ML20135F337

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Proposed Tech Specs Relocating Requirements for Main Vent wide-range Iodine & Particulate Sampler & Reactor Coolant Sampling Sys to Section 6.16,per 831101 Generic Ltr 83-37
ML20135F337
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 09/09/1985
From:
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20135F276 List:
References
GL-83-37, NUDOCS 8509170223
Download: ML20135F337 (14)


Text

.

s TABLE 3.3-6 9

{

RADIATION MONITORING INSTRUMENTATION m

MINIMUM P

CHANNEyS APFi.ICABLE ALARM / TRIP MEASUREMENT k

INSTRUMENT OPERABL E_

MODES

_SETPOINT RANGE ACTION u,

l. AREA MONITORS Ea
a. Containment i.

Purge & Iahaust 4

Isolation 3

6 1 220 mr/hr 10-

- 10 mr/hr 16

b. Containment A"*a liigh Range 2
1. 2. 3. & 4 1 10 R/hr 1 - 10 R/hr 30 R
2. PROCESS MONITOR'.,

s.

y

a. Containment 5

1.

Gaseous Ailivity a) RCS teekd9e 6

Detecelon 1

1, 2, 3. & 4 Not Applicable 1 - 10 cpm 14 ii. Particulair Activity E

s) RCS Ieak39e k

Detection 1

1, 2, 3, & 4 Not Applicable 1 - 10 cp, j4 6

2 Noble (ro g

b. M:ble O: Efiluent Monitors 2

P

i. Main Vent wide 10'7 to 10+5 pCf/cc 30 ]

1 1, 2, 3. & 4

.J.ange,

(y m

y

-O,2 c- 0 5.'

^ ^

L-

.. 3,1 i

%. /.' 2e.;

b.',,,

O^

g O " R L ; ~^ 7c.... J ^

,L,;, ' 'l Mu

..~.c

L r,'.,_. c.'

20 r

  • Alarm setpoint to t e specified in a controlled sfocument (e.g., setpoint control nanual) hD 850909 KO P

7

I'jb a

_'%h TABLE 4.3-3 D

G RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS O

CHANNEL MODES IN WHICH P

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE y

INSTRUMENT CHECK CALIBRATION TEST REQUIRED 3

1.

AREA MONITORS C5 a.

Containment s

i.

Purge & Exhaust Isolation S

R M

6 b.

Containment Area High Range S

R M

1, 2, 3, & 4 w1 2.

PROCESS MONITORS w

4 a.

Containment co

i. Gaseous Activity a) RCS Leakage Detection S

R M

1, 2, 3, a 4 ii. Particulate Activity

?T

' a) RCS Leakage Detection S

R H

1, 2, 3, & 4 5

Nolelt 6ms b.

" 51: 5 Effluent Monitor m

A 1.

Main Vent Wide Range 5

R M

1. 2, 3, & 4 3 g

^ & Na,- : G G t) 1^^: e $P-mcR

^':, ?gc

.,..a c

,! a ;!;;._;,;,,; e, 2, 3, ; 'j e c =. = = s2. =

u, w.: ua-.=
, a v:.

I TLANT SYSTEMS i

3 7.13 POST-ACCIDENT SAMPLING LIMI G CONDITION FOR OPERATION

/

3.7.13 T post-accident sampling system shall be OPERABLE and capa e of processing amples from all of the below listed points:

a.

RCS s pie via hot leg b.

RCS samp via low pressure safety injection, and c.

Containment ump sample via low pressure safety in etion.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a.

With the operability o the post-accide t sampling system less than the LIMITING CONDITION F OPERATION ecified above, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> initiate the preplan ed altern te method of processing specified sample (s), and ei er:

Restore the system dTPduBha within 7 days, or 1.

Prepare and submit)a Spe ial Report to the Co C.

2.

to Specification 6.9.2 thin 30 days following the event, 5

g out$ $ng the action ken, the cause of the inoperability, and

~-

the plans and schedu for restort g the system to OPERABLE

status, b.

The provisions of Sp cifications 3.0.3 an

.0.4 are not applicable.

SURVEILLANCE REQUIREMEN 1

4.7.13 The post-ace dent sampling system shall be demonst ted OPERABLE at least once per Tix 6) months by comparing the results of a CS sample analyzed by labor tory techniques with the results analyzed b the below listed analyzin equipment:

1.

Boro Analyzer 2.

H regen and Oxygen Analyzer 3.

pH Analyzer Liquid Radioisotopic Analyzer.

t LVERT CLIFFi - UNIT 1 3/4 7-78 Amendment No. 4

y 4

l l'

INSTRUMENTATION BASES by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.

3/4.3.3.2 INCORE DETECTORS The OPERABILITY of the incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.

3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that suffi-cient capability is available to promptly determine the inagnitude of a seismic event and evaluate the response of those features important to safety. This capability is required to permit comparison of the measured response to that used in the design basis for the facility and is consistent with the recomendations of Regulatory Guide 1.12. " Instrumentation for Earthquakes", April 1974.

3/4.3.3.4.

METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23 "Onsite Meteorological Programs",

February 1972.

3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room.

This capability is required in the event control room habitability is lost and is consistent with General Design Criteila 19 of 10 CFR 50.

CALVERT CLIFFS - UNIT 1 0 3/4 3-2 Q Q.F g

m

/

INSTRUMENTATION

/

BASES 3/4.3.3.6 POST-ACCIDENT INSTRUMENTATION The OPERABILITY of the post-accident instrumentation ensure: 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, "THI-2 Lessons Learned Task Force Status Report and Short-Term Recorrrnendations."

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 cap bility until the inoperable instrumentation is restored to operability.

3/4.3.3.8 MACTIVE GASEOUSJiMti,ENT MONITORINWTRUMENTATION 10 DINE Aptt PARTI' ;ULATE SAMPL)K t

(

p he OPERAB.ITY of e Iodine and Par <

culate Sar pler en s that Io e and Par culate amples ca be o ined for and lysi ring and f

owing an ciden. The surve e requirements re a high d ree av ilabilit I

he s m n alled et th r quir nt c NURE 7

l' ltem I F.1.

e am er//o atipn no a u.

in' t y anal 5 s.

s._

CALVERT CLIFFS - UNIT 1 B 3/4 3-3 AmendmentNo.26,52,4A; y

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4 PLANT SYSTEMS BASES 3/4.7.12 PENETRATION FIRE BARRIERS The functional integrity of the penetration fire barriers ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment. The penetration fire barriers are a passive element in the facility fire protection program and are subject to periodic inspections.

During periods of time when the barriers are not functional, a continuous fire watch is required to be maintained in the vicinity of the affected barrier until the barrier is restored to functional status.

W.13 POST-ACCIDENT SAMPLING SYSTEM The OP TV of the Post-Accident Sampling ensures the

~

capability to obta analyze reactor cool nd containment atmos-phere samples during and in an a nt.

The surveillance require-mentsensureahighdeg%{

ity.

The Post-Acciden ling System was ins to meet the require-ments of NUREG-tem 11.8.3.

The system's opera as not assumed in any ac t analysis.

)

CALVERT CLIFFS - UNIT I B 3/4 7 7 Amendment No. 26 /(

1 l

l

. ADMINISTRATIVE CONTROLS 6.15 IODINE MONITORING The licensee shall imolement a progra/which will ensure the capability' l

to accurately detennine the airborne iodine concentration in vital areas under accident conditions.

This program shall include the following:

1.

Training of personnel, 2.

Procedures for m nitoring, and 3.

Drovisions for maintenance of sampling and anal / sis equipment.

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B BLE 3.3-6 g

RADIATION MONITORING INSTRUMENTATION Gg MINIMJM CHANNELS APPLICABLE ALARM / TRIP MEASURE.T NT p

INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION t

z?

1.

AREA MONITORS

  • h a.

Containment z

I q

1.

Purge & Exhaust Isolation 3

6

< 220 mr/hr 10~

- 10 mr/hr 16 4

u b.

Containment Area High 3

Range 2

1, 2, 3 & 4

< 10 R/hr 1 - 10 R/hr 30 0

2.

PROCESS MONITORS a.

Containment d

3*

1.

Gaseous Activity m

A, a) RCS Leakage Detection 1

1, 2, 3 & 4 Not Applicable 10 - 10 c,

j4 I

6

'11. Particulate Activity I

a) RCS Leakage g

g Detection 1

1, 2, 3 & 4 flot Applicable 10 - 10 cpm 14 1

6 i

y b.

"-- Effluent 3

Monitors a

g 1.

Main Vent Wide E

Rang:C:

GA5 10'7 to 105 1

1, 2, 3 & 4 pCi/cc 30 di 5

h q T _- ~ e 5:.

.:=
,;, s ; ;

% ? =.= :1 c:

L _ = L - m_ s t, 2, 5.:,

'!: 7 't: ' ^ '

d ' " ^ ' A u

y ts

  • Alarm setpoint to be specified*in a controlled document (e.g., setpoint control manual).

e

- - - - - - - - - ~ -

3 t

n TABLE 4.3-3 N

f, RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS n

C CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE

]

INSTRUMENT CHECK CALIBRATION TEST REQUIRED J

s 1.

AREA MONITORS Q

a.

Containment N

i.

Purge & Exhaust Isolation S

R M

6 i

b.

Containment Area High Range 5

R H

1, 2, 3, a 4 w1 2.

PROCESS M)MITORS wL a.

Containment oo

i. Gaseous Activity a) RCS Leakage Detection 5

R H

1, 2, 3, & 4 ii'. Particulate Activity F

a) RCS Leakage Detection 5

R H

1. 2, 3, & 4

}

NOIL Gas 3

a b.

til: 0 ; Effluent Monitors 2

i. Main Vent Wide Range S

R H

1, 2, 3, & 4

&SUGCif.SAS-e T:: 1 S?

z=

p., Q s.:

,,2, 2, 2 ':

?, D w v > L _=_ 5 ? - e t A

H: :'i:. - : -

. : ? ;;-

..a

', ', 3, !4 1

-D

ANT SYSTEMS

'3/

.13 POST-ACCIDENT SAMPLING LIMIT CONDITION FOR OPERATION 1

/

3.7.13 Th post-accident sampling system shall be OPERABLE and ca ble of processing mples from all of the below listed points:

a.

RCS mple via hot leg b.

RCS sam e via low pressure safety injection, and c.

Containmen sump sample via low pressure safet injection.

APPLICABILITY: MODES 1,

, and 3.

ACTION:

a.

With the operability o the post-a ident sag ding system less than the LIMITING CONDI ON FOR Of yn tpecified above, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> initiate e prFFTannec alPl!PHate method of processing specified s w l "s) 1 fed eibher.*

1.

Restore the s m 30, O BLE status within 7 days, or 2.

Prepare and submit a pecial eport to the Comission pursuant to Specification 6

.2 within 0 days following the event, outlining the act n taken, the ause of the inoperability, and the plans a schedule for re toring the system to OPERABLE statu.

b.

The provi,sions Specifications 3.0.3 an 3.0.4 are not applicable.

SURVEILLANCE REOUIR ENTS x

4.7.13 The ' post accident sampling system shall be demonstrat d OPERABLE at least once per ix (6) months by comparing the results of a RC sample!

analyzed by 1 oratory techniques with the results analyzed by t e below-listed anal ing equipment:

1.

oron Analyzer Hydrogen and Oxygen Analyzer 3.

p!! Analyzer 4.

Liquid Radioisotopic Analyzer.

~

CAL 7ERT CLIFFS - UNIT 2 3/4 7-70

'AmendNntNo.g L---

PLANT SYSTEMS BASES 3/4.7.12 PENETRATION FIRE BARRIERS The functional integrity of the penetration fire barriers ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility.

This design feature minimizes the possiMlity of a single fire rapidly involving several areas of the facility prior to detection and extinguishment. The penetration fire barriers are a passive element in the facility fire protection program 4

and are subject to periodic inspections.

During periods of time when the barriers are not functional, a continuous fire watch is required to be maintained in the vicinity of the affected barrier until the barrier is restored to functional status, i

M 13 POST-ACCIDENT SAMPLING SYSTEM i

The OPE

.of the Post-Accident Sampling S ensures the capability to obtain.

nalyze reactor coolan containment atmos-phere samples during and e

n an acci The Surveillance Required ments ensure a high degrg { {

The Post-Accident Sa g System was ins to meet the require-ments of NUREG-0737 I.B.3.

The sy: tem's operat s no,t assumed in any acciden ysis.

.O CALVERT CLIFFS - UNIT 2 8 3/4 7 7 AmendmentNo.JJ,4 i

1 J

INSTRUMENTATION

/

BASES by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.

3/4.3.3.2 INCORE DETECTORS The OPERABILITY of the incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.

3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that suffi-cient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to sa fety. This capability is required to pemit comparison of the measured response to that used in the design basis for the facility and is consistent with the recomendations of Regulatory Guide 1.12. " Instrumentation for Earthquakes", April 1974.

3/4.3.3.4.

METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.

This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recomendations of Regulatory Guide 1.23 'Onsite Meteorological Programs".

February 1972.

3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room.

This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.

mendNd

pg CALVERT CLIFFS - UNIT 2 B 3/4 3-2

4 j

_ INSTRUMENTATION

/'

BASES l'

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 reconenendations 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-Tem Recomendations."

3/4.3.3.7 FIRE DETECTION INSTRUMENTATION OPERAT,ILITY 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 inoperabic, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to operability.

3/4.3.1JP"Itm0!OACTIVE GAS 5WPIFFLUENT MONIMNSTRUME N

[

IODME AND PAATICULATEJEFLER

/

Th ERABI of the dine Particul e Samp" r ensu th Iodi nd P,ar ulate Sa es ca e obtained or an.rsis du ng fall ing ccident.

e sur 111ance requi n

ensure i

degre availability.

l

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I CALVERT CLIFFS - UNIT 2 B 3/4 3-3 Amendment No. JJ 26 #I, 1

l l

r ADMINISTRATIVE CONTROLS 6.15 IODINE MONITORING The licensee shall implement a program *which will ensure the capability l

to accurately detemine the airborne fodine concentration in vital areas under accident conditions. This program shall include the fc110 wing:

N 1.

Training of personnel, 2.

Procedures for monitoring, and 3.

Provisions for maintenance of sampling and analysis equipment.

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cALVERT CLIFFS-UNIT 2 6-22 Amendment No.

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