVE EFFLUENTS SOLID RADIOACTIVE WASTE LIMITING CONDITION FOR OPERATION 3.11.3 The solid radwaste program shall be used in accordance witE a PROCESS CONTROL PROGRAM to process wet radioactive wastes to meet shipping and burial ground requirements.

APPLICABILITY: At all times.

ACTION:

With the provisions of the PROCESS CONTROL PROGRAM not satisfied, a.

suspend shipments of defectively processed or defectively packaged solid radioactive wast,es from the site.

b.

The provision of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.3 THE PROCESS CONTROL PROGRAM shall be used to verify the.

SOLIDIFICATION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive waste (e.g., filter sludges, spent resins, evaporator i

bottoms, boric acid solutions, and sodium sulfate solutions).

i v-i 2

CALVERT CLIFFS UNIT 2 3/4 11-16 Amendment No. 86 i

_ _ _ _ _ _ _ _ _ _ _. _ _ _ _. _ _ _ _ _, _ _ ~,. _ _,

4 1

l RADIOACTIVE EFFLUENTS TOTAL DOSE LIMITING CONDITION FOR OPERATION 4

3.11.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuefcycle sources 4

shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyrold, which shall be limited to less than or equal to 75 mrems.

APPLICABILITY: At all times.

l ACTION:

With the calculated doses from the release of radioactive materials in liquid a.

4 or gaseous effluents exceeding twice the limits of Specification 3.II.l.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.II.2.2.b, 3.11.2.3.a, or 3.ll.2.3.b, calculations shall be made including direct radiation contributions from the reactor units and outside storage tanks to determine whether the above limits of Specification 3.11.4 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.405c, she.Il include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this a

report.

It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already-been corrected, the Special Report shall include a request for a variance in accordance with the provisici s of 40 CFR Part 190. Submittal of the report Is considered a timely request, and a variance is granted until staff action on 9'

the request is complete.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not app!! cable.

SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be i

determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the ODCM.

4.11.4.2 Cumulative dose contributions from direct radiation from the reactor units and outside storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in Specification 3.11.4.a.

k CALVERT CLIFFS UNIT 2 3/4 11-17 Amendment No. 86 l

J

4 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 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 conducted a.

as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Specification 6.9.1.7, a description of the reasons for not conducting the program as required and riv plans for preventing a recurrence.

b.

With the level of radiaactivity as the result of plant effluents in an environmental sample at a specified location exceeding the reporting levels of Table 3.12-2, prepare and submit to the Commission within 30 days after receiving the sample analysis, 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 dose

to a MEMBER O? THE PUBLIC is less than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2, and 3.11.2.3. When more than one of the radionuclides in Table 3.12-2 are detected in the sample this report shall be submitted if:

concentration (1) + concentration (2) +..> l.0 reporting ievel (1) reporting level (2)

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 is equal to or greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition sha!! be reported and described in the Annual Radiological Environmental Operating Report.

CALVERT CLIFFS UNIT 2 3/4 12-1 Amendment Nn. 82, 86

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING ACTION: (Continued) c.

With fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days.

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

Pursuant to Specification 6.9.1.7, identify the cause of the l

unavailability of samples and Identify the new location (s) for obtaining the replacement samples in the next Annual Radiological Environmental Operating Report.

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 i

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.

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

CALVERT CLIFFS UNIT 2 3/4 12-2 Amendment No. 81,86

4 I

TABLE 3.12-1 (Continued) 9

~

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3 ~ Exposure Pathway Number of Representative Sampling and Jype and Frequency, and/or Sample Samples and Sample Locations, Collection Frequency of Analysis n

d

b. Food Products Samples of 3 different kinds of Ponthly during growing Gama isotopic and broad leaf vegetation grown,near season.

I-131 analysis.

I m

I the site boundary at 2 different g

locations of highest predicted a

annual average groundlevel D/Q (Ibl-Ib6).

m s

d 1 sample of each of the similar Monthly during growing Gamma isotopie and broad leaf vegetation grown 15-season.

1-131 analysis.

30 km distant in the least prevalent wind direction (Ib7-g Ib9).

N

~

e, j

r a

i an v

4 TABLE 3.12-1 (Continued) o h

\\

TABLE NOTATION a

a The code in parenthesis, e.g. DRI, Al, defines generic sample locations in this specification that can be used to h

identify the specific locations in the map (s) and table in the ODCM. Specific parameters of distance and direction y

sector from the central point between the twd containment buildings and additional description where pertinent, is

[

g provided for each sample location in Table 3.12-1, and in a table and figure (s) in the ODCM. Refer to NUREG-0133, g

" Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, October 1978", and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the H

N required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction of automatic sampling couipment. If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7.

It is recognized thEt, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these

?

instances suitable alternative media and locations may be chosen for the particular pathway in question aad appropriate substitutions made within 30 days in the radiological environmental monitoring program. Pursuant to Specification 6.9.1.7, identify the cause of the unavailability of samples for that pathway and identify the new location (s) for obtaining samp)les in the next Annual Radiological Environmental Operating Report and also include in the report a w

h revised figure (s and table for the ODCM reflecting the new location (s).

b 1

'P One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may m

be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading. Due to the geographical limitations,9 sectors are monitored F

around the Calvert Cliffs Nuclear Power Plant.

8. c Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times

{

the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

e in

e 4

TABLE 4.12-1 0

\\

N, DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSISa,b g

LOWER LIMIT OF DETECTION (LLD)c h

Airborne Particulg)te Water Fish & Invertebrates Milk Food Products Sediment Analysis (pCi/l) or Gases (pCi/m (pCi/kg, wet)

(pCi/l)

(pCi/kg, wet)

(pCifkg, dry)

Gross Beta 4

0.01 H-3 2000*

Mn-54 15 l30 Fe-59 30 260 Co-58,60 15 130 e

{

Zn-65 30 260 Zr-Nb-95 15 d

I-131 I

0.07 1

60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 f

1f no drinking water pathway exists, a value of 3000 pCi/l may be used.

a

!?

TABLE 4.12-1 (Continued)

TABLE NOTATION a

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 Radiological Environmental Oper~ating Report pursuant to Specification 6.9.1.7.

b Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.

c 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 sys'em 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:

4.66sb 2.22 Y

exp (- Aa t)

E-V Where:

LLD is the "A priori" lower limit of detection as defined above, as picocuries per unit mass or volume, sb s the standard deviation of the background counting rate or of the counting.

i rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, l

V is the sample size in units of mass or volume, 1

l 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield, when applicable, 1 is the radioactive decay constant for the particular radionuclide, and l

6 t for environmental samples is the elapsed time between sample collection, or l

end of the sample collection period, and time of counting Typical values of E, V, Y and at should be used in the calculation.

i CALVERT CLIFFS UNIT 2 3/4 12-10 Amendment No. 82, 86

TABLE 4.12-1 (Continued)

TABLE NOTATION 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 perforrned 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 6.9.1.7.

d LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.

v-CALVERT CLIFFS UNIT 2 3/4 12-11 Amendment No.82, 86

3/4.12 J1AD,I,0kOGICAL ENVIRONMENTAL MONITORING LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 9 meteorological sectors of ty(nearesj) milk animal, t nearest residence and the nearest garden

of greater than 50 m 500 ft producing bror.d leaf vegetation. (For elevated releas.s as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify within a distance of 5 km (3 miles) the locations in each f the 9 meteorological sectors of all milk animals and all gardens of 2

greater than 50 m producing broad leaf vegetation).

APPLICABILITY: At all times.

ACTION:

a.

With a land use census identifying a location (s) that yields a calculated dose or

~

dose commitment greater than the values currently being calculated in Specification 4.11.2.3, identify the new location (s) in the next Annual Radiological Environmental Operating Report, pursuant to Specification 6.9.1.7 b.

With a land use census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the new location (s) to the radiolog(ical envlonmental monitoring program within 30 days. The sampling location s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted. Pursuant to Specification 6.9.1.7, identify the new location (s) in the next Annual Radiological Environmental Operating Report and also laclude in the report a revised figure (s) and table for the ODCM reflecting the new 4

location (s).

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS l

4.12.2 The land census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental pperating Report pursuant to Specification 6.9.1.7

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census.

Specifications for broad leaf vegetation sampling in Table 3.12-1.4b shall be followed, including analysis of control samples.

CALVERT CLIFFS - UNIT 2 3/4 12-12 Amendment No. 87,86; I

3/4.12 RADIOLOGICAL ENVIRONMENTAL M NITORING 1

INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission, that correspond to samples required by Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

a.

With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Specification l

6.9.1.7.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

~

SURVEILLANCE REQUIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in the ODCM. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7.

i

+

l l

l CALVERT CLIFFS UNIT 2 3/4 12-13 Amendment No. PL86 l

l

INSTRUMENTATION BASES 3/4.3.3.6 POST-ACCIDENT INSTRUMENTATION The OPERABILITY of the post-accident instrumentation ensores that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, "Instru-mentation for Light-Water-Cooled Nuclear Plants to Assess Plant Conditions During and Following an Accident," December 1975, and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."

3/4.3.3.7 FIRE DETECTION INSTRUMENTATION OPERALILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages.

Prompt detection of fires will reduce the poten-tial for damage to safety related equipment and is an integral element in the overall facility fire protection program.

In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to operability.

3/4.3.3.8 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION IODINE AND PARTICULATE SAMPLER The OPERABILITY of the Iodine and Particulate Sampler ensures that Iodine and Particulate Samples can be obtained for analysis during and v-following an accident. The surveillance requirements ensure a high degree of availability.

The sampler was installed to meet the requirements of NUREG-0737 Item II.F.1.

The sampler's operation was not assumed in any accident analysis.

CALVERT CLIFFS - UNIT 2 B 3/4 3-3 Amendment No. JJ, M,81

INSTRUMENTATION BASES 3/4.3.3.9 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to-monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of Specifica-tion 3.ll.2.1.a based on average annual X/Q. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

3/4.3.3.10 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure

.that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

~1 -

CALVERT CLIFFS - UNIT 2 B 3/4 3-4 Amendment No. 86

RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 1

3/4.11.1.1 CONCENTRATION This specification is provided to ensure that the concentration of radioactive materials i

released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design objectives of Appendix I,10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part 20.106(e) to the population.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300,

~

Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination -

Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, 3. K.,

" Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

3/4.11.1.2 DOSE l

This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I,10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in-Section IV.A of Appendix ! to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable."

The dose calculation methodology and parameters in the ODCM implement the T

, requirements in Section III.A of Appendix ! that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977, Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977, and NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants".

i CALVERT CLIFFS UNIT 2 B 3/411-1 Amendment No.86

..~..

RADIOACTIVE EFFLUENTS BASES (Continued) 3/4.11.1.3 LIQUID RADWASTE TREATMENT SYSTEM

}

The requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable".

This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 4

CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part

50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I,10 CFR Part 50, for liquid effluents.

3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE l

This specification is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS. The annual dose limits are i

. the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1.

These limits prov"de reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, exceeding the limits specified in Appendix B, l

Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE i

PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.

The required detection capabilities for radioactive materials in gaseous waste samples v-are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination -

Application to Radiochemistry," Anal. Chem. 40. 586-93 (1968), and Hartwell, 3.K.,

i

" Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

l l

CALVERT CLIFFS UNIT 2 B 3/411-2 Amendment No. 86 3

t

- - - - - - -.. ~,, _, - ~ _. _. -., _,...

,,_._.m r--.-

F RADIOACTIVE EFFLUENTS B ASES (Continued) 2 3/4.11.2.2 DOSE - NOBLE GASES This specification is provided to implement the requirements of Sections 11.B, III.A and IV.A of Appendix I,10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix 1 to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revisien 1, July 1977, and NUREG-0133 " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants".

The ODCM equations provided for determining the air doses at and beyond the SITE l

BOUNDARY are based upon the historical annual average atmospheric conditions.

4 i

l l

i

{

l CALVERT CLIFFS UNIT 2 B3/411-3 Amendment No. 86 r-

RADIOACTIVE EFFLUENTS BASES (Continued) 3/4.11.2.3 DOSE -IODINE 131 AND RADIONUCLIDES IN PARTICULATE FORM This specification is provided to implement the requirements of Sections ll.C, III.A and IV.A of Appendix I,10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix 1.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable."

The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix 1 that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109,

" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 30, Appendix I," Revision 1, October 1977, Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,"

Revision 1, July 1977, and NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants". These equations also provide for.

determining the actual doses based upon the historical annual average atmospheric conditions.

The release rate specifications for iodine-131 and radionuclides in particulate form with half lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were:

1) individual inhalation of airborne radionuclides,2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas-where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

3/4.11.2.4 GASEOUS RADWASTE TREATMENT SYSTEM i

The requirement that the appropriate portions of these systems be used, when specified, i

provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable".

This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose j

design objectives set forth in Sections II.B and II.C of Appendix I,10 CFR Part 50, for gaseous effluents.

CALVERT CLIFFS UNIT 2 B 3/411-4 Amendment No. 86

RADIOACTIVE EFFLUENTS BASES (Continued) 3/4.11.2.5 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limit of oxygen.

Maintaining the concentration of oxygen below its flammability limit provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

3/4.11.2.6 GAS STORAGE TANKS The tanks included in this specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by another Technical Specification to a quantity that is less than the quantity that provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed 10 CFR 100 limits.

Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed accident guidelines.

3/4.11.3 SOLID RADIOACTIVE WASTE This specification implements the requirements of 10 CFR Part 50.36a and General design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters are-included in the PROCESS CONTROL PROGRAM.

-3/4.11.4 TOTAL DOSE This specification is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrems to the total body or any organ, except the thyroid, which shall be limited to sess than or equal to 75 l

mrems. The Special Report will describe a course of action that should result in the i

limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part i

190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cytle sources is negligible.

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CALVERT CLIFFS UNIT 2 B 3/411-5 Amendment No. 86 l

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RADIOACTIVE EFFLUENTS BASES (Continued) l If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part6 20.405c, is considered to be a timely request and fulfilis the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Specifications 3.11.1.1 and 3.11.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

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CALVERT CLIFFS UNIT 2 B 3/411-6 Amendment No. 86

ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.l.4 The POSRC shall meet at least once per calendar month anh as convened by the POSRC Chairman or his designated alternate.

QUORUM 6.5.1.5 A quorum of the POSRC shall consist of the Chaiman or his designated alternate and four members including alternates.

RESPONSIBILITIES 6.5.1.6 The POSRC shall be responsible for:

Review of l) all procedures required by Specification 6.8 and changes a.

thereto, 2) any other proposed procedures or changes thereto as determined by the Plant Superintendent to affect nuclear safety, b.

Review of all proposed tests and experiments that affect nuclear safety.

Review of all proposed changes to Appendix "A" Technical Specifications.

c.

d.

Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.

Investigation of all violations of the Technical Specifications includ-e.

ing the preparation and forwarding of reports covering evaluation and recomendations to prevent recurrence to the Manager - Nuclear Power Department and to the Chairman of the Off Site Safety Review Comittee.

f.

Review of all REPORTABLE EVENTS.

g.

Review of facility operations to detect potential safety hazards.

h.

Perfomance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Off Site Safety Review

)

Comittee.

v 1.

Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the Off Site Safety Review Comittee.

j. Review of the Emergency Plan and implementing procedures and shall submit recomended changes to the Off Site Safety Review Comittee.

k.

Review of any accidental, unplanned or uncontrolled radioactive release that exceeds 25% of the limits of Specification 3.11.1.2, 3.11.2.2 or 3.11.2.3, including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent 4

recurrence and for forwarding of these reports to the Plant Superinten-l dent anc' the Off Site Safety Review Comittee.

l.

Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL.

CALVERT CLIFFS - UNIT 2 6-7 Amendment No. JJ.J5.26,75 86 i

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ADMINISTRATIVE CONTROLS AUTHORITY 6.5.1.7 The Plant Operations and Safety Review Committee.'shall:

a.

Recomend to th'e Plant Superintendent written approval or disap-l proval of items considered under 6.5.1.6(a) through (d) above, b.

Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.

c.

Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Manager -

l Nuclear Power Department and the Off Site Safety Review Comittee of disagreement between the POSRC and the Plant Superintendent; however, the Plant Superintendent shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

j RECORDS 6.5.1.8 The POSRC shall maintain written minutes of each meeting and copies shall be provided to the Manager - Nuclear Power Department J

and Chaiman of the Off Site Safety Review Comittee.

6.5.2 0FF SITE SAFETY REVIEW COMMITTEE (OSSRC) j FUNCTION 6.5.2.1 The Off Site Safety Review Committee shall function to provide independent review and audit of designated activities in the y-areas of:

a.

nuclear power plant operations b.

nuclear engineering c.

chemistry and radiochemistry i

d.

metallurgy and non-destructive examination l

f e.

instrumentation and control f

f.

radiological safety f

g.

mechanical and electrical engineering i

h.

quality assurance practices CALVERT CLIFFS - UNIT 2 6-8 Amendment No.26 I

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ADMINISTRATIVE CONTROLS B

6 AUDITS I

6.5.2.8.1 Audits of facility activities shall be performed under the cog-nizance of the OSSRC. These audits shall encompass:

The confomance of facility operation to provisions contained within a.

the Technical Specifications and applicable license conditions at least once per 12 months.

b.

The perfomance, training and qualification of the entire facility staff at least once per 12 months.

The results of actions taken to correct deficiencies occurring in c.

facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.

d.

The performance of activities required by the Quality Assurance Program to meet the criteria of Appendix "B",10 CFR Part 50, at least once per 24 months.

e.

Deleted.

f.

The Safeguards Contingency Plan and implementing procedures at least once per 12 months in accordance with 10 CFR 73.40(d).

g.

Any other area of facility operation considered appropriate by the OSSRC or the Vice President-Supply, h.

The Facility Fire Protection Program and implementing procedures at

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least once per 24 months.

1.

An independent fire protection and loss prevention program inspection v

and audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protection firm.

j. An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant at least once per 36 months.

k.

The radiological environmental monitoring program and the results thereof at least once per 12 months.

1.

The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.

m.

The PROCESS CONTROL PROGRAM and implementing procedures for proces-sing and packaging of radioactive wastes at least once per 24 months.

n.

The performance of activities required by the Quality Assurance

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Program for effluent and environmental monitoring at least once per 12 months.

CALVERT CLIFFS - UNIT 2 6-11 Amendment No. JJ,$5,.86

ADMINISTRATIVE CONTROLS 6.5.2.8.2 Review of facility activities shall be performed under the cognizance of the OSSRC. These reviews shall encompass:

a.

The Facility Emergency Plan and implementing procedures at least once per 12 months in accordance with 10 CFR Part 50.54(t).

AUTHORITY 6.5.2.9 The OSSRC shall report to and advise the Vice President-Supply on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

RECORDS i

6.5.2.10 Records of OSSitC activities shall be prepared, approved and distributed as indicated below:

a.

Minutes of each OSSRC meeting shall be prepared, approved and forwarded to the Vice President-Supply within 14 days following each meeting.

b.

Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Vice President-Supply within 14 days following completion of the review.

c.

Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Vice President-Supply and to the management positions responsible for the areas audited within 30 days after i

completion of the audit.

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6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a.

The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR l

Part 50, and b.

Each REPORTABLE EVENT shall be reviewed by the POSRC and the results of this review shall be submitted to the OSSRC and the Manager - Nuclear Power Department.

CALVERT CLIFFS - UNIT 2 6-12 Amendment No. 26,65,75, 86

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

a.

The facility shall be placed in at least HOT STANDBY within one hour.

b.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Manager - Nuclear Power Department and the OSSRC shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c.

A Safety Limit Violation Report shall be prepared. The report shall i

be reviewed by the POSRC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

k d.

The Safety Limit Violation Report shall be submitted to the Commission, the OSSRC and the Manager - Nuclear Power Department within 14 days of the violation.

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

1 a.

The applicable procedures recomended in Appendix "A" of Regulatory Guide 1.33 Revision 2 February 1978.

b.

Refueling operations.

c.

Surveillance and test activities of safety related equipment.

y d.

Security Plan implementation.

e.

Emergency Plan implementation.

1 l

f.

Fire Protection Program implementation.

g.

The amount of overtime worked by plant staff members performing safety related functions must be limited in accordance with the l

NRC Policy Statement on working Hours (Generic Letter No. 82-12).

h.

PROCESS CONTROL PROGRAM implementation.

i. OFFSITE DOSE CALCULATION MANUAL implementation.

i 6.8.2 Each procedure and administrative policy of 6.8.1 above and changes thereto shall be reviewed by the POSRC and approved by the Plant Superinten-i dent prior to implementation and reviewed periodically as set forth in i

administrative procedures.

CALVERT CLIFFS - UNIT 2 6-13 Amendment No.JJ,26,56,65,86 l

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C ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 6.8.1 above may be made pro-vided:

a.

The intent of the originial procedure is not altered.:

b.

The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.

c.

The change is documented, reviewed by the POSRC and approved by the Plant Superintendent within 14 days of implementation.

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS

6. 9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.

STARTUP REPORT

6. 9.1.1 A sumary report of plant startup and power escalation testin shall be submitted following (1) receipt of an operating license (2) g amendment to the license involving a planned increase in power level.

(3) installation of fuel that has a different design or has been manu-factured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thennal, or hydraulic perfor-mance of the plant.

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

l AmendmentNo.//'ff.U,75 CALVERT CLIFFS - UNIT 2 6-14

ADMINISTRATIVE CONTROLS 6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation),.supplanentary reports shall be submitted at least every three months until all three events have been completed.

M ANNUAL rep 0RTS 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.

6.9.1.5 Reports required on an annual basis shall include:

a.

A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their a according to work and job functions,gociated man rem exposure e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter TLD, or film badge measure-ments. Sn.all exposures totalling less than 20% of the individual total dose need not be accounted for.

In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

b.

The complete results of steam generator tube inservice inspections perfomed during the report period (reference Specification 4.4.5.5.b).

c.

Documentation of all failures and challenges to the pressurizer PORVs or safety valves, y A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

2f This tabulation supplements the requirements of l20.407 of 10 CFR Part 20.

l CALVERT CLIFFS - UNIT 2 6-15 Amendment No. U, 5 0 l

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ADMINISTR ATIVE CONTROLS MONTHLY OPERATING REPORT 6.9.1.6.

Routine reports of operating statistics and shutdown experience shall be i

submitted on a monthly basis to the Director, Office of Inspection and Enforcement, U.S.

Nuclear Regulatory Commission, Washington, D.C.

20555, ATTN: Document Control Desk, with a copy to the Regional Administrator and to the NRC Resident. Inspector, no later than the 15th of each month following the calendar month covered by the report.

4 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

6.9.1.7 Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

1 The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, with operational sontrols as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Specification 3.12.2.

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The Amual Radiological Environmental Operating Reports shall include the results of

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analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the Table and Figures in the ODCM, as well as summarized and tabulated results of these analyses 4

and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and l

explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the radiological environmental monitoring program; at least two legible maps ** covering all sampling locations keyed to a table giving distances and directions from the central point between the two containment buildingsl the results of licensee participation in the Interlaboratory j

Comparison Program, required by Specification 3.12.3; discussion of all deviations from the sampling schedule of Table 3.12-1 and discussion of all analyses in which the LLD 1

required by Table 4.12-1 was not achievable.

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A single submittal may be made.

- One map shall cover stations near the site boundary; a second shall include j

the more distant stations.

l CALVERT CLIFFS UNIT 2 6-16 Amendment No. M,50,n, 86 i

q ADMINISTRATIVE CONTROLS The Annual Radiological Environmental Operating Report will include the identification of the cause of unavailability of samples (if any), and will describe the locations used for the replacement samples. The report will also include any permanent changes in the sample locations which could appear in the monitoring program. It willinclude a revised figure (s) and table for the ODCM reflecting the new location (s).

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

6.9.1.8 Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days af ter January I and July 1 of each year.**

The Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the plant as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The Radioactive Effluent Release Report to be submitted within 60 days af ter January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of,hQnt frequency distributions of wind speed, wind direction, and atmospheric stability.

This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents-released from the unit or station during the previous calendar year. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in

.y the OFFSITE DOSE CALCULATION MANUAL (ODCM).

A single submittal may be made for Calvert Cliffs, since the radwaste systems are common to both units.

l In lieu of submission with the Semi-Annual Reports, Sr89, Sr90 analyses results may l

be submitted in a supplementary report within 120 days after January 1 and July 1 of each year.

l In lieu of submission with the first half year Radioactive Effluent Release Report, this summary of required meteorological data may be retained on site in a file that shall be provided to the NRC upon request.

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l CALVERT CLIFFS UNIT 2 6-17 Amendment No. H,5, 86 i

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ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued)

The Radioactive Effluent Release Report to be submitted 60 days after January I of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev.1, October 1977, and NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants".

The Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period:

a.

Container volume, b.

Total curie quantity (specify whether determined by measurement or estimate),

c.

Principal radionuclides (specify whether determined by measurement or estimate),

d.

Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),

e.

Solidification agent or absorbent (e.g., cement).

The Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in" gaseous and liquid ef fluents made during the reporting period.

The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations identified by the annual land use census pursuant to Specification 3.12.2.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the NRC Regional Office within the time period specified for each report.

These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

CALVERT CLIFFS UNIT 2 6-18 Amendment No. H,75, 86

ADMINISTRATIVE CONTROLS a.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

b.

Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

c.

Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.

d.

Seismic event analysis, Specification 4.3.3.3.2.

e.

Core Barrel Movement, Specification 3.4.11.

f.

Fire Detection Instrumentation, Specification 3.3.3.7.

g.

Fire Suppression Systems, Specifications 3.7.11.1, 3.7.11.2, 3.7.11.3, 3.7.11.4 and 3.7.11.5.

h.

Penetration Fire Barriers, Specification 3.7.12.

i.

Steam Generator Tube Inspection Results, Specification 4.4.5.5.

J.

Specific Activity of Primary Coolant, Specification 3.4.8.

k.

Containment Structural Integrity, Specification 4.6.1.6.

1.

Radioactive Effluents -- Calculated Dose and Total Dose, Specifications 3.11.1.2, 3.11.2.2, 3.11.2.3, and 3.11.4.

m.

Radioactive Effluents -- Liquid Radwaste, Gaseous Radwaste and Ventilation Exhaust Treatment Systems Discharges, Specifications 3.11.1.2 and 3.11.2.4.

n.

Radiological Environmental Monitoring Program, Specification 3.12.1.

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l CALVERT CLIFFS UNIT 2 6-18a Amendment No. H./75, 86

ADMINISTRATIVE CONTROLS s

6.16 PROCESS CONTROL PROGRAM (PCP) 6.16.1 The PCP shall be approved by the Commission prior to implementation.

6.16.2 Licensee initiated changes to the PCP:

1.

Shall be submitted to the Commission in the Semiannual Radioactive Effluent Relean Report for the period in which the change (s) was made.

This submittal shall contaim a.-

An evaluation supporting the premise that the change did not reduce the overall conformance of the solidified waste product to existing i

criteria for solid wastes; and b.

A reference to the date and the POSRC meeting number in which the change (s) were reviewed and found acceptable to the POSRC.

2.

Shall become effective upon review and approval by the responsible Nuclear Power Department unit and approval of Plant Superintendent.

6.17 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.11.1 The ODCM shall be approved by the Commission prior to implementation.

6.17.2 Lic'ensee initiated changes to the ODCM:

1.

S$all be submitted to the Commission in the Semlannual Radioactive Effluent Release Report for the period in which the change (s) was made effective. This submittal shall contain:

,a.

Sufficient information to support the rationale for the change.

Information submitted should consist of a package of those pages of the or-ODCM to be changed with each page numbered and provided with a change number and/or change date together with appropriate analyses or evaluations justifying the change (s);

b.

A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and Documentation of' tt.e fact that the change has been reviewed and l

c.

found acceptable by the POSRC.

~ 2.

Shall become effective upon review by the POSRC and approval of the Plant j

Superintendent.

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j CALVERT Cl.!FFS UNIT 2 6-23 Amendment No. 86 I

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ADMINISTRATIVE CONTROLS 6.18 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6.18.1 Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid) shall be reported to the Commission in the Semlannual Radioactive Effluent Release Report for the period in which the modification to the waste system is completed. The discussion of each change shall contain:

a.

A description of the equipment, components and processes involved.

b.

Documentation of the fact that the change including the safety analysis was reviewed and found acceptable by the POSRC.

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l CALVERT CLIFFS UNIT 2 6-24 Amendment No.86

i CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NOS.1 AND 2 APPENDIX B PARTI ENVIRONMENTAL TECHNICAL SPECIFICATIONS FACILITY OPERATING LICENSE NOS. DPR-53 AND DPR-69

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l DELETED See Appendix A Technical Specifications' l

Sections 3/4.11 and 3/4.12 1

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t e

ISSUED BY THE U. S. NUCLEAR REGULATORY COMMISSION CALVERT CLIFFS UNIT 1 Amendw nt No. 23,79 700.86 CALVERT CLIFFS UNIT 2 Amendment No. 7. 53. S2. 86

ML20129E769

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