Text

Amends 139 & 122 to Licenses DPR-53 & DPR-69,respectively, Raising Tech Specs Fuel Enrichment Limits for Spent Fuel Storage to 5.0 Weight Percent U-235
	ML20005G253
Person / Time
Site:	Calvert Cliffs
Issue date:	01/10/1990
From:	Capra R; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20005G254	List: ML20005G253; ML20005G255;
References
	NUDOCS 9001180340
	Download: ML20005G253 (43)
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NUCLEAR REGULATORY COMMISSION j

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WASHING TON, D. C. 20555 1i

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BALTIMORE GAS.AND ELECTRIC COMPANY l

DOCKET N0.~50-317:

CALVERT. CLIFFS NUCLEAR POWER PLANT.. UNIT 1 AMENDMENT-TO FACILITY OPERATING. LICENSE

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1 Amendment No.139 s

License No. DPR-53 l.

1.

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

.A.

The application for amendment by. Baltimore Gas and Electric Company (the licensee) dated June 9, 1988, as supplemented on October 25,.

November 17 and December 28, 1988,- complies with the standards and.

K requirementsof:theAtomicEnergyActof1954,asamended(theAct)

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and the Comission's rules and regulations set forth in 10 CFR Chapter I;

-B.-

TheLfacility will operate in conformity with the application.

-the provisions-of the'Act, and the rules and regulations of the Comission; L

C.

Thereisreasonableassurance(i)thattheactivitiesauthorized by this amendment can be conducted without endangering the health

and, safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; i

D.

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

- E.

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

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-2.

Accordingly, the license is amended by changes to the Technical

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-Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. '0PR-53 is hereby amended to read as follows:

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i; (2): Technical Specifications-I'

.The Technica11 Specifications contained in Appendices A'and B, as g-revised-through Amendment No.139, are hereby-incorporated in the'.

L11 cense.1The-licensee:shall operate the facility in accordance with Lthe Technical Specifications.

3.

This, license amendment is effective 30 days after the' date of its issuance.

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.FOR~THE NUCLEAR REGULATORY COMMISSION 3 s L s e. C' W J

Robert A. Capra, Dire'ctor Project. Directorate I-1 Division of Reactor Projects - I/II t

Office of Nuclear Reactor Regulation-

Attachment:

Changes to the-Technical Specifications

- Date of' Issuance:- January 10, 1990

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'ATTACHNENT--T0 LICENSE AMENOMENT AMENDMENT NO.' 139 FACILITY OPERATING LICENSE NO.- DPR-53 DOCKET N0. 50-317 Revise Appendix A as.follows:

-Remove Pages Insert-Pages 3/4'6-11** -

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3/4 6-12**

3/4 6-13**

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3/4 6-15**

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0verleaf pages provided for continuity purposes only.

- Reissued pages from Amendment No.128, 6-I

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CONTAINMENT SYSTEMS 1

' SURVEff I ANCE REOUIREMEN~m (Continued)

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b.

At least once per refueling-interval, during shutdown, by:

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Verifying that'each automatic valve in the flow path actu-~

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. ates' to its correct position on Safety Injection Actuation test signal.-

1 2,'

Verifying' that' each spray pump starts automatically' on a Containment Spray Actuation test signal.

c,

. At least once per 5 years by performing.an air or smoke flow test through each spray header and' verifying 'each spray nozzle is unobstructed.

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CALVERT CLIFFS - UNIT I 3/4 6-11 Amendment No. 12'8' 139 i. '.

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CONTAINMENT SYSTEMS CONTAINMENT COOLING SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.2 Two independent groups of containment air recirculation and cooling units shall be OPERABLE with two units to each group.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a.

With one group of required containment air recirculation and cooling units inoperable and both containment spray systens OPERABLE, restore the inoperable group of air recirculation and cooling units to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With three required containment air recirculation and cooling units inoperable and both containment spray systems OPERABLE, restore at least one required air recirculation and cooling unit to OPERACLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Restore both above required groups of contain-ment air recirculation and cooling units to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c.

With one group of required containment air recirculation and cool-ing units inoperable and one containment spray system inoperable, restore the inoperable containment spray system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Restore the inoperable group of containment air recirculation and cooling units to OPERABLE status within 7 days of initial loss or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.6.2 2 Each containment air recirculation and cooling unit shall be demonstrated OPERABLE:

a.

At least once per 31 days on a STAGGERED TEST BASIS by:

1.

Starting each unit from the control room.

2.

Verifying that each unit operates for at least 15 minutes.

3.

Verifying a cooling water flow rate of 1 2000 gpm to each cooling unit when the full flow service water outlet valves are fully open.

b.

At least once per 18 months by verifying that each unit starts automatically on a Containment Spray Actuation test signal.

CAlVERT CLIFFS - UNIT 1 3/4 6-12 Amendment No. S7 139

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d CONTAINMENT SYSTEMS 3/4.6.3 IODINE REMOVAL' SYSTEM J.

' LIMITING CONDITION FOR' OPER ATION 3.6.3.1= 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 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months and in

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

SURVEILLANCE REOUIREMENTS O

'"4.6.3.1=

Each iodine filter _ train _ shall_ be demonstrated OPERABLE

a. '

'At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filter

' and charcoal n'dsorber train and verifying that the train operates 3

for at least 15 minutes.

l b.

At. least once per refueling interval 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 2 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 10E 2.

Verifying that the HEl'A filter banks remove t 99% of the DOP when they are tested in-place in accorGance with ANSI N510-1975 while operating the filter train at a flow rate of 20,000 cfm 10%.

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CALVERT CLIFFS - UNIT I 3/4 6-13 Amendment No. Wfil 139

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CONTAINMENT SYSTEMS i

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t SURVEILLANCE REQUIREMENTS (Continued) i 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 carbor, 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 t

canisters shall be prepared by emptying a representative sample from an adsorber test tray section, mixing-the-he adsorbent thoroughly, and obtaining samples at least two

- e inches in diaueter and with a length equal to the thickness of the bed. Successive samples will be removed from different test tray sections.

1 4.

Verifying a filter train flow rate of 20,000 cfm i10%

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 4

analysis of a carbon sample obtained from a test canister i

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demonstrates a removal efficiency of > 95, for radio-i active elemental iodine when the senTe is tested in accor-e j

dance with ANSI N510-1975 (130?C IN 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

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iodine when the samples are tested in accordance with ANSI N510-1975 (130'C, 95% R.H.) and the samples are n

i prepared by emptying a representative sample from an adsorber l

T 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.

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CALVERT CLIFFS - UNIT 1 3/4 6-14 Amendment No. 8'I 139

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CONTADHdENT SYSTT.MS SURVFft 1 ANCE REOUlurMEN11 (Continued)

Subsequent to reinstalling the adsorber tray used for obtaining the carbon sample, the filter train shall be dem-onstrated OPERABLE by also verifying that the charcoal adsorbers remove P. 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 i 10%

d.

At least once per refueling interval by:

1.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is < 6 inches W ter h

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

2.

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

9 CALVERT CLIFFS - UNIT I 3/4 6-l$

Amendment No. //, //,128 139 i

CONTAINMENT SYSTEMS Li SURVEILLANCE REQUIREMENTS (Continued) l i

After each complete or partial replacement of a HEPA filter i

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L bank by verifying that the HEPA filter banks remove 1 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 L

20,000 cfm i 10%,

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After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove 1

199% 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 i10%.

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 i

" Industrial Ventilation" and Section 8 of ANSI N510-1975, 1

1 CALVERT CLIFFS - UNIT 1 3/4 6-16 Amendment No 39' 139

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i CONTAINMENT SYSTEMS 3 /4.6.4 CONTAINMENT ISOLATION Y ALVES LIMITING CONDITION FOR OPERATION 3.6.4.1 The containment isolation valves specified in Table 3.6-1 shall be OPERABLE with isolation times as shown in Table 3.6-1.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With one or more of the isolation valve (s) specified in Table 3.6-1 inoperable, either:

a.-

Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or b'

Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one deactivated automatic valve secured in the isolation position, or c.

Isolate the affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one closed manual valve or blind flange; or d.

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

e.

The provisions of Specification 3.0.4 are not applicable provided that the affected penetration is isolated.

SURVEll.L ANCE REOUIREMENTS 4.6.4.1.1 The isolation valves specified in Table 3.6-1 shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair, or replacement work is performed on the valve or its associated uctuator, control, or power circuit by performance of a cycling test and verification of isolation time.

P CALVERT CLIFFS - UNIT 1 3/4 6-17 Amendment No. )W 139

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C,QN'TAINMENT SYSTEMS

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SURVEILLANCE REOUIREMENTS (Continued)

4.6.4.1.2 Each isolation valve specified in Table 3.6-1 shall be demonstrated

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OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per i

refueling interval by:

a.

Verifying that on each containment isolation Channel A or Channel B test signal, each required isolation valve actuates to its isolation posi-i tion.

b.

Verifying that on each Containment Radiation-High Test Channel A or r

Channel B test signal, both required containment purge valves actuate f

to their isolation position.

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c.

Verifying that on each Safety injection Actuation Channel A or Channel B test signal, each required isolation valve actuates to its isolation position.

I 4.6.4.1.3 The ' isolation time of each power operated or automatic valve of Ta-ble 3.6-1 shall be determined to be within its limit when tested pursuant to Techni-cal Specification 4.0.5.

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CALVERT CLIFFS - UNIT 1 3/4 6-18 Amendment No. M. ////4139

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CowrAINMENT SYSTEMS ELECTRIC HYDROGEN RECOMBINERE - W j

,' LIMITING CONDITION FOR OPERATION i

l 3.6.5.2 Two independent containment hydrogen recombiner systems shall be i

OPERABLE.

l) l APPLICABILITY: MODES 1 and 2.

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ACTION With on hydrogen recombiner system inoperable, restore the inoperable system to

(.f OPERABLE ttatus within 30. days or be in at least HOT STANDBY within the next 6 i

hours.

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SURVEILLANCE REOUIREMENTS 1

4.6.$.2 Each hydrogen recombiner system shall be demonstrated OPERABLE:

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At least once per 6 months by verifying during a recombiner system functional test that the minimum heater sheath temperature incraases' to a 7000F within 90 minutes and is maintained for at s

least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

b.'

At least once per refueling interval by:

1.

Performing a CHANNEL CAllBRATION of all recombiner instrumentation and control circuits.

L 2.

Verifying through a visual examination that there is no U

evidence of abnormal conditions within the recombiners (i.e., loose wiring or structural connections, deposits of foreign materials, etc.)

3.

Verifying during a recombiner system functional test that the heater sheath temperature increase to a 12000F within 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months and is maintained for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4 Verifying the integrity of the heater electrical circuits by performing a continuity and resistance to ground test following the above required functional test. The resis-tance to ground for any heater phase shall be a 10.000 ohms.

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.CALVERT CLIFFS - UNIT 1 3/4 6-27 Amendment No. /W8' 139 l

CONTAINMENT SYSTEMS 314.6.6 PENETRATION ROOM EXHAUST AIR FILTRATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.6.1 Two indeperdent containment penetration room exhaust air filter trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

With one containment penetration room exhaust air 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 k

4.6.6.1 Each containment penetration room exhaust air filter train shall be demonstrated OPERABLE:

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

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 comunicating 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 2000 cfm + 10%.

CALVERT CLIFFS - UNIT 1 3/4 6-28 Amendment No. 139

d' p PLANT SYSTEMS 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMIJATION Q3JTING CONDITION FOR OPERATION 3.7.2.1 The temperatures of both the primary and secondary coolants in the' steam generators shall be > BO'F when the pressure of either coolant l

in the steam generator is > 200 psig.

APPLICABILITY: At all times.

ACTION:

With the requirements of the above specification not satisfied:

a.

Reduce the steam generator pressure of the applicable side to 1 200 psig within 30 minutes, and b.

Perform an engineering evaluation to determine the effect of the overpressurization on the structural integrity of the steam generator. Determine that the steam generator remains acceptable. for continued operation prior to increasing its temperatures above 200'F.

SURVEILLANCE REQUIREMENTS 4.7.2.1 ~The pressure in each side of the steam generators shall be determined to be < 200 psig at least once per hour when the temperature of either the primary or secondary coolant < 80*F.

l CALVERT CLIFFS-UNIT 1 3/4 7-13 Amendment No. 82139

n l1 ANT SYSTEMS 3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3.1 At least two component cooling water loops shall be OPERABLE. At least one component cooling water heat exchanper shall be operating and the remaining component cooling water heat exchanger may be in standby.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With only one component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within 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_ hours.

SURVEILLANCE REOUIREMEN13 4.7.3.1 ' At least two component cooling water loops shall be demonstrated OPERABLE:

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

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

At least once per refueling interval during shutdown, by verifying that each automatic valve servicing _ safety related equipment actuates to its correct position on a Safety injection Actuation test signal.

CALVERT CLIFFS - UNIT 1 3/4 7-14 Amendment No.

,I2f 139

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k PLANT SYSTEMS 3/4.7.4 SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4.1 At least two andependent service water loops shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION With'only one service water loop OPERABLE, restore at least two loops to OPERABLE status within~ 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within 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 4.7.4.1 At least two service water loops shall be demonstrated OPERABLE n.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position, b.

At least once per refueling interval during shutdown, by verifying that l

each automatic valve servicing safety related equipment actuates to its correct position on Safety Injection Actuation and Containment Spray Actuation test signals.

CALVERT CLIFFS - UNIT I 3/4 7-15 Amendment No.

AE8 139

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.s-"i PLANT SYSTEMS i

1 3/4.7.5 SALTWATER SYSTEM r

- LIMITING CONDITION FOR' OPERATION l

3.7.5.1 At least two independent saltwater loops shall be OPERABLE.

-P APPLICABILITY:

MODES 1, 2, 3 and 4 i

ACTION With only one saltwater loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within 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 REOUTREMENTS 4.7.5.1 At least two saltwater loops shall be OPERABLE.

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At least once per 31 days be verifying that each valve (manual power j-a.-

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

b.

At least once per refueling interval during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety injection Actuation test signal.

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CALVERT CLIFFS - UNIT 1 3/4 7-16 Amendment No. k, llSS 139

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DE11AM FEAT

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5.4.2

-.Thetotalwaterandsteamvolumeofghereactorcoolantsystemis 10,614 460 cubic feet at a nominal T,yg of 532 F.

5.5 IETEOR0 LOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1, 5.6 FUEL STORARE CRITICALITY - SPENT FUEL 5.6.1 The spent fuel storage racks are e signed and shall be maintained with a minimum 10 3/32" x 10 3/32" ctnter to center distance between fuel.

assemblies placed in the storage racks to ensure a k gf of s 0.95 with the storage pool filled with unborated water. ThekerIfs0.95includesthe t

conservativeallowancesforuncertaintiesdescri$60inSection9.7.2ofthe FSAR. The maximum fuel enrichment to be stored in the fuel pool will be 5.0 3

-weight percent.-

CRITICALITY - NEW FUEL' 5.6.2 The new fuel storage racks are designed and shall be maintained with a nominal 18 inch center to center distance between new fuel assemblies such that k 5.0 weight ff will not exceed 0.95 when fuel having a maximum enrichment of percent U 235 is in place and vartous densities of unborated water are assumed including aqueous foam moderation and full flood conditions.

The k

of-5 0.95 includes the conservative allowance for uncertainties described fr 18 Section 9.7.2 of the FSAR.

DRAINAGE 5.6.3 The sps7,t fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 63 feet.

CAPACITY 1

5.6.4

.The fuel storage pool is designed and shall be maintained with a combined storage capacity, for both Units 1 and 2, limited to no more than 1830 fuel assemblies.

5.7 COMPONENT CYCLIC OR TRANSIENT LINITS 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.

1 CALVERT CLIFFS - UNIT 1 5-5 Amendment No. 27//#7//#3,

1. ,134, 136, 139

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l TABLE 5.7-1 l

9 COMPONENT CYCLIC OR TRANSIENT LIMITS E

l Component Cyclic or Transient Limit Design Cycle or Transient O

Reactor Coolant System 500 heatup and cooldown cycles 70*F to 532*F to 70'F U

g 400 reactor trip cycles 100% to 0% RATED THERMAL POWER Z

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10 Primary Hydrostatic Tests 3125 psia and 60'F > NOTT 320 Primary Leak Tests 2500 psia and 60*F > NDTT T

Steam Generator 10 Secondary Hydrostatic Tests 1250 psia Secondary Side and temperature > 100'F 320 Secondary Leak Tests 1000 psia Secondary Side With Primary - Secondary ap of-820 psi and shell side temperature between 100'F and 200'F E

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g UNITED STATES

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i NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20665 BALTIN0RE GAS.AND ELECTRIC COMPANY DOCKET NO. 50 318 o

CALVERT. CLIFFS NUCLEAR. POWER PLANT. UNIT 2 l

AMEN 0 MENT TO FACILITY OPERATING. LICENSE Amendment No.122 License No. DPR-69 1.

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

1 A.

The application for amendment by Baltimore Gas and Electric Company L

(the licenste) dated June 9, 1988, as supplemented on October 25, l

- November 17 and December 28, 1988, 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 1;

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L B.

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

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

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

and L

E.

The issuance of this amendment is in accordance with 10 CFR Part b

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

2.

Accordingly, the license is amended by changes to the Technical L

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:

b l

v.

2 (2) Technical Specifications l

The Technical Specifications contained in Appendices A and B as i.

revised through Amendment No.122, are hereby incorporated in the license. The licensee shall operate the facility in accordance with 3

L the Technical Specifications, t, -

3.

This license amendment is effective 30 days after the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION SMQ

- {W I

Robert A. Capra, Director

~

Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: January 10, 1990 L

L L

I i

i l

i

_~

)

ATTACHMENT TO LICENSE AMENDNENT Pg. l' of 2 AMENDMENT NO.122. FACILITY-0PERATING LICENSE NO. DPR-69 DOCKET H0. 50-318 i

Revise Appendix A as follows:

Remove.Pages insert Pages i

3/4 4-33**

3/4 4-34**

3/4 4-34 3/4 5-1**

3/4 5-1**

3/4 5-2**

-3/4 5-5**

3/4 5-5**

3/4 5-5A**-

3/4 5 Sa**

3/4 6-11**

3/4 6-12**

i 3/4 6-13**

3/4 6-13**

3/4 6-14**.

3/4 6-14**

3/4 6-15**

3/4 6-16**

3/4 6-17**

3/4 6 18**

3/4 6-18**

3/4 6-27**

t 3/4 6-28**

3/4 6-28**

s 3/4 7-13**

3/4 7-13**

3/4 7-14**

3/4 7-15**

3/4 7-16**

I 555 5-5 5-6*

5-6*

Overleaf pages provided for continuity purposes only.

Reissued pages from Amendment No. 110.

)

w

q<-#

I REACTOR COOLANT-SYSTEM REACTOR COOLANT SYSTEM VENTS

+

LIMITING CONDITION FOR OPERATION I

3.4.13 One reactor coolant system vent path consisting of two solenoid valves l

in series shall be OPERABLE and closed at each of the following locations:

a.

Reactor vessel' head b.

Pressurizer vapor space 3

APPLICABillTY:. MODES 1 and 2 ACTION:

a..

With the reactor. vessel head. vent path inoperable, meintain the inopecable vent path closed with power removed from the actuator of the solenoid _ valves in the inoperable vent path, and:

1.

If the pressurizer vapor space vent path is also inoperable, restore both inoperable vent paths to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , or

\\

r

2..

If the pressurizer vapor space vent path is OPERABLE, restore the inoperable reactor vessel head vent path to OPERABLE status within 30 days or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

b. ' With only the pressurizer vapor space vent path inoperable, maintain the iroperable vent path closed witti power removed from the valve actuator of the solenoid valves in the inoperable vent path, and:

-i 1.

Verify at least one PORV and its associated flow path is OPERABLE within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and restore the inoperable pressurizer vapor space vent path to OPERABLE status prior to entering MODE 2 following the next HOT SHUTDOWN of sufficient duration, or l

2.

Restore the inoperable pressurizer vapor space vent path to OPERABLE status within 30 days, or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

The provisions of Specification 3.0.4 are not applicable.

c.

SURVE:LLA. ICE REQUIREMENTS l

l l 4.4.13.1 Each reactor coolant system vent path shall be demonstrated OPERABLE j

by testing each valve in the vent path per Specification 4.0.5.

i 4

I CALVERT CLIFFS.- UNIT 2 3/4 4-33 Amendment No.Ap/ 122 i

+ -3 c.

~

g.

E

._W b

REACTOR COOLANT SYSTEM e

REACTOR COOLANT SYSTEM VENTS SURVEILLANCE REOUIREMENTS (Continued)

' 4.4.13.2 Each reactor coolant s) stem vent path shall be demonstrated OPERABLE at least once per refueling interval by:

l a.

Verifying all manual isolation valves in each vent path are locked in the open position, b.

Verifying flow through the reactor coolant system vent paths with the vent valves open.

9 CALVERT CLIFFS - UNIT 2 3/4 4-34 Amendment No. ///, ))9122 f

3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

SAFETY INJECTION TANKS a-LIMITING CONDITION FOR OPERATION 3.5.1 Each reactor coolant system safety injection tank shall be OPERABLE with:

a.

The isolation valve open, b.

A contained borated water volume of between 1113 and 1179 cubic feet of borated water (equivalent to tank levels of between 187 and 199 inches, respectively),

c.

A boron concentration of between 2300 and 2700 ppm, and l

d.

A nitrogen cover-pressure of between 200 and 250 psig.

APPLICABILITY: MODES 1, 2 and 3.*

ACTION:

a.

With one safety injection tank inoperable, except as a result of a closed isolation valve, restore the inoperable tank to OPERABLE status within one hour.or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , b.

With one safety injection tank inoperable due to the isolation

' valve being closed, either immediately open the isolation valve or be in HOT STANDBY within one hour and be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.5.1 Each safety injection tank shall be demonstrated OPERABLE:

a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by:

1.

Verifying the contained borated water volume and nitrogen cover-pressure in the tanks, and 2.

Verifying that each safety injection tank isolation valve is open.

With pressurizer pressure 1 1750 psia.

CALVERT CLIFFS - UNIT 1 Amendment No. $8,/ ' 139 CALVERT CLIFFS - UNIT 2 3/4 5-1 Amendment No. 31, 122

t a

h EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REOUIREMENT!i (Continu2d) s b.

At least once per 31 days by verifying the boron concentration of the safety injection tank solution.

At least once per 31 days when the RCS pressure is above 2000 psig, by c.

verifying that power to the isolation valve operator is removed by main-taining the feeder breaker open under administrative control, d.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to increasing the RCS pressure above 1750 psia by verifying, via local indication at the valve, that the tank isolation valve is open.

1 i

At least once per refueling interval by verifying that each safety injection l_'

e.

tank isolation valve opens automatically under each of the following condi-tions:

1.

When the RCS pressure exceeds 300 psia, and 2.

Upon receipt of a safety injection test signal.

f.

Within one hour prior to each increase in solution volume of a 1% of I

normal tank volume by verifying the boron concentration at the operating high pressure safety injection pump discharge is between 2300 and 2700 i

ppm.

4 Amendment No./ Amendm

,/WB 139 CALVERT CLIFFS - UNIT I 3/4 5-2

/MO 122 CALVERT CLIFFS - UNIT 2

p 4.

q e

s EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)

+

e.

At least once per refueling interval by:

l l.

Verifying automatic isolation and interlock action of the shutdown cooling system from the Reactor Coolant System when the Reactor Coolant System pressure is above 300 m

psia.

I' 2.

A visual inspection of the containment sump and verifying i'

that the subsystem suction inlets are not restricted by L-debris and that the sump components (trash racks, 6

screens, etc.) show no evidence of structural distress or corrosion.

L(

3.

Verifying that a minimum total of 100 cubic feet of solid I.'

granular trisodium phosphate dodecahydrate (TSP) is con-tained within the TSP storage baskets.

i.

4.-

-Verifying that when a representative sample of 4.0 0.1 grams of TSP from a TSP storage basket is submerged, without agitation, in 3.5 0.1 liters of 77 100 F borated water from the RWT, the pH of the mixed solution is raised

~

to a 6 within '4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , f.

At least once per refueling interval, during shutdown, by:

l_

1.

Verifying that each automatic valve in the flow path actu-ates to its correct position on a Safety injecti'on Actuation test signal.

2.

Verifying that each of the following pumps start automati-cally upon receipt of a Safety injection Actuation Test Signal:

a.

High-Pressure Safety injection pump.

It b.

Low-Pressure Safety injection pump.

1 l-l t

CALVERT CLIFFS - UNIT 2 3/4 5-5 Amendment No. [jif, //, g. If 6122 L

~~"r f

f EMERGENCY CORE COOLING SYSTEMS o

i SURVE!LLANCE REQUIREMENTS (Continued)

I g.

By perfonning a flow balance test during shutdown following i

completion of HPSI system modifications that alter system flow characteristics and verifying the following flow rates for a

[

single-HPSI pump system *:

l.

The sum of the three lowest flow legs shall be greater than 470** gpm.

h.

By verifying that the HPSI pumps develop a total head of 2900 ft i

on recirculation flow to the refueling water tank when tested pursuant to Specification 4.0.5.

f:

i f

I l

A HPSI pump system is a HPSI pump and one of two safety injection headers.

- These limits contain allowances for instrument error, drift or fluctuation.

CALVERT CLIFFS - UNIT 2 3/4 5-Sa Amendment No.16,E6,89, 97 122

4 CONTAINMENT SYSTEMS

' SURVEft I ANCE REOUIREMENTS (Continued) b.

At least once per refueling interval, during shutdown, by:

l' Verifying that each automatic valve in the flow path actu-ates to its correct position on Safety Injection Actuation test signal.

2.

Verifying that each spray pump starts automatically on a Containment Spray Actuation test signal.

c.

At least once per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.

1 CALVERT CLIFFS - UNIT 2 3/4 6-!!

Amendment No MD 122

=

s' CONTAINMENT SYSTEMS CONTAINMENT COOLING SYSTEM i

LIMITING CONDITION FOR OPERATION 3.6.2.2 Two independent groups of containment air recirculation and cooling i

units shall.be OPERABLE with two units to each group.

i APPLICABILITY:. MODES 1, 2 and 3.

a R

ACTION:

(

)

L a.

With one group of required containment air recirculation and cooling units inoperable and both containment spray systems OPERABLE, restore the inoperable group of air recirculation and

-{

cooling units to OPERABLE status within 7 days or be in at least L

HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

i b.

With three required contai0 ment air recirculation and cooling I

units inoperable and both containment spray systems OPERABLE, L

restore at least one required air recirculation and cooling unit.

to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Restore both above required groups of contain-ment air recirculation and cooling units to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , c.

With one group of required containment air recirculation and cool-units ~ inoperable and one containment spray system inoperable, restore.the inoperable containment spray system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Restore the inoperable group of containment air recirculation and cooling units to OPERABLE status within 7 days of initial loss or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4 SURVEILLANCE REQUIREMENTS 4.6.2.2 Each containment air recirculation and cooling unit shall be demonstrated OPERABLE:

a.

At least once per 31 days on a STAGGERED TEST BASIS by:

1.

Starting each unit from the control room.

2.

Verifying that each unit operates for at least 15 minutes.

3.

Verifying a cooling water flow rate of > 2000 gpm to each cooling unit when the full flow service water outlet valves are fully open, b.

At least once per 18 months by verifying that each unit starts automatically on a Containment Spray Actuation test signal.

CALVERT CLIFFS - UNIT 2 3/4 6-12 Amendment No. 74 122

9

^

i

!a CONTAINMENT SYSTEMS 3/4.6.3 IODINE REMOVAL SYSTEM LIMITING 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 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 REOUIREMENE 4.6.3.1 Each lodine filter. train shall be demonstrated OPERABLE:

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

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

b.

At least once per refueling interval or (1) after any structural l

maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical rplease in any ventilation zone communicating with the system by:

1.

Verifying that the charcoal adsorbers remove t 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 i 10%

2.

Verifying that the llEPA filter banks remove 1 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 1 10%

i CALVERT CLIFFS - UNIT 2 3/4 6-13 Amendment No. II6 122

+'

CONTAINMENT SYSTEMS j '.

SURVEILLANCE REQUIREMENTS (Continued) 3.

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

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 l

. sample is tested in accordance with ANSI N510-1975 (130*C, n

95% R.H.).

The carbon samples not obtained from test

[

canisters shall be prepared by emptying a representative L

sample from an adsorber test tray section, mixing the i

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 L

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.

p

'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 L'

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 r

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 i

ANSI N510-1975 -(130'C, 95% R.H.) and the samples are prepared by emptying a representative sample from an adsorber I

test-tray section, mixing the adsorbent thoroughly, and l

obtaining samples at least two inches in diameter and with L

a length equal to the thickness of the bed.

Successive samples L

will be removed from different test tray sections.

CALVERT CLIFFS - UNIT 2 3/4 6-14 Amendment No. 6/6 122

=

y 4

. [ -

CONTAINMENT SYSTEMS

, SURVEILLANCEREOUIREMENTS (Continued)

I i

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 t. 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 i 10%

d.

At least once per refueling interval by:

.l 1.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is < 6 inches Water Gauge while oper-o ating 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.

i

't

'\\

f I'

6 l

O 1

l l

1.

,f,//p/122 CALVERT CLirFS - UNIT 2 3/4 6-15 Amendment No.

F CONTAINMENT SYSTEMS

('

SURVEILLANCE REQUIREMENTS (Continued)

L e.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove > 99% of I

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 + 10%.

i i-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 3

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

+ 10%.

g.

After maintenance affecting 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 provisions of Section 9 of

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

5 F

P CALVERT CLIFFS - UNIT 2 3/4 6-16 Amendment No. If 122

a x,, -

[ 1-ji /

,[. b g,1 ' l ' '

j,

-s

', ; 2 s *

,f 3-} 4:.,

4

~;: ~,

~ CONTAINMENT SYSTEMS ?

9..

i r

j

'+..

o 'm 3/4.6.4 -: CONTAINMENT ISOL ATION VALVES.

1

.G<

./ LIMITING ' CONDITION FOR OPER ATION d

eW k_

. 3.6.4.11 The containment isolation valves specified in Table 3.6-1 shall be l

e e.

~ OPERABLE.with isolation times as'shown in Table 3.6-1.

g

/M APPLICABILITY:

- MODES 1.- 2, ' 3, and 4.

ACTIONi f

]

r i

d4 With one or.'more.of the isolation' valve (s) specified in Table 3.61 inoperable,-

+'

L either:'

I M

s,,

7 a..

Restore-the inoperable valve (s)'ts OPERABLE status ~ within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or I

r n 4

b.-

.lsolate eachinffected: penetration within 4= hours by use of at-least one-

,1 deactivated automatic' valve secured in the isolation position, or

,~S; c.

Isolate the.affected. penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use' of at least one

~"

closed ~ manual valve or blind, flange;: or.

j

d.

bel 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 -3G hours,

- The provisions of. Specification 3'0.4 are not applicable provided that the-

[

c.

affected penetration is isolated.

.a

[

. rW

.l SURVEILL'ANCE R'EOUIREMENTE 24.6.4.1.1 The isolation-valves specified in Table 3.6-1 shall. be demonstrated LOPERABLE prior' to returning: the valve to service after maintenance, repair, or-

- replacement work is performed on the valve-or its associated actuator, control, or

,j power circuit by performance of a cycling ' test and verification of isolation time.

L.

y

,2 15W 9

t

. Is; L

{lt i

1

+

m t-m s

CALVERT CLIFFS - UNIT 2 3/4 6-17 Amendment No. /1% 122 j

'b

' ~

- w

i

'A,

s

f+i

1 CONTAINMENT' SYSTEMS -

- SURVEILL ANCE ' REOUIREMENTS (Continued)

.. 4.6.4.1.2 ~

Each isolation ~ valve specified in Table 3.6-1 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per refueling-interval by; a.'

' Verifying that on each containment isolation Channel A or Channel B test signal, each required ' isolation valve actuates to' its isolation' posi-tion.

b.

Veilfying that on each Containment Radiation-High Test Channel A or-Channel B~ test signal, both requirea containment purge valves actuate'-

to their= isolation position,

. Verifying that on each Safety injection Actuation Channel A or Channel c.

B test signal,' each required-isolation valve actuates to its isolation

. position.-

4.6.4.1.3 The isolation time of each power opertted or automatic valve of Ta-c

'?

-ble 3.6-1 shall be determined to be within its limit when tested pursuant to Techni--

g cal Specification 4.0.5.

i}-

s..

t.

1 I

CALVERT CLIFFS - UNIT 2 3/4 6-18 Amendment No. [, //. [/YW122 DLL._---_-__--____-_-_-_---

gi?

~

f, [(n 4

n

%. g 'N; s

n

o. l y

5

.u..

N CONTAINMENT SYSTEMS '

((;

s s

/

- ELECTRIC HYDROGEN RECOMBINERE '- W.

4 y

l.*

LIMITING CONDITION FOR OPER ATION

\\

$^

~

[

3.6.5.2 ' Two independent containment hydrogen recombiner systems shall be OPERABLE.

u

. ~

APPLICABILITY:1. MODES l' and 2.

ACTION:

.s l-3, With on hydrogen.recombiner system inoperable, restore the~ inoperable system to

OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6

[W hours.

SURVEILLANCE REOUIREMENTS 1,

11

4.6.5.2. Each hydrogen recombiner system shall be ' demonstrated OPERABLE

l At least once per 6 months by verifying during a recombiner -

o a.

. system functional test that the minimum heater sheath. temperature m

. increases to z 7000F within 90 minutes and is maintained for at least' 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

y bi L At least once per refueling' interval' by:

1:'

.g

,4 1.

! Performing a CHANNEL CALIBRATION of all recombiner instrumentation and control circuits.

. 2.

. Verifying. through a visual examination that there is no j evidence of abnormal conditions within the recombiners

. (1.e., loose wiring or~ structural connections, ' deposits of

'l foreign materials, etc.)

3.

Verifying during a recombiner system functional test that

.the ' heater. sheath temperature increase to a 12000F within 5

- hours and is maintained for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.

Verifying the integrity of the heater electrical circuits by performing a continuity and resistance to ground test following the above required functional test. The resis-sc

. tance to ground for any heater phase shall be z 10,000 ohms.

l l

CALVERT CLIFFS - UNIT 2 3/4 6-27 Amendment No.

(if122

A 9

CONTAINMENT SYSTEMS 3/4.6.6 PENETRATION ROOM EXHAUST AIR FILTRATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.6.1 Two independent containment penetration room exhaust air filter trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

With one containment penetration room exhaust air 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 4.6.6.1 Each containment penetration room exhaust air filter train shall be demonstrated OPERABLE:

a.

At least once per 31 days on STAGGERED TEST BASIS by initiating, 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) af ter 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 cf 2000 cfm + 10%.

CALVERT CLIFFS - UNIT 2 3/a 6-28

]

l;9.

1,.?

s-

-.r.

9., 0..

4 *-

iPLdNTSYSTEMS m

3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION LIMITING CONDITION FOR OPERATION r

3.7.2.1 The temperatures of both the primary and secondary coolants in i

-the steam generators shall be > 90'F when the pressure of either coolant

]

in the steam generator is > 200 psig.

APPLICABILITY:- At all-times.

ACTION:

With the requirements of the above specification not satisfied:

'a.

Reduce the steam generator pressure of the applicable side to

< 200.psig.within 30 minutes, and

~

b.

-Perform an engineering evaluation to determine the effect of 4

the overpressurization on the structural integrity of the Steam generator.

Determine that the steam generator remains-I acceptable for continued' operation prior to increasin'g its temperatures above 200'F.

I SURVEILLANCE REQUIREMENTS 4.7.2.1 The pressure in each side of the steam generators shall be j

determined to be < 200 psig at least once per hour when the temperature of either the primary or secondary coolant < 90*F.

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J CALVERT CLIFFS-UNIT 2 3/4 7-13 Amendment No. /// 122

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PLANT SYSTEMS i'

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3/413 COMPONENT COOLING WATER SYSTEM

1.IMITING CONDITION ' FOR OPER ATION p'

3.7.3.1-At. least two component cooling ' water loops shall be OPERABLE. At least one: component: cooling water heat exchanger shall be operating and the remaining component cooling water heat exchanger may be in standby.

APPLICABILITY:

MODES 1, 2, 3.. and 4.

. ACTION:

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. With' only one component cooling water loop OPERABLE, restore at least.- two: loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next'6 7

hours' and'in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , 1

b SURVEILliANCE REOUIREMENE

~4.7.3.1 ' At least two component cooling water loops shall be demonstrated OPERABLE:

At least once perL 31 days by verifying that each ' valve (manual, power a.

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

b.

~At least. once per refueling interval during shutdown, by verifying that l

l cach' automatic valve servicing safety related equipment actuates to its

-correct position on.a Safety Injection Actuation test signal.

0 9

CALVERT CLIFFS - UNIT 2 3/4 7-14 Amendment No.

M9 122

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PLANT SYSTEMS 3/4.7I4 SERVICE WATER SYSTEM f LIMITING CONDITION FOR OPERATION -

3.7.4.1 At least' two independent service water loops shall' be OPERABLE.

' APPLICABILITY:

MODES 1,' 2, 3' and 4

+

R ACTION:-

' With only one service water loop OPERABLE, restore at least two loops to OPERABLE

- status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be' in at least-HOT STANDBY.within 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 REOUIREMEN13 4.7.4.1 ' At least two service water loops shall~ be demonstrated OPERABLE

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. At'least once per 31 days by verifying that each valve (manual, power '-

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operated or-automatic) in the flow path that is not locked, sealed, or '

otherwise secured in position, is-in its correct position, b.

At least once per refueling interval during shutdown, by verifying-that l

each automatic valve servicing safety' related equipment actuates to its correct position'on Safety Injection Actuation and Containment Spray g

l Actuation test signals.

J CALVERT CLIFFS - UNIT 2 3/4 7-15 Amendment No.f,440 122 l

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PLANT SYSTEMS 3/4.7.5 SALTWATER SYSTEM 4 ;

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' LIMITING CONDITION FOR OPERATION L 3.7.5.I' At least two. independent saltwater loops shall be OPERABLE.

--M APPLICABILITY:

MODES 1, 2, 3 and 4

ACTION:

With only one saltwater loop OPERABLE, restore at least two loops to OPERABLE

status: within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or ~ be 'in at.least-HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and x.

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

. SURVEILLANCE REOUIREMEN13 v

. 4.7.5.I' ' At least two saltwater loops shall.be OPERABLE.

3 At =least once per 31 days be. verifying that each valve (manual power

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operated or automatic) in the flow ~ path that is not locked, sealed, or otherwise secured in p'osition, is in its correct position.

b.

At least once-per refueling interval during shutdown, by' verifying that.

'each automatic valve servicing safety related equipment actuates to its-correct: position on a Safety Injection Actuation test signal.

CALVERT CLIFFS - UNIT 2 3/4 7-16 Amendment No.[, II0122

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j DESIGN FEATURES 40 LUNE 5.4.2 The total. water and steam volume of the reactor coolant system is.

. 10,614 i 460 cubic feet at a nominal T,yg of 532 F' 5.5 METEOROLOGICAL TOWER LOCATION ~

5. 5. l ~

The meteorological: tower shall be located as shown on Figure 5.1-1.

j 5.6-FUEL 1 STORAGE.

n CRITICALITY --SPENT FUEL:

5.6.1 The spent fuel storage racks are designed and shall be maintained-with a minimum 10 3/32" x 10 3/32" center-to-center distance between fuel

- assemblies placed in the storage racks to ensure a k rf of 10.95 with the-

storage pool filled with-unborated water.

The k 8f10.95includesthe n

ff conservative allowances for uncertainties descriIed in'Section 9.7.2 of the FSAR. The maximum fuel enrichment to be stored in the fuel pool will be. 5.0 l-

' weight percent.

CRITICALITY - NEW FUEL J

D 5.6.2 LThe new fuel storage racks.are designed and.shall be maintained.

with a nominal 18. inch center-to center distance between new fuel.. assemblies

such that-k ff will not exceed 0.95 when fuel having a maximum enrichment-of.

5.0 weight, percent U-235 is in place and various densities of unborated. water.

-1 are assumed including. aqueous-foam moderation and full flood conditions. The k,gg.of 1 0.95 includes-the conservative allowance for uncertainties described in Section 9.'7.2 of ~ the FSAR.

lj DRAINAGE j

l 5.6.3 The spent fuel storage. pool is designed and shall be maintained to y

prevent Inadvertent draining of the pool below elevation 63 feet.

CAPACITY 5.6.4 The fuel storage pool is designed and shall be maintained with a o

combined storage capacity, for both Units 1 and 2, limited to no more than

~'1830 fuel assemblies.

l 5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.

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CALVERT CLIFFS - UNIT 2 5-5 Amendment No. J2//39//M,

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a-TABLE 5.'7-1

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9 COMPONENT CYCLIC OR' TRANSIENT LIMITS r-9

- Design Cycle or Transient:

Component Cyclic or-Transient Limit PM Reactor Coolant System 500 heatup and cooldown cycles:

70 F to 532*F to 70*F G

b

~ 400 reactor trip cycles 100% to'0% RATED THERMAL-POWER.

5

-4 10 Primary ifydrostatic Tests

~ 3125 psia and 60*F > NDTT.

320 Primary Leak Tests 32500 psia and 60*F--> NOTT T

1250 psia Secondary Side and ' '

l Steam Generator

10. Secondary-Ilydrostatic Tests temperature _ > 100*F-l

' 320 Secondary Leak Tests 1000 psia Secondary Side With Primary - Secondary 'ap of -

820 psi and shell side temperature between 100 F y

and 200*F to E

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