Text

Amends 83 & 66 to Licenses DPR-53 & DPR-69,respectively, Revising Tech Spec Surveillance Requirements for Equipment Hatch & safety-related Air Filter Sys
	ML20074A990
Person / Time
Site:	Calvert Cliffs
Issue date:	05/05/1983
From:	Clark R; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20074A991	List: ML20074A990; ML20074A993; ML20074A994;
References
	NUDOCS 8305170259
	Download: ML20074A990 (64)
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a arcy g'o UNITED STATES e

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NUCLEAR REGULATORY COMMISSION g. ',.

.:. C VVASHINGTON, D. C. 20555 t Y, sj/

y BALTIM0RE GAS AND ELECTRIC COMPANf DOCKET N0. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 83 License No. DPR-53 1.

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

A.

The application for amendment by Baltimore Gas & Electric Company (the licensee) dated February 24, 1983 as supplemented by letter dated March 22, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission'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 Commission; C.

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

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

The issuance of this amendment is in accordance with 10 CFR

)

Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

l B305170259 830505 PDR ADOCK 05000317 P

PDR i

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2-2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license l

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. 83, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION 7>

b

.S. i.I'.

/rt?l:%d y Robert A. Clark, Chief I

Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: May 5, 1983 i

L_

ATTACHMENT TO LICENSE AMENDMENT NO. 83

-FACILITY OPERATING LICENSE NO. DPR-53 DOCKET N0. 50-317 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated.

The revised pages are identified by Amendment. number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.-

Pages 2-9 8 2-7 3/4 3-2 3/4 3-6 3/4 3-7 3/4 6-1 3/4 6-14 3/4 6-15 3/4 6-26 3/4 6-29 3/4 6-30 3/4 7-18 3/4 7-20 3/4 7-22 3/4 7-23 3/4 9-13 3/4 9-14 t

f

TABM _2_.2-l_ -(Cont'd) g k

R EACTOR...P.RO T.E.C.T I.V E.l.ilS.T.R.u.tl.E.ilTAT.l.a.'l T R I P S E.T Po. l fl f..L.i t t l TS- - -

-4 n

.C FUNCTIONAL UtilT

.T._RI P._S.E.T rol flT ALLOWABLE VALUES

_n n.

[

4.

Pressurizer Pressure - liigh 1 2400 psia 1 2400 psia E

5.

Containment Pressure - liigh 1 4 psig 1 4 psig Q

6.

Steam Generator Pressure - Low (2) 1 635 psia 1635 psia s

7.

Steam Generator Water Level - Low

10 inches below top

> 10 inches below top of feed ring.

of feed ring.

8.

Axial flux offset (3)

Trip setpoint adjusted to Trip setpoint adjusted to not exceed the limit lines not exceed the limit' lines of. Figure 2.2-1.

of, Figure 2.2-1.

7*

9.

Thermal Margin / Low Pressure (1) a.

Four Reactor Coolant Pumps Trip setpoint adjusted to

'Trin setpoint adjusted to Operating not exceed the limit lines be 'not less than the larger of Figures 2.2-2 and 2.2-3.

of (1) the value calculated from Figures ~2.2-2 and 2.2-3 and (2) 1875 psig.

b.

Steam Generator Pressure

~< 135 psid

~< 135 psid Difference - High (1)

{

10.

Loss of Load ti. f..

it. A.

l h

'"g Rate of Change of Power - liigh (4) 1 2.6 decades per minute 1.2.6 decades per minute 11.

E TABLE fl0TATION U

-4 (1) Tripmaybebypassedbe}ow10 % of RATED TilERMAL POWER; bypass shall be automatically removed when TilERMAL POUER is >_ 10 % of RATED tiler!1AL POWER.

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TABLE 2.2-1 (Cont'd) 9 TABLE NOTATIONS (Cont'd)

P M

(2) Trip may be manually bypassed below 710 psia; bypass shall bc automatically removed at or above 710. psia.

3 (3) Trip may. be bypassed below 15% of RATED TilERf1AL POWER; bypass shall be automatically removed when.

i c

TilERi1AL P0tJER is > 15% of RATED tiler!1AL POWER.

=

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(4) Trip may be bypassed below 10 % and' above 12%.'of RATED TilERMAL POWER.

t 4

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LIM TING SAFETY SYSTEM SETTINGS BASES The Thermal Margin / Low Pressure trip setpoints include allowances for equipment response time, measurement uncertainties, processing error and a further allowance of 40 psia to compensate for the time delay associated with providing effective termination of the occurrence that exhibits the most rapid decrease in margin to the safety limit.

Asymmetric Steam Generator Transient Protection Trip Function (ASGTPTF)

The ASGTPTF utilizes steam generator pressure inputs to the TM/LP calculator, which causes a reactor trip when the difference in pressure between the two steam generators exceeds the trip setpoint. The ASGTPTF is designed to provide a reactor trip for those Anticipated Operational Occurrences associated with secondary system malfunctions which result in asymmetric primary loop coolant tenperatures. The most limiting event is the loss of load to one steam generator caused by a single Main Steam -Isolation Valve closure.

The equipment trip setpoint and allowable values are calculated to account -

for instrument. uncertainties, and will ensure a trip at or before reaching the analysis setpoint.

Loss of Load '

j A Loss of Load trip causes a direct reactor trip when operating above 15% of RATED THERfiAL POWER.

This trip provides turbine '*otection, reduces the severity of the ensuing transient and helps avoid the lifting of the main steam line safety valves during the ensuing transient, thus extending the service life of these valves. No credit was taken in the accident analyses for operation of this trip.

Its functional capability is required to enhance overall plant equipment service life and reliability.

i Rate of Change of Power-High The Rate of Change of Power-High trip is provided to protect the core during startup operations and its use serves as a backup to the administra-tively enforced startup rate limit.

Its trip setpoint does not correspond to a Safety Limit and no credit was taken in the accident analyses for operation of this trip.

Its functional capability at the specified trip setting is required to enhance the overall reliability of the Reactor Protection System.

CALVERT CLIFFS - UNIT 1 B 2-7 Amendment No. 27, 32, 39, AS, 71, 8 3.8 r

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3/4.3. -INSTRUMENTATION 1

3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION LIMITING CONDITION FOR OPERATION t

3.3.1.1 As a' minimum, the reactor protective _ instrumentation channels and bypasses of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as :

shown in Table 3.3-2.

j -

APPLICABILITY: As shown in Table 3.3-1.

ACTION:

As shown in Table 3.3-1.

SURVEILLANCE REQUIREMENTS 1

4.3.1.1.1 Each re' actor protective instrumentation channel shall be demonstrated OPERABLE by the_ performance of the CHANNEL CHECK, CHANNEL-CALIBRATION and CHANNEL FUNCTIONAL TEST operations during'the MODES and at the frequencies shown in Table 4.3-1.

4.3.1.1.2.

The logic'for the bypasses shall be demonstrated 0PERABLE prior to each reactor startup unless performed-during the preceding 92 days. The total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel ~

affected by bypass operation.

4.3.1.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME-of each reactor trip function shall be demonstrated to be within its limit at least once per 18 months..Each test shall. include at least one channel'per function such that all channels ~are tested at least once every'N times 18 months where N is' the total number of redundant channels in a specific reactor trip function as shown 'in the " Total No. of Channels" column of Table 3.3-1.

4 j -

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4 CALVERT CLIFFS - UNIT 1 3/ + 3-1 e

TABLE 3.3-1 REACTOR PR01ECTIVE INSTRUMENTATION 9

MINIMUM TOTAL NO.

CilANNELS CilANNELS APPLICABLE-P FUNCTIONAL UNIT OF CilANNELS TO TRIP OPERABLE MODES ACTION 1.

Manual Reactor Trip 2

1 2

1, 2 and

1 h.-.

2.

Power level - High 4

2 3(f) i, 2 2#

[

3.

Reactor Coolant Flow - Low 4/SG 2(a)/SG 3/SG 1, 2 (e) 2#

4.

Pressurizer Pressure - liigh 4

2 3

1, 2 2#

5.

Containment Pressure - liigh 4

2 3

1, 2 2#

6.

Steam Generator Pressure - Low 4/SG 2(b)/SG 3/SG 1,* 2 2#

7.

Steam Generator Water

{

Level - Low 4/SG 2/SG 3/SG 1,-2 2#

[

8.

Axial. Flux Offset 4

2(c) 3 1

2#

9.a.

Ihermal ;1argin/ Low Pressure 4 2(a) 3 1, 2 (e)'

2#

b.

Steam Generator Pressure Difference - liigh 4

2(a) 3 1, 2 (e) 2#

8 10.

Loss of Load 4

2(c) 3 1

2#

l h

5 E

N e

ca b

TABLE 3.3-1 (Continued)

ACTION STATEMENTS b.

Within one hour, all functional units receiving an input from the inoperable channel are also placed in the same condition (either bypassed or tripped, as applicable) as that required by a. above for the inoperable channel.

c.

The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months while performing tests'and maintenance on that channel provided the other inoperable channel is placed in the tripped condition.

ACTION 3 With the number of channels OPERABLE'one less than required.

by the Minimum Channels OPERABLE requirement, verify compli-ance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

ACTION 4 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in HOT.

STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to I hour for surveillance testing per Specification 4.3.1.1.

CALVERT CLIFFS - UNIT 1 3/4 3-5

- - - - - - - - - - - ~

.n TABLE 3.3-2 Py REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES w

b FUNCTIONAL UNIT RESPONSE TIME

?

f 1.

Manual Reactor Trip Not Applicable 2.

Power Level - High

< 0.40 seconds *# and < 12.0 secor}ds ##

3 Reactor Coolant Flow - Low

< 0.50 seconds 4.

Pressurizer Pressure - High

< 0.90 seconds 5.

Containment' Pressure - High 1 0.90 seconds 6.

Steam Generator Pressure - Low 1 0.90 seconds 7.

Steam Generator Water Level - Low 1 0.90 seconds 8.

Axial Flux Offset 1 0.40 seconds *# and i 12.0 seconds ##

i 9.a.

Thermal targin/ Low Pressure

< 0.90 seconds *# and < 12.0 seconds ##

b.

Steam Generator Pressure Difference - liigh 1 0.90 seconds 10.

Loss of Load Not.Tpplicable N

m E.

11. Wide Range Logarithmic Neutron Flux Monitor Not Applicable CD A

Neutron detectors are exempt from response time testing.

Response time of the neutron flux signal portion 2

?

of the channel shall be measured from detector output or input of first electronic component in channel.

Response time does not include contribution of RTDs.

1. RTD' response time only. This value is equivalent to the time interval required for the RTDs output to achieve 63.2% of its total change when subjected to a step change in RTD temperature.

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TABLE 4.3-1

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9 E

REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS xH N

CHANNEL MODES IN WilICll E

CilANNEL CHANNEL FUNCTIONAL SURVEILLANCE.

U FUNCTIONAL UNIT CilECK CALIBRATION TEST REQUIRED h

1.

Manual Reactor Trip N.A.

N.A.

S/U(1)

N. A.,

2 2.

Power Level - liigh a.

Nuclear Power S

D(2),ft(3),Q(5) M

.1, 2

b.

AT Power S

D(4),R M

'l.

3.

Reactor Coolant Flow - Low S

R M

l ', 2 4.

Pressurizer Pressure - liigh S

R M'

1, 2 5.

Containment Pressure - liigh S

R M

1, 2 6.

Steam Generator Pressure - Low S

R M

1, 2 7.

Steam Generator Water Level - Low S

R M

1, 2 8.

Axial Flux Offset S

R M.

1 9.a.

Thermal flargin/ Low Pressure S

R f1 1, 2, I

b.

Steam Generator Pressure Difference -

ji Iligh S

R

!1 1, 2 8

10.

Loss of Load N.A.

N.A.

S/U(1)

N.A.

_l Ei

TABLE 4.3-1 (Continued) n@

si REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS 5

b!

CHANNEL MODES IN WHICH 41 CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED i

i Ei

11. Wide Range Logarithmic Neutron S

R(5)

S/U(1) 1, 2, 3,,4,

1 Flux Monitor 5 and *

12. Reactor Protection System Logic Matrices N.A.

N.A.

M and S/U(1) 1, 2

13. Reactor Protection System Logic Matrix Relays N.A.

N.A.

M and S/U (1) 1, 2

'{

14. Reactor Trip Breakers N.A.

N.A.

M 1, 2 and

ca 03 O

s 5

D t

a 1

1 3/4.6 CONTAlf4 MENT SYSTEMS 3/4. 6.1 PRIfiARY CONTAlflMEf;T CONTAI!1 MENT INTEGRITY LIMITING C0!1DITI0ft FOR OEPRATION 3.6.1.1 Primary CONTAINf1ENT INTEGRITY shall be maintained.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

Without primary CONTAINMENT INTEGRITY, restore C0f;TAINMENT INTEGRIT'Y within i.

one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD I

SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLA"CE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT IllTEGRITY shall be demonstrated:

a.

At least once per 31 days by verifying that all penetrations

not capable of being closed by OPERABLE containment -automatic isolation valves and required to be closed during accident conditions are closed by valves, blind. flanges,in deactivated automatic valves secured in their positions, except as provided in Table 3.6-1 of Specification 3.6.4.1.

I b.

By verifying that each containment air lock is OPERABLE per Specification 3.6.1.3.

c.

By verifying that the equipment hatch is closed and sealed, prior to entering ltode 4 following a shutdown where the equipment hatch was opened,'by conducting a Type B test pdr Appendix J to 10 CFR Part 50.

Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed, or otherwise secured in the closed position.

These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more.

often than once per 92 days.

' CALVERT CLIFFS - UNIT 1 3/4 6-1 Amendment No. 9 ?

CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE 1

LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to':

a.

An overall integrated leakage rate of:

L 346,000 SCCM), 0.20 percent by weight of the containment l

1,pe(r 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at P, 50 psig, or 1.

air a

2.

1Lt (61,600 SCCM), 0.058 percent by weight of the c.ontainment l

air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at a reduced pressure of P. 25 psig.

t b.

A combined leakage rate of 1 0.60 L (207,600 SCCM), for all penetra -

l l

tions and valves subject to Type B $nd C tests when pressurized to P.

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

ACTION:

With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L SCCM) or 0.75 L (46,200 SCCM), as applicable.

l or (b) with the 8ea(259,500sured combined leakage bate for all penetrations and val subject to Types B and C tests exceeding 0.60 L, restore the leakage rate (s) to within the limit (s)' prior to increasing the keactor Coolant System temperature above 200 F.

SURVEILLANCE REQUIREMENTS-

4. 6.1. 2.

The containment leakage rates shall. be demonstrated at the following test schedule and shall be determined in conformance with the criteria.specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4 -

1972:

Three Type A tests (Overall Integrated Containment Leakage Rate) shall a.

be conducted at 40 + 10 month intervals during shutdown at either P a

(50 psig) or at P T25 psig) during each 10-year service period.

The third test of each set shall be conducted during the shutdown for the 10-year plant inservice inspection.

CALVERT CLIFFS - UNIT 1 3/4 6-2 Amendment No. 75 e

CONTAINMENT SYSTEMS 3/4.6.3 IODINE REMOVAL SYSTEM LIMITING CONDITIO!i FOR OPERATION' 3.6.3.1 - Three independent containment iodine filter trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

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

SURVEILLANCE REQUIREMENTS 4.6.3.1 Each iodine filter train shall be demonstrated OPERABLE:

At least once per 31 c!ays on a STAGGERED TEST BASIS by initiat-a.

ing, from the control room, flow through.the HEPA filter and.

charcoal adsorber train and verifying.that the train operates for at least 15 minutes.

b.

At least once per 18 months or (1) after any structural maintenance on the HEPA filter-or char' coal adsorber housings, or (2) following painting, fire or chemical. release in any ventilation zone communicating with the system by:

1.

Verifying that the charcoal adsorbers remove > 99%

of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the filter train at a flow rate of 20,000 cfm + 10%.

2.

Verifying that the HEPA filter banks remove > 99% of the DOP when they are tested in-place in accordan'ce with ANSI N510-1975 while operating the filter train at a flow rate of 20,000 cfm + 10%.

i CALVERT CLIFFS - UNIT 1 3/4 6-13 l

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I b

CONTAIN!iENT SYSTEMS-SURVEILLANCE REQUIREMENTS (Contin'ued)-

3.

Verifying within 31 days after removal' that a laboratory-

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analysis of a carbon sample from'either,at least one test T

J.

- canister'or at least two carbon samples' removed from one of the charcoal,adsorbers demonstrates a removal effi-4 ciency of > 95% for. radioactive elemental iodine when the

~

sample is tested in accordance with ANSI.N510-1975 (130*C, 95% R.H.).

,Th'e carbon. samples' not' obtained from test canisters shal1 be p'repared -by emptying a representative sample from an_adsorber test tray section, mixing the adsorbent thoroughly', and obtair.ing samples at least two inches in diameter and with a ~1sngth equal to the thickness of the b'ed.

Succes'sive samples _will be removed from different test tray sections.

4.

Verifying a filter train flow rate of 20,000 cfm + 10%

i during system operation when-tested in accordance with ANSI NE10-1975.

After every J20 hours pf charcoal adsorber operation by-either:

. c.

L 1.

Verifying with'inL31 days after removal that a laboratory analysis of_a ca'rbon sample obtained from a test canister demonstrates a removal efficiency of > 955 for radio--

active elem5ntal' iodine wh'enithe sampTe is tested in accor-dance witR ANSI'N510-1975 (130*C,' 95% R.H.); or 2.

Verifying.within'31, days after removal that.a laboratory analysis of at least two carbon samples demonstrate a

~

removal efficiency ^of > 95%'for radioactive elemental i

. iodine when the' samples are; tested in accordance with

~

ANSI _ N510-1975 (130*C, 95% R.H.) and the-samples are prepared by ' emptying a representative sample from an.adsorber test tray s'ection, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with -

a length 1gual to, the thickness of the bed. Successive samples will be removed from different test. tray sections.

A s

CALVERT CLIFFS - UNIT 1 3/4 6-14 Amendment No. 33 t

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7

o CONTAlliMET;T SYSTEl15 SURVEILLANCE REQUIREMENTS (Continued)

Subsequent to reinstalling the adsorber' tray used for obtaining the carbon sample, the filter train shall be demonstrated OPERABLE'by also verifying that the charcoal adsorbers remove > 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-pla:e in '

accordance with ANSI fl510-1975 while operating the filter train at a flow rate of 20,000 cfm + 10%.

d.

At least once per 18 months by:

1.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is < 6 inches Water Gauge while operating the filter train at a flow rate of 20,000 cfm + 10%.

2.

Verifying that the filter train starts on a Containment Isolation test signal.

CALVERT CLIFFS - UNIT 1 3/4 6-15 Amendment No. 38,83

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) e.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove 3. 99% of the D0P when they are tested in place in accordance with ANSI N510-1975 while operating the filter train 'at a flow rate of 20,000 cfm + 10%.'

f.

After each complete.or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove 3.99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the filter train at a flow rate of 20,000 cfm

+ 10%.

g.

After maintenance affecting the air flow distribution by testing in-place and verifying that the air flow distribtuion is uniform within + 20% of the average flow per unit when tested in accordance with the provisions of Section 9 of

" Industrial Ventilation" and Section 8 of ANSI N510-1975.

CALVERT. CLIFFS - UNIT 1 3/4 6-16 Amendment No. 38

_p

TABLE 3.6-1 (Continued)

C0flTAINf1EllT ISOLATI0fl VALVES r-PEllETRATION ISOLATION ISOLATI0fl VALVE ISOLATION n,

il0.

CilANNEL IDENTIFICATION f10.

FUtlCTION TIME (SEC0!lDS)

L

?

61 NA 76Y-1 Refueling Pool Outlet NA NA 293!1-1 NA NA 293t1-1 NA E-NA 293f t-1 NA a

62 SIAS A MOV-6579 Containment Heating Outlet

<13 64 NA 238-1 Containment lleating Inlet NA i

(1) Manual or remote manual valve which is closed during plant. operation.

g (2) itay be opened below 300"F to establish shutdown cooling flow.

L (3) Containment purge isolation valves will be shut in MODES 1, 2, 3 and 4 per TS 3/4 6.1.7.

_ l llay be open on an intermittent basis under administrative control.

- Containment purge isolation valves isolation times will only apply for MODES 5 and 6 during which time these valves may be opened.

Isolation time is NA for MODES ~1, 2, 3 and 4 per TS 3/4 6.1.7 during which E

time these valves must remain closed.

E R

8-v.y O

CONTAINMENT SYSTEMS 3/4.6.5 COMBUSTIBLE GAS CONTROL HYDROGEN ANALYZERS LIMITING CONDITION FOR OPERATION

3. 6. 5.1 Two independent containment hydrogen analyzers shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTION:

With one hydrogen analyzer inoperable *, restore the inoperable analyzer to OPERABLE status,within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS l

l 4. 6. 5.1 Each hydrogen analyzer shall be demonstrated OPERABLE at least once per 92 days on a STAGGERED 1EST BASIS by performing a CHANNEL CALIBRATION using sample gases in accordance with manufacturers' recommendations, f

f

During the period from May 15 to July 15, 1983, one hydrogen analyzer may be made inoperable, at any given time, for the purpose of replacing system solenoid valves with environmentally qualified valves.

During this time, Specification 3.0.4 is not applicable to this requirement.

l CALVERT CLIFFS - UNIT 1 3/4 6-26 Amendment No. 60, 74, 8 3 i

t n

a

CO*. ::'J'E';T SYSTEMS SU:!E:LLA';CE REQUIREMENTS (Continued) 2.

Verifying that the HEPA filter banks remove 1 9% of the 9

DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the filter train at a flow rate of 2000 cfm + 10%.

3.

Verifying within 31 days after removal that a laboratory analysis of a carbon sample from either at least one test canister or. at least two carbon samples removed from one of the charcoal adsorbers demonstrates a removal efficiency of 1 90% for radioactive methyl iodide when the sample is tested in accordance with ANSI N510-1975 (130*C, 95L

..H.).

The carbon samples not obtained from test canisters shall be prepared by emptying a representative sample from an adsorber test tray section, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the b ed'.

Successive samples will be removed from different test tray sections.

4 lerifying a system flow rate of 2000 cfm + 10% during system operation when tested in accordance with ANSI

510-1975.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by either:

1.

Verifying within 31 days after removal that a laboratory aralysis of a carbon sample obtained from a test canister demonstrates a removal efficiency of > 90% for radioactive ethyl iodide when the sample is tested in accordance with ANSI N510-1975 (130*C, 955 R.H.); or 2.

7erifying within 31 days after removal tha't a laboratory analysis of at least two carbon samples demonstrate a removal efficiency of 1 90% for radioactive methyl iodide when the samples are tested in accordance with ANSI N510-1975 (130*C, 95% R.H.) and the samples are prepared CJ.L'J:F.T CLIFFS - UNIT 1 3/4 6-29 Amendment No. F 4

_. __ - _. ___ _ __ - _=_ __ - ____

CONTAlfetENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) by emptying a representative sample fro'm an adsorber test tray section, mixing the adsorbent thoroughly, and obtain-ing samples at least two inches in diameter and with a length equal to the thickness of the bed.

Successive samples will be removed from different test tray sections.

Subsequent to reinstalling the adsorber tray'used for obtaining the carbon sample, the filter train shal.1 be i

demonstrated OPERABLE by verifying that the charcoal adsorbers remove > 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place -in accordance with ANSI N510-1975 while operating.the ventilation system at a flow rate of 2000 cfm i 10%.

I d.

At leas,t once per 18 months by:

1.

Verifying that the pressure drop across the combined HEPA filters and charc.oal adsorber banks is < 6 inches Water Gauge while operating the filter train at a flow rate of 2000 cfm i 10%.

2.

Verifying that the filter train starts on a Containmerit Isolation Test Signal.

4 1

CALVERT CLIFFS - UNIT 1 3/4 6-30 Amendment No. 35, C 3 e

e

+,..

. PLANT SYSTEMS t

'3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION

3. 7. 6.1 - The control room emer'gency ventilation system shall be OPERABLE with:

a.

Two filter trains, b.

Two air conditioning uni,ts,*

c.

Two isolation valves in each control room outside air intake

duct, t

d.

Two isolation valves in the common exhaust to atmosphere duct, I

and-I e.

One isolation valve in the toilet area exhaust duct.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a.

With one filter train inoperable, restore the inoperable train to.

OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , b.

With one air conditioning unit inoperable, restore the inoperable l

unit to' OPERABLE status within 7 days or be in at least HOT STANDBY l

within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD _ SHUTDOWN within the following _

30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

+

I With one isolation valve per control room outside air intake duct c.

inoperable, operation may continue provided the other isolation valve in the same duct is maintained closedt otherwise,'be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d.

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

e.

With the toilet area exhaust duct isolation valve inoperable, restore the inoperable valve to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

For the duration of the October 1982 Unit 2 refueling ottage with Unit 2 in MODES 5 or 6 and one air conditioning unit inoperable, restore the-

)

inoperable unit to' operable status within 21 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

CALVERT CLIFFS - UNIT 1 3/4 7-17 Amendment No. E9, 76

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 4.7.6.1 The control room emergency ventilation system shall tne demon-strated OPERABLE:

a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the control room air temperature is 1 120 F.

~

b.

At least once per 31 days by, initiating flow through each HEPA filter and charcoal adsorber train and verifying that each train operates for at least 15 minutes.

c.

At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housing, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system by:

1.

Verifying that the charcoal adsorbers remove 2. 99% of a halogenated hydrocarbon refrigerant test gas when they are. tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 2000 cfm + 10%.

2.

Verifying that the HEPA filter banks remove > 99% of the DOP when they are tested in-place in accordance with AMSI N510-1975 while operating the ventilation system at a flow rate of 2000 cfm + 10%.

3.

Verifying within 31 days after removal that a laboratory analysis of a carbon sample from either at least one test canister or at least two carbon samples removed from one of the charcoal adsorbers demonstrates a removal efficiency of 2.90% for radioactive methyl iodide when the sample is tested in accordance with ANSI N510-1975 (130 C, 95%

R.H.).

The carbon samples not obtained from test canisters shall be prepared by emptying a representative sample from an adsorber test tray section, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed. Successive samples will be removed from different test tray sections.

CALVERT CLIFFS-UNIT 1 3/4 7-18 Amendment No.3 h O

e e

-Q

,,a-PLAr!T SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) 4.

Verifying a system flow rate of 2000 cfm + 10% during system operation when tested in accordance with ANSI N510-1975.

d.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by either:

1.

Verifying within 31 days after removal that a laboratory analysis of a carbon sample obtained from a test canister demonstrates a removal efficiency of > 90% for radioactive methyl iodide when the sample is tested in accordance with ANSI H510-1975 (130*C, 95% R.H.); or 2.

Verifying within 31 days after removal that a-laboratory analysis of at least two carbon samples demonstrate a removal efficiency of > 90% for radioactive methyl iodide when the samples are tested in accordance with ANSI N510-1975 (130*C, 95%'R.H.) and the samples are prepared by emptying a representative sample from an adsorber test tray section, mixing the adsorbent thoroughly, and obtaining samples at le'ast two inches in diameter and with a length equal to the thickness of the bed.

Successive samples will be removed from different test tray sections.

Subsequent to reinstalling the adsorber tray used for obtaining the ' carbon sample, the filter train shall be demonstrated OPERABLE by also verifying that the charcoal adsorbers remove > 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while opera' ting the ventila-tion system at a ' flow of 2000 cfm + 10%.

CALVERT CLIFFS-UNIT ]

3/4 7-19 Amendment No. 8 3

i

/

PLANT SYSTEMS j

SURVEILLANCE REQUIREMENTS (Continued) e.

At least once per 18 months by:

1.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is <'4 inches Water Gauge while operating the ventilation system at a flow rate of 2000 cfm + 10%.

2.

Verifying that on a control room high radiation test signal, the system automatically switches into a recircu-lation mode of operation with flow through the HEPA filter, and charcoal adsorber banks and that the isola-tion valves close.

f.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove 3.99% of the D0P when they are tested in place in accordance with ANSI N510-1975 while operating the filter system at a flow rate of 2000 cfm 1,10%.

g.

After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove 3.99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the filter system at a flow rate of 2000 cfm +

10%.

r CALVERT CLIFFS - UNIT 1 3/4 7-20

PLANT SYSTEMS 3/4.7.7 ECCS PUMP-R0OM EXHAUST AIR FILTRATION SYSTEM-LIMITING CONDITION FOR OPERATION 3.7.7.1 The ECCS pump room exhaust ventilation system shall be OPERABLE with one HEPA filter and charcoal adsorber train and two exhaust fans.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a.

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

b.

With the ECCS exhaust filter train inoperable, restore the filter train to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE0VIREMENTS 4.7.7.1 The ECCS pump room exhaust ventilation system shall be demon-strated OPERABLE:

a.

At least once per 31 days by initiating, from the control room, flow through the HEPA filter and charcoal adsorber train and verifying that each exhaust fan operates for at least 15 minutes.

b.

At least once per 18 months or (1) after any structural main-tenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any venti-lation zone communicating with the system by:

CALVERT CLIFFS - UNIT 1 3/4 7-21 e

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Conti'nued)

~

1.

Verifying that the charcoal adsorbers remove > 99% of a halogenated hydrocarbon refrigeran'. test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the filter train at a fl.ow rate of 3000 cfm + 10%.

2.

Verifying that the HEPA filter banks remove > 99% of the 00P when they are tested in-place in accordance with ANSI N510-1975 while operating the-filter train at a flow rate of 3000 cfm + 10%.

3.

Verifying within 31 days after removal that a laboratory analysis of a carbon sample from either at least one test canister or at least two carbon samples removed from one of the charcoal adsorbers demonstrates a removal effi-ciency of > 90% for radioactive methyl iodide when the sample is tested in accordance with ANSI N510-1975 (130 C, l

95% R.H.).

The carbon samples not obtained from test canisters shall be prepared by emptying a representative sa'mple from an adsorber test tray section, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thick-ness of the bed.

Successive samples will be removed from different test tray sections.

4.

Verifying a system flow rate of 3000 cfm + 10% during system operation when tested in accordance with ANSI N510-1975.

c.

After every-720 hours of charcoal adsorber operation by either:

1.

Verifying within 31 days after removal that a laboratory analysis of a carbon sample obtained from a test canister demonstrates a removal efficiency of > 90% for radioactive methyl iodide when the sample is tested in accordance with ANSI N510-1975 (130 C, 95% R. H.); or 1

CALVERT CLIFFS-UNIT 1 3/4 7-22 Amendment No. //,8 3 n

PLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 2.

Verifying within 31 days after removal -that a laboratory analysis of at least two carbon samples demonstrate a removal efficiency of 3,90% for _ radioactive methyl iodide

~

when the samples are tested in accordance with ANSI N510--

-1975 (130 C, 95% R.H.) and the samples are prepared by emptying a representative sample from an adsorber test tray section, mixing the adsorbent thoroughly, and obtain-ing samples at least two inches in diameter and with a length equal ~to the thickness of the bed.

Successive samples will be removed from different test tray sections.

Subsequent to reinstalling the adsorber. tray used for obtaining the carbon sample, the filter train shall be demonstrated OPERABLE by also verifying that the charcoal adsorbers remove 2,99% of a halogenated hydrocarbon.

refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the

' ventilation system at a flow rate of 3000 cfm + 10%.

d.

At least once per 13 months by verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is < 4 inches Water Gauge while operating the filter train at a flow rate of 3000 cfm + 10%.

CALVERT CLIFFS - UNIT 1 3/4 7-23 Amendment No. 38,_3

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) e.

' After each complete or partial replacement o,f a HEPA filter bank by verifying that the HEPA filter banks remove > 99% of the DOP when they.are tested in-place in accordance with ANSI H510-1975 while operating the filter train at a flow rate of 3000 cfm i 10%.

f.

After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove

> 995 of a halogenated hydrocarbon refrigerant test gas.when they are tested in-place in accordance with ANSI N510-1975 while operating the filter train at~ a flow rate of 3000 cfm i

.105.

g.

After maintenance affecting the air flow distribution by testing in-place and verifying that the air flow distribution is uniform within i 20% of the average flow per. unit when tested in accordance with the provisions of Section 9 of

" Industrial Ventilation" and Section 8 of ANSI N510-1975.

CALVERT CLIFFS-UNIT 1 3/4 7-24 Amendment No. 38

O REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued) b.

At least once per 18 months or (1) after any structural main-tenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any venti-lation zone communicating with the system by:

1.

Verifying that the' charcoal adsorbers remove > 99% of a-halogenated hydrocarbon refrigerant test gas when they are tested in-place in _ accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 32,000 cfm + 10%.

2.

Verifying that the HEPA filter banks remove > 99% of the

~

D0P when they are tested in-place in accordance with ANSI N510-1975 while operating-the ventilation system at a flow rate of 32,000 cfm + 10%.

3.

Ver'ifying within 31 days after removal-that a laboratory _

analysis of a carbon sample from either at least one test canister'or at least two carbon samples removed from one of the charcoal adsorbers demonstrates a removal efficiency of > 90% for radioactive methyl iodide when the sample is tested in accordance with ANSI N510-1975 (130 C, 95%

R.H.).

The carbon"samp;es not obtained from test canisters shall be pr'epared by emptying a representative sample from an adsorber test tray section, mixing the adscrbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed.

Successive samples will removed from different test tray sections.

4.

Verifying a system flow rate of 32,000 cfm + 10% during system operation when tested in accordance with ANSI N510-1975.

CALVERT CLIFFS - UNIT 1 3/4 9-13 Amendment No. 2 6

REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Conti'nued) c.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by either:

1.

Verifying within 31 days after removal that a laboratory analysis of carbon sample obtained from a test canister demonstrates a removal efficiency of 3,90% for radioactive methyl iodide when the sample is tested in accordance with ANSI N510-1975 (130 C, 95% R.H.); or 2.

Verifying within 31 days after removal that a laboratory analysis of at least two carbon samples demonstrate a removal efficiency of > 90% for radioactive methyl iodide when the samples are tested in accordance with ANSI N510-1975 (130*C, 95% R.H.) and the samples are prepared by emptying a representative sample from an adsorber test tray section, mixing the adsorbent thercughly, and obtain-ing samples at least two inches in diameter and with a length equal to the thickness of the bed.

Successive samples will be removed from different test tray sections.

Subsequent to reinstalling the adsorber tray used for obtaining the carbon sample, the filter train shall be demonstrated OPERABLE by also verifying that the charcoal adsorbers remove 3. 99% of a halogenated hydrocarbon refrigerant. test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 32,000 cfm + 10%.

CALVERT CLIFFS - UNIT 1 3/4 9-14 Amendment No. - ?

'~

0 -

v

pR RfCp

+?

[o, UNITED STATES

! ) 3,gf(.,g NUCLEAR REGULATORY COMMISSION g//

E WASHINGTON. D. C. 20555 BALTIMORE GAS AND ELECTRIC COMPANY DOCKET N0. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.66 License No. DPR-69 1.

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

A.

The application for amendment by Baltimore Gas & Electric Company (the licensee) dated February 24, 1983 as supplemented by letter dated March 22, 1983, complies with the standards and requireme'nts of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth ir.

10 CFR Chapter I; B.

The faci,11ty will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission'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 Commission's regulations and all applicable requirements have been satisfied.

) 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. 66, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

{k.xls. lll.

l8s.'.%lf.

Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

~

Changes to the Technical Specifications Date of Issuance: May 5, 1983 I

ATTACHMENT TO LICENSE AMENDMENT NO. 66 FACILITY OPERATING LICENSE NO. DPR-69 DOCKET N0. 50-318' Replace thi following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and contain ~ vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

Pages 2-9

^

B 2-7 3/4 3-2

~

3/4 3-6 3/4 3-7 3/4 6-1 3/4 6-14 3/4 6-15 3/4 6-26 3/4 6-29' 3/4 6-30 3/4 7-18 3/4 7-19 3/4 7-22 3/4 7-23 3/4 9-13 3/4 9-14

.l m

-s ee---

-aee - v e

swr y'

,Lme3--

-w r

w-

,e w

rwy

TABLE 2.2-1 (Cont'd) n?

M REACTOR PROTECTIVE IllSTRUMEllTATI0ff TRIP SETPOIllT LIMITS G

FUNCTIONAL UtilT TRl_P SETPOINT ALLOWABLE VALUES T

4.

Pressurizer Pressure - liigh 1 2400 psia 1 2400 psia E

5.

Containment Pressure - High 1 4 psig 1 4 psig

--i m

6.

Steam Generator Pressure - Low (2)

> 685 psia

> 685 psia 7.

Steam Generator Water Level - Low

> 10 inches below top

> 10 inches below top of feed ring, of feed ring.

8.

Axial flux offset (3)

Trip setpoint adjusted to Trip setpoint adjusted to not exceed the limit lines not exceed the limit lines

. of Figure.2.2-1.

of Figure 2.2-1.

9.

Thermal Margin / Low Pressure (1.)

a.

Four Reactor Coolant Pumps Trip setpoint adjusted to Trin setpoint adjusted to Operating not exceed the limit lines be not less than the larger of Figures 2.2-2 and 2.2-3.

of (1) the value calculated from Figures 2.2-2 and 2.2-3 and (2) 1875 psig.

b.

Steam Generator Pressure Difference - liigh (1)

~ 135 psid

--< 135 psid s

{6 10.

Loss of Load it. A.

il. A.

l h

g 11.

Rate of Change of Power - liigh (4) 1 2.6 decades per minute 1 2.6 decades per minute Op TABLE fl0TATION

-4 O

(1 ) Tripmaybebypassedbe}ow10 % of RATED TilERMAL POWER; bypass shall be automatically removed when m

- 10~ % of RATED TilERNAL POWER.

TilERiiAL POWER is >

e a,

J

t l

e a

isp 5

8 n

7 e

h e

w vo d

b e

a vo r

m o

er ta y

l d

l e

a v

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a r

mo y

t l

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a ac e

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t R

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W mo a

O t

h P

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a L

s A

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1 f

b a

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)

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l b

T

)

a d

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'D n

s E

't o

R T

n C

s E

A o

(

s W

R C

a O

(

p P

f S

y o

l b

L t0 A

l 1

I iR 2

T a

RE 1

2 A

i EW T

s iO e

l 2

0 p

TP v

l o

f E

5 DL b

L E

8 EA a

B L

7 Tl i

A B

AR d

T A

w RE n

l T

o i

a fT le o

~,

b D

%E d

5T 0

A e

1 1

s R

s w

w a

of o

p l o l

y e

e b

b%

b 5

y d1 d

l e

e s >-

s l

a s

s u

as a

n pi p

a y

y a

bR b

9 r

E e

eW e

b bO b

P y

y y

a aL a

m mA m

l i

p pR.

p i

i E i

r ri r

l T

TT T

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2 3

4

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O 4 9G :*

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g3&a-O.

.?

n 6

1 r

LIMITING SAFETY SYSTEM SETTINGS BASES i

The Thermal Margin / Low Pressure trip setpoints include allowances for equipment response ' time, measurement uncertainties, processing error and a further allowance of 40 psia to compensate for the time delay associated with providing effective tenni' nation of the occurrence that exhibits the most rapid _ decrease in margin to the safety limit.

Asymmetric-Steam Generator Transient Protection Trio Function (ASGTPTF)

The ASGTPTF utilizes steam generator pressure inputs to the TM/LP calculator, which causes a reactor trip when the difference in pressure between.the two steam genera ors exceeds the trip setpoint.

The ASGTPTF is designed to provide a reactor trip for those Anticipated Operational Occurrences associated with secondary system malfunctions which_ result in asymmetric primary loop coolant tenperatures. The most limiting event is the loss of load to one steam generator caused by a single Main Steam Isolation Valve closure.

The equipment trip setpoint and allowable values are calculated to account for _ instrument uncertainties, and will ensure a trip at or before reaching the analysis setpoint.

i Loss of Load A Loss of Load trip causes a direct reactor trip when operating above 15% of RATED THERMAL POWER.

This trip provides turbine protection, reduces the severity o*f the ensuing transient and helps avoid the lifting of the main steam line safety valves during the ensuing transient, thus extending-the service life of these valves.

No credit was taken in the accident analyses for operation of this trip.

Its functional capability is required to enhance overall plant equipment service life and reliability.

Rate of Change of Power-High The Rate of Change of Power-High trip is provided to protect the core during startup operations and its use serves as a backup to the administra-tively enforced startup rate limit.

Its trip setpoint does not correcpond to a Safety Limit and no credit was taken in the accident analyses for operation of this trip.

Its functional capability at the specified trip setting.is required to enhance the overall reliability of the Reactor Protection System.

CALVERT CLIFFS - UNIT 2 B 2-7 Amendment No. 9, Jg, 3J, gy, : 3

+

r 3/4.3 INSTRUMENTATION

~

3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1.1 As a minimum, the reactor protective instrumentation channels-and bypasses of Table 3.3-1 shal,1 be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2.

APPLICABILITY: As shown in Table 3.3-1.

i ACTION:

As shown in Table 3.3-1.

SURVEILLANCE REQUIREMENTS 4. 3.1.1.1 Each reactor protective instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3-1.

4.3.1.1.2 The logic for the bypasses shall be demonstrated OPERABLE prior to each reactor startup unless performed during the preceding 92 days. The total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by bypass operation.

4.3.1.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of.each reactor trip function shall be demonstrated to be within its limit at least once per 18 months.

Each test shall include at least one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the " Total No. of Channels" column of Table 3.3-1.

CALVERT, CLIFFS - UNIT 2 3/4 3-1

TABLE 3.3-1 REACTOR PROTECTIVE INSTRUMENTATION 9

MINIMUM TOTAL N0.

CilANNELS CilANNELS APPLICABLE I

P FUNCTIONAL UNIT OF CilANNELS TO TRIP OPERABLE MODES ACTION l

h

1. ' Manual Reactor Trip 2

1 2

1, 2 and

1

[

h 2.

Power Level - liigh 4

2 3(f) 1, 2 2#,

3.

Reactor Coolant Flow - Low 4/SG' 2(a)/SG 3/SG 1, 2 (e)

-2#

4.

Pressurizer Pressure - liigh 4

2 3

1, 2 2#

5.

Containment Pressure - liigh 4

2 3

1, 2 2#

d. Steam Generator Pressure - Low 4/SG 2(b)/SG 3/SG 1, 2 2#

7.

Steam Generator Water

{

Level - Low 4/SG 2/SG 3/SG 1, 2 2#

[

8.

Axial Flux Offset 4

2(c) 3 1

2#

9..i.

ihennal Ilargin/ Low Pressurc 4 2(a) 3 1, 2 (e) 2#

b.

Steam Generator Pressure Difference - liigh 4

2(a) 3 1, 2 (e) 2# -

s a

10.

Loss of Load 4

2(c) 3 1

2#

i 5.

2 a

!?

O C3

TABLE 3.3-1 (Continued)

ACTION STATEMENTS b.

Within one hour, all functional units receiving an input from the inoperable channel.are also placed in the same condition-(either bypassed or tripped, as applicable) as that required by a. above for the inoperable channel.

c.

The Minimum Channels OPERABLE requirement is met; howevsr, one additional channel may be bypassed for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months while performing tests and maintenance on that channel provided the other inoperable channel is placed in the tripped condition.

'ACTIO" 3 With the number of channels OPERABLE one less than required by the. Minimum Channels OPERABLE requirement, verify compli-ante with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

ACTION 4-With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for surveillance testing per Specification 4.3.1.1.

CALVERT CLIFFS - UNIT 2 3/4 3-5 O

s-

M n

TABLE 3.3-2 i

My REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES

-1 b

I FUNCTIONAL UNIT RESPONSE TIME

'W f

1.

Manual Reactor Trip Not Applicable 2.

Power Level - High s 0.40 seconds *# and s 12.0 seconds ##

ro 3.

Reactor Coolant Flow - Low 1 0.50 seconds 4.

Pressurizer Pressure - High

< 0.90 seconds 5.

Containment Pressure - High 1 0.90 seconds 6.

Steam Generator Pressure - Low s 0.90 seconds 7.

Steam Generator Water Levil - Low s 0.90 seconds 8.

Axial Flux Offset

< 0.40 seconds *# and < 12.0 seconds ##

9.a.

Thermal iargin/ Low Pressure

< 0.90 seconds *# and s 12.0 seconds ##

b.

Steam Generator Pressure Difference - High 1 0.90 seconds 10.

Loss of Load Hot Applicable N

to E

11. Wide Range Logarithmic Neutron Flux Monitor Not Applicable 2

5

Neutron detectors are exempt from response time testing.

Response' time of the neutron flux signal portio 6 2

P of the channel shall be measured from detector output or input of first electronic component in channel.

Response time does not include contribution of RTDs.

E

1. RTD response time only.

This value is equivalent to the time. interval required for the RTDs output -

p to achieve 63'2% of its total change when subjected to a step change in RTD temperature.

y b

c'

TABLE 4.3-1 c,4 2-

' C: '

REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS 9

--i E2 CilANNEL MODES IN WillCll

'l CllANNEL CilANNEL FUNCTIONAL SURVEILLANCE UI FUNCTIONAL UNIT CilECK CAllBRATION TEST REQUIRED j

sY. ' Manual Reactor Trip N.A.

N.A.

S/U(1) fl. A.

[

2.

Power Level - liigh a.

Nuclear Power S

D(2),it(3),Q(5) M 1, 2 b.

AT Power S

D(4),R M

i N

3.

React,or Coolant Flow - Low S

R M

1, 2 4.

Pressprizer Pressure - liigh S

R M

1, 2 5.

Containment Pressure - liigh S

R M

1, 2 da

6. ' Steam Generator Pressure - Low S

R M

1, 2 7.

Steam Generator Water Level - Low S

R M

1, 2 s

8.

Axia! Flux Offset S

R M

1

(

,N 9.a.

Thermal !1argin/ Low I'ressure S

R 11

.I, 2

, a 6

b.

Steam Generator Pressure Difference -

E-liigh S

R

!1 1, 2 10.

Loss of Load N.A.

N.A.

S/U(1)

N.A.

l E.

M O

C)

g TABLE 4.3-1-(Continued)

Gg REACTOR PROTECTIVE INSTRUMENTATION' SURVEILLANCE REQUIREMENTS.

e n

k CilANNEL-MODES IN Wl'lICil' y

CilANNEL

. CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CilECK CALIBRATION TEST REQUIRED

11. Wide Range Logarithmic Neutron S

R(5)

S/U(1)

'1, 2,'3, 4.,

H Flux Monitor 5 and *r m

12.

Reactor Protection System Logic Matrices h.A.

N.A.

M and'S/U(1) 1, 2 13.

Reactor Protection System Logic Matrix Relays N. A.

N.A.

M and S/U (1) 1, 2 14.

Reactor Trip Breakers N.A.

N.A.

M 1, 2'and

Y m

D

/

e 9

4

l' l*3/4.6' CONTAINME"T SYSTEMS 3/4.6.l' PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OEPRATION 3.6.1.1 Primary CONTAINtiENT INTEGRITY shall be maintained.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and-in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REOUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

a.

At least once per 31 days by verifying that all penetrations

not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-1 of Specification 3.6.4.1.

I b.

By verifying that each containment air lock is OPERABLE per Specification 3.6.1.3.

c.

By verifying that the equipment hatch is closed and sealed, prior to entering flode 4 following a shutdown where the equipment hatch was opened, by conducting a Type B test per Appendix J to 10 CFR Part 50.

Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked.. sealed, or otherwise secured in the closed position.

These penetrations shall be verified c.losed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.

CALVERT CLIFFS - UNIT 2 3/4 6-1 Amendment No. 3, p 3 s

. -. ~

CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION-3.6.1.2 Containment leakage rates shall be limited to:

a.

An overall integrated leakage rate of:

1.

<La (346,000 SCCM), 0.20 percent by weight of the containment ~

l air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at P, 50 psig, or a

2.

<Lt (44,600 SCCM), 0.042 percent by weight of the containment I

air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at a reduced pressure of-P. 25 psig, t

b.

A combined leakage rate of < 0.60 L (207,600 SCCM) for all penetra-l~

tions and valves subject to Type B $nd C tests when pressurized to P.

3 APPLICABILITY: N0 DES 1,2,3and4.

ACTION:

With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L SCCM),.or 0.75 L (33,400 SCCM), as applicable, J

or (b)'with the 8ea(259,500suredcombinedleakagerkte.forallpenetrationsand valves subject to Types B and C tests exceeding 0.60 L, restore the leakage a

rate (s) to within the limit (s) prior to increasing the Reactor Coolant System temperature above 200 F.

SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4 - 1972:

Three Type A tests (0verall Integrated Containment Leakage Rate) a.

shall be conducted at 40 + 10 month intervals during shutdown at (50 psig) er at P either P,The third test of bac(25 psig) during each 10-year service period.

h set shall be conducted during the shutdown for the 10-year plant inservice inspection.

CALVERT, CLIFFS - UNIT 2 3/4 6-2 Amendment No. 56

CONTAINMENT SYSTEMS 3/4.6.3 IODINE REMOVAL SYSTEM

-LI"ITING CONDITION FOR OPERATION ~

3.6.3.1 Three independent containment iodine filter trains shall-be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one iodine filter train inoperable, restore the inoperable t' rain to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.3.1 Each iodine filter train shall be demonstrated OPERABLE:

At least once per 31 days on a STAGGERED TEST BASIS by initiat-a.

ing, from the control room, flow through the HEPA filter and charcoal adsorber train and verifying that the train operates for at least 15 minutes.

-b.

At least once per 18 months or (1) after.any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system by:

1.

Verifying that the charcoal adsorbers remove > 99%

of a halogenated hydrocarbon refrigerant test gas when

~

they are tested in-place in accordance with ANSI N510-1975 while operating the filter train at a flow rate of 20,000 cfm + 10%.

2.

Verifying that the HEPA filter banks remove > 99% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the filter train at a flow rate of 20,000 cfm + 10i!.

E

~15 CALVERT CLIFFS - UNIT 2 3/4 6-13 e

CONTAINMENT SYSTEMS SURVEILLANCE RE0OIRE'MENTS (Continued) 3.

Verifying within 31. days after removal that a laboratory analysis of a carbon sample from either at least one test canister or at least two carbon samples removed from one of the charcoal adsorbers demonstrates a removal effi-ciency of > 95% for radioactive elemental iodine when the sample is tested in accordance with ANSI. N510-1975 (130'C, 95% R.H.).

The carbon samples not obtained from test canisters shall be prepared by snptying a representative sample from an adsorber test tray section, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed.

Successive samples will be removed from different test tray sections.

4.

Verifying a filter train flow rate of 20,000 cfm + 10%

during system operation when tested in accordance with ANSI N510-1975.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by either:

c.

1.

Verifying within 31 days after removal that a laboratory analysis of a carbon' sample obtained from a test canister demonstrates a removal efficiency of > 955 for radio-active elemental iodine when the sampTe is tested in accor-dance with -ANSI N510-1975 (130*C, 95% R.H.); or 2.

Verifying within 31 days after removal that a laboratory analysis of at least two carbon samples demonstrate a removal efficiency of,95% for radioactive elemental 2

iodine when the samples are tested in accordance with ANSI N510-1975 (130*C, 95% R.H.) and the samples are prepared by emptying a representative sample from an adsorber test tray section, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed.

Successive samples will be removed from different test tray sections.

CALVERT CLIFFS - UNIT 2 3/4 6-14 Amendment No. C 0 CONTAI*iF.Ef;T SYSTEf ts SURVEILLANCE REQUIREMENTS (Continued)

Subsequent to reinstalling the adsorber. tray used for obtaining the _ carbon sample, the filter train shall be demonstrated OPERABLE by-also verifying that the charcoal adsorbers re' move > 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with Ai:SI N510-1975 while operating the filter train at a flow rate of 20,000 cfm + 10%.

d.

At least once per 18 months by:

1.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is <-6 inches Water i

Gauge while operating the filter train at a flow rate of 20,000 cfm + 10%.

2.

Verifying that the filter train starts on a Containment Isolation test signal.

CALVERT CLIFFS - UNIT 2 3/4 6-15 Amendment No. 27, o J f

e

--.v 2

_u

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) e.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks' remove > 99% of the D0P when they are tested in place in accordance with ANSI N510-1975 while operating the filter train at a flow rate of 20,000 cfm + 10%.

f.

After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove

> 99% of a halogenated hydrocarbon refrigerant test gas.when they are tested in-place in accordance with A!1SI N510-1975 while operating the filter train at a ficw rate of 20,000 cfm

+ 10%.

g.

After maintenance effecting the air flow distribution by testing in-place and verifying that the air flow distribution is uniform within + 20% of the average flow per unit when tested in accordance with the prJViGions Of Section 9 of

" Industrial Ventilation" and Section 8 of ANSI il510-1975.

CALVERT CLIFFS - UNIT 2 3/4 6-16 Amendment No. 21

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CONTAINMENT SYSTEMS.

3/4.6.5 COMBUSTIBLE GAS CONTROL HYDR 0 GEN ANALYZERS LIMITING CONDITION FOR OPERATION 3.6.5.l Two independent containment hydrogen analyzers shall be OPERABLE.

APPLICALILITY: MODES 1 and 2.

ACTION:

With one hydrogen analyzer inoperable *, restore the ir. operable analyzer to OPERABLE status within 30 days or be in at least HOT STANDBY within

~

the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.6.5.1 Each hydrogen analyzer shall be demonstrated OPERABLE at least once per 92 days on a STAGGERED TEST BASIS by performing a CHANNEL CALIBRATION using sample gases in act'ordance with manufacturers' recommenda tions.

During the period from tiay 15 to July 15, 1983, one hydrogen analyzer may be made inoperable, at any given time, for the purpose of replacing system solenoid valves with environmentally qualified valves.

During t.his time, Specification 3.0.4 is not applicable to this requirement.

CALVERT CLIFFS - UNIT 2 3/4 6-26 Amendment No. 42 EE, E C N

-w 9.-,

CONTAINMENT SYSTEMS SURVEILLANCE REOUIRIMENTS (Continued) 2.

Verifying that the HEPA filter banks remove > 99% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the filter train at a flow rate of 2000 cfm i 10%.

3.

Verifying within 31 days after removal that a laboratory analysis of a carbon sample from either at least one test canister or at least two carbon samples removed from one of the charcoal adsorbers demonstrates a removal efficiency of > 90% for radioactive methyl iodide when the sample is tested in accordance with ANSI N510-1975 (13C*C, 95%

R.H.).

The car' on samoles not obtained from test canisters c

shall be prepared i3y emptying a representative sanale from an adsorber test tray section, mixing the adsorbant thcroughly, and obtaining samples at least two inches in diameter and with a length equal to the thicsness of the bed. Successive samples will be removed from different test tray sections.

4 Verifying a system flow rate of 2000 cfn i 10% during system operation when tested in accordance with ANSI N510-1975.

c.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by either:

1.

Verifying within 31 days after removal that a laboratory analysis of a carbon sample obtained from a test canister demonstrates a remova) efficiency of > 90% for radioactive methyl iodide when the sample is tested in accordance with ANSI N510-1975 (130*C, 95% R.H.); or 2.

Verifying within 31 days after removal that a laboratory analysis of at least two carbon samples demonstrate a removai efficiency of > 90% for radioactive methyl iodide when the samples are tested in accordance with ANSI

~

N510-1975 (130*C, 95% R.H.) and the samples are prepared CAL'KRT CLIFFS - UNIT 2 3/4 6-29 Amendment No.f r

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) by empty.ing a representative sample from an adsorber test tray section, mixing the adsorbent thoroughly, and obtain-ing samples at least two inches in diameter and with a length equal to the thickness of the bed. Successive samples will be removed from different test tray sections.

Subsequent to reinstalling the adsorber tray used for obtaining the carbon sample, the filter train shal! be i

demonstrated OPERABLE by verifying that the charcoal adsorbers remove >; g9% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with A'iti N510-1975 while optrating tae ventilation syste.t et a flew rate of 2000 cf.n + 10%.

I d.

At least once per 18 months by:

1.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber tanks is.< 6 inches Water Gauge while operating the filter train at a flow rate of 2000 cfm + 10%.

2.

Verifying that the filter train starts on a Containment Isolation Test Signal.

1 I

CALVERT CLIFFS - UNIT 2 3/4.6-30 Amendment No. /Ji t: -"

O e

w

- ~ - -

r-

+

p-g-p7--

PLANT SYSTEMS 3/4.7.6 CONTROL RdOM EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION

3. 7. 6.1 The control room emergency ventilation system shall be OPERABLE with:

a.

Two filter trains, b.

Two air conditioning units, Two isolation valves in each control room outside air intake

duct, d.

Two isolation valves in the cot. mon exhaust to atmosphere duct, and E.

Cne isolation valve in the toilet area exhaust duct.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a.

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

b.

With one air conditioning unit inoperable, restore the inoperable unit to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following I

30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c.

With one isolation valve per control room outside air intake duct l

inoper able, operation may continue provided the other isolation valve in the same duct is maintained closed;- otherwise, be in at-least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD Sh<TDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d.

With one common exhaust to atmosphere duct isolation valve in-operable, restore the inoperable valve to OP.ERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 ho~urs.

e.

With the toilet area exhaust duct isolation valve inoperable, restore the inoperable valve to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or'be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

CALVERT CLIFFS - UNIT 2 3/4 7-17 Amendment No. f), f), 57

W.

PLANT SYSTEMS SURVEILLANCE RE0VIREMENTS 4.7.6.1 The control room emergency ventilation system shall be demon-strated OPERABLE:

a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the control room air temperature is 1 120 F.

b.

At least once per 31 days by initiating flow'through each HEPA filter and charcoal adsorber train ar.d verifying that each train operates for at least 15 minutes.

c.

At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal aosorber housing, or (2) following painting, fire ar chemical release in any vertilation zona communicating wich the systen by:

1.

Verifying that tha charcoal 3drorbers remove ;_99% of a halogenated hydrocarbon refrigerant test cas when they are tested in-place in accordance with ANSI N510-1975 whil'e operating the var.tilation system at a flow rate of 2000 cfm + 10%.

2.

Verifying that the HEPA filter banks remove > 99% of the D0P when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 2000 cfm + 10%.

3.

Verifying within 31 days after removal that a laboratory analysis of a carbon sample from either at least one test canister or at least two carbon samples removed from one of the charcoal adsorhers demonstrates a r.emoval efficiency of > 90% for radioactive methyl iodide when the sample is tested in accordance with ANSI N510-1975 (130 C, 95%

R.H.).

The carbon samples not obtained from test canisters shall be prepared by emptying a representative sample from an adsorber test tray section, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to.the thickness of the 7

l bed.

Successive samples will be removed from different test tray sections.

CALVERT CLIFFS-UNIT 2 3/4 7-18 Amendment No. C6

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.

Verifying a system flow rate of 2000 cfm i 10% during system operation when tested in accordance with ANSI N510-1975.

d.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by either:

1.

Verifying within 31 days after removal that a laboratory analysis of a carbon sample obtained from a test canister demonstrates a removal efficiency of > 90% for radioactive methyl iodide when the sample is tested in accordance with ANSI N510-1975 (130 C, 95% R.H.); or 2.

Verifying within 31 days after removal that a laboratory analysis of at least two carbon saaples demonstrate a removai efficiency of > 90% for radioactive methyl iodide when the samples are tested in accordance with ANSI H510-1975 (130*C, i

95% R.H.) and the samples are prepared by emptying a repr'esentative sample from an edsorber test tray section, mixing the adsorbent thoroughly, ano obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed.

Successive sampies will be removed from different test tray sections.

Subsequent to reinstalling the adsorber tray used for obtaining the carbon sample, the filter train shall be demonstrated OPERABLE by also verifying that the charcoal adsorbers remove > 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI f{510-1975 while operating the ventila-tion system at a flow of 2000 cfm i 10%.

CALVERT CLIFFS-UNIT 2 3/4 7-19 Amendment No. S5

,.._s

't PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) e.

At least once per 18 months by:

1.

Verifying that the pressure drop across' the combined HEPA filters and charcoal adsorber banks is < 4 inches Water Gauge while operating the ventilation system at a flow rate of 2000 cfm + 10%.

2.

Verifying that on a control room high radiation test signal, the system autamatically switches into a recircu-lation mode of operation witia flow through the HEPA filters and charcoal adsorber banks and that the isol3-tion valves close, f.

After each complete or partial replacement of a HEFA filter bank by verifying that the HEPA filter banks remove > 99% of the D0P when they are tested in place in accordance Wlth /.NSI H510-1975 while operating the filter system at a flow rite of 2000 cfm + 10%.

g.

After each complete or partial replace. Tent of a charcoal adsorber bank by verifying that the charccal adsorbers remove

> 99% of a halogenated hydrocaroon refrigerant test gas when they are testad in-place in accordance with ANSI N510-1975 while operating the filter system at a flow rate of 2000 cfm +

10%.

CALVERT CLIFFS - UNIT 2 3/4 7-20

' O t

PLANT SYSTEMS 3/4.7.7 ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.7.1 The ECCS pump room exhaust ventilation system shall be OPERABLE with one HEPA filter and charcoa1 adsorber train and two exhaust fans.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a.

With one ECCS pump room exhaust fan inoperable, restore the inopersble fan to OPERAELE status within 7 days or be in at least HOT STANDBf within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With the ECCS~ exhaust filter train inoperable, restore the filter train to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STAND 3Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and'in COLD SHUTDOWN within the followir.g 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

-SURVEILLANCE REQUIREMENTS 4.7.7.1 The ECCS' pump room exhaust ventilation system shall be demon-strated OPERABLE:

a.

At least once per 31 days by initiating, from the control rcom, flow through the HEPA filter and charcoal adsorber train and verifying that each exhaust fan operates for at least 15 minutes.

b.

At least on e per 18 months or (1) after any structural main-tenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any venti-lation zone communicating with the system by:

CALVERT CLIFFS - UNIT 2 3/4 7-21

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I e-w.

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 1.

Verifying that the charcoal adsorbers remove > 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the filter train at a flow rate of 3000 cfm + 10%.

2.

Verifying that the HEPA filter banks remove > 99% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the filter train at a flow rate of 3000 cfm + 10%.'

3.

Verifying within 31 days after removal that a laboratory aralysis of a carbon sample from either at least one test L

canister or at least two ~ carbon samples removed frcm one of the charcoal adsorbers demonstrates a removal effi-i

. ciency of > 90% for radioactive methyl iodide when the i

(

sample is tested in accordance with ANSI N510-1975 (130 C, l

95% R.H.).

The carbon samples not obtained from test i

canisters shall be prepared by enptying a representative sample from an adsorber test tray section, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thick-ness of tne bed. Successive samples will be removed frca different tcst tray sections.

4.

Verifying a system flow rate of 3000 cfm + 10% durin~g systtm operation when tested in accordance with ANSI N510-1975.

Afterevery720hoursofch$rcoaladsorberoperationbyeither:

c.

l 1.

Verifying within 31 days after removal that a laboratory analysis of a carbon sample obtained from a. test canister demonstrates a removal efficiency of > 90% for radioactive methyl iodide when the sample is tested 'in accordance with ANSI N510-1975 (130 C, 95% R. H.); or CALVERT CLIFFS-UNIT 2 3/4 7-22 Amendment No.55, 3 3 i

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PLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 2.

Verifying within 31 days after removal that a laboratory analysis of at least two carbon samples demonstrate a removal efficiency of > 90% for radioactive methyl iodide when the samples are tested in accordance with ANSI N510-1975 (130 C, 95% R.H.) and the samples are prepared by emptying a representative sample from an adsorber test tray section, mixing the adsorbent thoroughly, and obtain-ing samples at least two inches -in diameter and with a length equal to the thickness of the bed. Successive samples will be renoved from different test tray sections.

Subsequent tc reinstalling the adsorber tray used for obtaining the cerban samp? e, the filter train sha'l be demons tratzd 0.cERABLE by also verifying that the charcoal adscreers remove > 997, of a halogenated hydrocarbor I

refrigerant test gas when they are tested in-place in accordar.ce with ANSI N510-1975 while operating the ventilation system et a flow rate of 2000 cfr. i 10%.

d.

At least once per 13 months by verifyir.g that che pressure drop across the combined HEPA filters and charceal adsorber banks is e 4 inches Water Gauge wnile operating the filter train at a flow rate of 3000 cfm i 10%.

CALVERT CLIFFS - UNIT 2 3/4 7-23 Amendment No. 27, r 3' 4

A A

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) e.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove > 99% of the D0P when they are tested in-place in accordance with ANSI N510-1975 while operating the filter train at a flow rate of:

3000 cfm + 10%.

f.

After each complete or partial replacement of a charcoal-adsorber bank by verifying that the charcoal adsorbers remove-99% of a halogenated hydrocarbon refrigerant test gas ~ when they are tested in-place in accordance with ANSI N510-1975 while operating the filter train at a flow rate of 3000 cfm +

10S.

g.

After maintenance affecting the air flow distributior. by testing in-place and verifying that the air floet distribution 4

l is uniform within + 20*,' cf the &verace flow per unit whcn tested in tecordance with the provisions of Section 9 c#

1

Indestrial Ventilation" and Section 8 cf ANSI N510-1975.

CALVERT CLIFFS-UNIT 2 3/4 7-24 Amendment No. 21

REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued) b.

- At least once per 18 months or (1) after any structural main-tenance an the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any venti-lation zone communicating with the system by:

1.

Verifying that the charcoal adsorbers remove > 99% of a halogenated hydrochrban refrigerant test-gas when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at-a flow rate of 32,000 cfm + 10%.

2.

Verifying that the HEPA filter banks remove > 99% of the DOP when they are tested in-place in accordance with-ANSI N510-1975 while operating the ventilation system at a flow rate of 32,000 cfm + 10%.

3.

Veritying within 31 days af ter removal that a laboratory I

analysis of a carbon sample frcm either at least one test canister or at least two carbon samples removed from one of the charcoal adsorcers demonstrates a removal efficiency of > 90% for radioactive methyl icdide when the sampic is tested in accordance.with ANSI N510-1975 (130'C,'95%

i R.H.).

The carbon samples not obtained from test canisters snall be prepared by emptying.a representative sample frem ar. ads 6rber test tray section, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed.

Successive samples will be removed from different test tray sections.

4 Verifying a system flow rate of 32,000 cfm + 10% during system operation when tested in accordance with ANSI N510-1975.

CALVERT CLIFFS - UNIT 2 3/4 9-13 Amendment No.6,6 6

m-REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued)'

c.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by either:

l.

Verifying within 31 day: after removal that a laboratory analysis of carbon sample obtained from a test canister demonstrates a removal efficiency of 3,90% for radioactive methyl iodide when the sample is tested in accordance with ANSI N510-1975 (130 C, 95% R.H.); or 2.

Verifying within 31 days after removal that a laboratory analysis of at least two carbon samples demonstrate a removal efficiency of 3,90% for radioactive methyl iodide -

when the samples are tested in accordance with ANSI N510,

1975 (130*C, 95% R.H.) and the samples are prepared by emptying a representative sample from an adscrber test tray section, mixing the adsorbant thoroughly, and obtain-i ing samples at least two inches in diameter and with a length equal to the thickness of the bed.

Successive samples will be removed from different test tray sections.

Subsequent to reinstalling the adsorber tray used for

~

obtaining the carbon sample, the filter train shall be demonstrated OPERABLE by also verifying that the charcoal adsorbers remove _3f 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 32,000 cfm + 10%.

t CALVERT CLIFFS - UNIT 2 3/4 9-14 Amendment No.

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