Text

Amends 59 & 41 to Licenses DPR-53 & DPR-69 Respectively, Implementing Secondary Water Chemistry Monitoring Program to Inhibit Steam Generator Tube Degradation.Program Includes Sampling Schedule & Point Identification
	ML20032D426
Person / Time
Site:	Calvert Cliffs
Issue date:	11/04/1981
From:	Clark R; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20032D427	List: ML20032D426; ML20032D432; ML20032D433;
References
	NUDOCS 8111160339
	Download: ML20032D426 (20)
	v • d • e

--

o ne UNITED STATES' og NUCLEAR REGULATORY COMMISSION

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WASHINGTON, D. C. 20566

$ { C T,/

BALTIW)RE GAS AND ELECTRIC COMPANY 00CKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO.1 AMENDMENT T0. FACILITY OPERATING LICENSE Amendment No. 59 i

License No. DPR-53

~ 1.

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

A.

The applications for enendment by Baltimore Gas & Elect'ic Company-(the licensee) dated January 29 and July 30, 1981,

~

comply with the standards and req'uirements 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;-

4 B. -The facility will operate in conformity with th'e applications, the provisions of the Act,- and the rules and regulations of

' the Commission; y

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 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 appifcable requirements have been satisfied.

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8111160339 811104 PDR ADOCK 05000317 P

PDR

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2.

Accordingly, Facility License No. ~DPR-53 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, by amending paragraph 2.C.(2), and by adding' paragraph 2.C.(5) to read as follows:

(2) Technical Specifications-The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 59, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

(5) Secondary Water Chemistry Monitoring Program

^

The licensee shall implem.ent a secondary water chemistry monitoring program to inhibit steam generator tube degrad-ation. This program shall-include:

a.

Identification of a sampling schedule for the critical-parameters and control points for these parameters.

y b.

Identification of the procedures used to quantify para-[

meters that are critical to control points.

c.

Identification of process sampling points.

d.

Procedure for recording and management of data.

e.

Procedures defining corrective actions for off control point chemistry conditions; and f.

~A procedure identifying the authority responsible for the interpret'ation of the data and _the sequence and timing of administrative events required to initiate corrective action.

3.

This license amendment is effective 3s of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Robert A. Clark, Chief

(

Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: November 4, 1981

ATTACHMENT TO LICENSE AMENDMENT NO. 59 FACILITY OPERATING LICENSE NO. DPR-53 DOCKET NO. 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 tc maintain document,

completeness.

Pages 3/4 7-10 3/4 7-11 3/4 7-12 4

3/4 7-17 3/4 7-31 3/4 9-8 3/4 10-5 B 3/4 7-2 e

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PLANT SYSTEMS

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MAIN STdDM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION

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3.7.1.5 -Each main steam line isolation valve shall be OPERABLE.

1, APPLICABILITY: MODES 1, 2 and 3.

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ACTION:

MODE 1 With one main steam line isolation valve inoperable, POWER OPERATION may continue provided the inoperable vab.e is either restored to OPERABLE status or closed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; otherwise, be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

MODES 2

, With one main steam line isolation valve inoperable, sub-and 3 sequent operation in MODES 1, 2 or 3 may proceed provided:

a.

The isolation valve is maintained closed.

b.

The. provisions of Specification 3.0.4 are not ar-licable.

Otherwise, be in HOT SHUTDOWN within tae next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.7.1.5 Each main steam line isolation valve shall be demonstrated OPERABLE by verifying full closure within 3.6 seconds when tested pursuant to Specif' cation 4.0.5.

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PLANT SYSTEMS N

3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM _

LIMITING CONDITION FOR OPERATION

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

a.

Two filter trains, b.

Two air conditioning ' units, c.

Two. isolation valves in each control room outside air intake

duct, d.

Two isolation valves in the common.cxhaust to atmosphere duct.

l and One isolation val've in the toilet area exhaust duct.,

e.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a.

With one filter train inoperable, restore the inoperable train to OPERABLE status within 7.d ys or be in at least HOT STANDBY. within 4

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 uait to GPERABLE 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 .

c.

With one isolation valve per control room outside air intake duct inoperable, operation may continue proviat] the other isolation valve in the same duct is maintained closed; otherwise, be in at least H0T STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the folicwing 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-l-

operable, restore the inoperable valve to OPERABLE status within 7 days or be in' at least HOT STANDBY within the nex' 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 .

'~

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e: Rith the toilet ' area-exhaust' duct isol'ation' valve inoperable,

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restore the inoperable valve to OPERABLE status witnin 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 1 3/4 7-17 Amendment No. 59

1 PLANT SYSTEMS _

^

N SURVEILLANCE REQUIREMENTS 4

e 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 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 connunicating with the system by:

1.

Verifying that the charcoal adsorbers remove > 99% of a halogenated hydrocarbon refrigerant test gas when they 9

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 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 adsorbers demonstrater a removal efficiency of > 90% for radioactive methyl iodide when the sample-is tested in accordance with AN!' N510-1975. (130 C, 95%

R.H.).

The carbon tamples not obtained from test canisters shall be prepared by either:

a)

Emptying one entire bec from a removed at:orber tray, mixing the adsorbent thoroughly, a'. obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed, or Emptv'ng a longitudinal sample from an adsorber b) tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a 4

length equal to the thickness of the bed, i

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TABLE 3.7-4 e

SAFETY RELATED HYDRAULIC SNUBBERS

PM SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT h

NO.

ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **

TO REMOVE.

g (A or I)

(Yes or No)

[

1-36-1 EUCTION #11 AUX. FEED PUMP 12' A

No No

?

l-36-1A SUCTION #11 AUX. FEED PUMP 12' A

No No -

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1-38-4 PRESSURIZER SAMPLE LINES 38' I

Yes No 1-38-5 PRESSilRIZER SAMPLE LINES 24' I

Yes No 1-38-6 PRESSURIZER SAM >LE LINES 37' I

Yes No g

h 1-24-1 DIESEL GENERATOR #12 EXHAUST 92' A

No No 8"

l-24-2 DIESEL GENERATOR #11 EXHAUST 92' A

No No 5

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SAFETY RELATED HYDRAULIC SNUBBERS

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. HIGH RADIATION ESPECIALL DIFFICULT-l 6

NO.

ON, LOCATIO_N AND ELEVATION TNACCESSIBLE Z0P'E**

TO REPOVE 5

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(A or I)

(Yes or No)-

-(Yes or No) 1 H

j l-24-3 EMERGENCYDIESEi.#12 EXHAUST 61' A

No

'No

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l-24-3A EMERGENCY DIESEL #12 EXHAUST.61' A

No No-j e

1-24-4 EMERGENCY DIESEL #11 EXHAUST 61' A'

No No I

l-24-4A EMERGENCY DIESEL #11 EXHAUST 61' A

No No j

1-24-5 DIESEL GENERATOR #21 EXHAUST 92' A

No No g

1-24-6 DIESEL GENERATOR #21 EXHAUST 62' A

No-No

?

l-24-6A DIESEL GENERATOR #21 EXHAUST 62' A'

No No M

l l-41-1

', SUCTION #13 CHARGING PLHP -10' A

No No 1

1-41-2 AUX. SPRAY 65' i

Yes No

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l-41-3 AUX. SPRAY 65' I

Yes No.

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4 REFUEL {NG OPERATIONS CRANE TRAVEL - SPENT FUEL STORAGE P0OL BUILDING LIMITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 1600 pounds shall be prohibited from travel over fuel assemblies in the storage pool, APPLICABILITY: With fuel assemblies in the storage pool.

ACTION:

With the requirements of the above specification not satisfied, place the crane loat' in a safe condition.,The provisions of Specification 3.0.3 are nc + applicable.

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SURVEILLANCE REQUIREMENTS 4.9.7 The weight of each load, other than a fuel assembly and CEA, shall be verified to be 1 1600 pounds prior to moving it over fuel assemblies.

i CALVERT CLIFFS - UNIT 1 3/4 9-7 4

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REFUEll*C OPERATIONS SHUTDOWN COOLING AND COOLANT CIRCULATION LIMITING CONDITION FOR OPERATION 3.9.3.1 At least one shutdown coo"'ng loop shall be in operation;*

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APPLICABILITY: MODE. 6 at all reactor water levels.

ACTION:

a. -With less than one shutdown ' cooling loop in operation *,. suspend l

)

all operations involving an increase in the reactor decay

heat lead or a reduction in baron concentration of the Reactor Coolant System and, specifically, the charging pumps shall be de-energized and the charging flow paths shall be closed. Close all containment penetrations providing direct access. from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

The shutdown cooling pumps may be de-energized during the time intervals required for. local leak rate testing of containment g

penetration number 41 pursuant to the requirements of Specifica-tion 4.6.1.2.d and/or to permit maintenance on valves: located in the common shutdown cooling suction line, provided (1) rgt operations are permitted which could cause dilution of the reactor coolant system, boron concentration and, specifically, the charging pumps shall be de-energized and the charging flow paths shall be closed (2) all CORE ALTERATIONS are suspended, (3) all containment penetrations providing direct access from the containment atmosphe e to the outside atmosphere are main-tained closed, and (4) the kater level above the top of the irradiated fuel is greater than 23-feet, b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE091REMENTS 4.9.8.1 A shutdown cooling loop shall be determined to be in operation and circulating reactor coolant at a flow rate of > 3000 gpm** at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

i

The s'hutdow'n coolin'g ioop may be removed from operation for,up to I hour per

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4 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.

- > 1500 gpm when the Reector Coolant System is drained to a level below the midplane of the hot leg.

l CALVERT CLIFFS - UNIT 1 3/4 9-8 Amendment No. 75, 55, 59

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j SPECIAL TEST EXCEPTIONS

_ COOLANT CIRCULATION LIMITING CONDITION FOR OPERATION 3.10.5 The reactor coolant circulation requirements of Specification 3.4.1 may be suspended and all reactor coolant pumps and shutdown cooling pumps may be de-energized during the. time intervals required 1) for local leak rate testing of containmen: penetration number 41 pursuant to the requirements of Specifica-tion 4.6.1.2.d and 2) to permit maintenance on val'ves located in the common shotdown cooling suction line or on *,he shutdown cooling flow control valve i

(CV-306) provided:

No operations are permitted which could cause dilution of

a..the. reactor coolant system boron concentration, and specifically, the charging pumps shall. be de-energized and the charging flow paths shall be closed, B

b.

The. xenon reactivity is l O.1". ok/k and is approaching stability.

4

-and-The SHUTDOWN MARGIN requirement of Specification 3.1.1.2 is 9

c.

verified'at'least once per 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months when no shutdown cooling or i

reactor coolar aumps are it -peration.

1 l

APPLICABILITY: MODES 4 and 5.-

ACTION:

)

With' the requirements of the above specification not satisfied, suspend all operations involving local 1 " k rate testing of containment pene*. ration number 41, maintenance on vt., as located in the common shutdown cooling suction line, and maintenance or valve CV-306.

SURVEILL*NCE P.EODIREf1ENTS i

4.10.5.1 The charging pumps shall be verified de= energized and the charging flow paths shall be verified closed at least once per hour.

4

4. l'0. 5. 2 The xeon react'ivity shall be determined to be 1 0.1% Ak/k and approaching stability within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months prior to suspending reactor coolant circulation.

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CALVERT CLIFFS - UNIT 1 3/4'10-5 Amendment No. 59 i

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3/4.7 PLANT SYSTEMS j

BASES 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 SAFETY VALVES The OPERABILITY of the main steam line code safety valves ensures that -he secondary system pressure will be limited to within its design pressure of 1000 psig during the most severe anticipated system opera-tional transient.

The maximum relieving capacity is associated with a turbine trip ~from 100%' RATED THERMAL POWER coincident with an assumed loss of condenser heat sink (i.e., no steam bypass to the condenser).

The specified valve lift settings and relieving caoacities are in accordance with the requirements of Section III of the ASME Boiler and Pressure Code, 1971 Edition.

The total relieving capacity for all valves on all of the steam lines is 12.18 x 1C lbs/hr which is 108 percent of the total ' secondary steam flow of 11.23 x 106 lbs/hr at 100% RATED THERMAL POWER. A minimum of 2 OPERA 2i.E safety valves per steam generator ensures that sufficient relieving capacity is available for removing 4

decay heat.

STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the iimitations o'f4 he ACTION requirements on the basis of the reduction in secondcry system steam flow and THERMAL POWER required by the reduced reactor trip settings of the Power Level-High channels.

The reactor trip setpoint reductions are derived on the following bases:

For two loop operation 3p, (X) - (Y)(V) x 106.5 Fo single loop operati m (two reactor coolant pumps operating in the sar loop)

SP = IX) ~ (Y)(U) x 46.8 X

where:

SP reduced reactor trip setpoint in percent of RATED

=

THERMAL POWER c

V maximum number of inoperable safety valves per steam

=

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BASES I

U-maximum number of inoperable safety valves per

=

operating steam line 106.5 =

Power Level-High Trip Setpoint for two loop operation t

46.d =

Power Level-High Trip Setpoint for single loop operation with two reactor coolant pumps operating in the same loop Total relieving capacity of all safety valves per X

=

steam line in.lbs/ hour Maximun relieving capacity of any one safety valve Y

=

1 in lbs/ hour

^

3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM The OPERABILITY of the auxiliary feedwater system ensures ' hat the t

Reactor Coolant System can be cooled down to less than 300*F from no mal operating conditions in the event of a total loss of offsite power.

Each steam driven euxiliary feedwater pump is capable of delivering a total feedwater flow of 700 gpm at a Total Dynamic Head of 2490 ft to the entrance of the steam generators. A capacity of 450 gpm, however, is sufficient to ensure that adequate feeowater flow is available to remove decay heat and reduce the.Reacter Coolant System temperature to less than 300 F when tne shutdown cooling systen may be placed into operation.

3/41.1.3 CONDFJyJE STORAGE TANK g

i The OPERACI'_ITY of the condenate storage tank with the minimem

" water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months with steam discharge to atmos-phere with concurrent with total loss of offsite power.

The contained water volume limit includes an allowance for water not usable because of tank, discharge line lpcation or other physica.1 characteristics.

3/4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant off-sits radiation dose will be limited to a small fraction CALVERT CLIFFS-UNIT 1 B 3/4 7-2 Amendment No. 59

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,0, UNITED STATES NUCLEAR REGULATORY COMMISSION

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BALTIMORE GAS AND ELECTRIC COMPAN,Y, 00CKE's NO. 50-318 CALVERT CLIFFS NUCLEAR F0WER PLANT UNIT NO. 2 AMENDMEN't TO FACILITY OPERATING LICENSE Amendment No. 41 License No. DPR-69 1.

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

The applications for amendment by Baltimore Gas & Electric A.

Company (the licensee) dated January 29 and July 30, 1981, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulttions set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the applications, the provisiont of the Act, ahd the rv'es and regulations of the Co, mission, There is reasonable assurance (1) that the activities m.

auth;rized by this anendment 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; 0.

The issuance of this anendment will not be inimical to the common d'efense and security or to the he:lth 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.

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2.

Accordingly, Facility License No. DPR-69 is amended by changes i'

to the Technical Specifications as indicated in the attachment to this license amendment, by amending _ paragraph 2.C.(2), and by adding paragraph 2.C.(7) to read as follows:

(2) Technical Specifications The Technical Specifications

tained in Appendices A and B, as revised through A.:.adment No. 41, are hereby incorporate:1 in the license. The licereee shall operate the facility in accordance with the Technical Specifications.

(5) Secondary Water Chemistry Mc.11toring Program

]

The licensee.shall implement a secondary-water' chemistry monitoring program to inhibit steam generator tube degrad-ation. This program shall include:

I

~

a.

Identification of a sampling schedule for the critical parameters and control points for these parameters.

4 b.

Identificction of the procedures used to quantify para--

meters that are critical to control points.

~

c.

Identification of proces's sampling points.

I i

d.

Procedure for recording and management of data.

e.

Procedures defining corrective actiow, for off controi l

point chemistry conditions; and f.

A procedure identifying the authority responsible for l

the intarpretation of the data and the sequence and timing of aEtinistrative events required to initiate corrective action.

j 3.

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

FOR THE NUCLEAR REGULATORY COMtilSS10N Robert A. Clark, Chief Operating Reactors Branch '#3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

November 4, 1981

ATTACHMENT TO LICENSE AMENDMENT NO. 41 FACILITY OP" RATING LICENSE NO. DPR,_6j9 DOCKET NO. 50-318, Replace tne following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and ctntain ve'rtical lines indicating the area of change.

The corresponding overleaf pages are also prcvided te maintain document completeness..

Pages 3/4 7-10 3/4 7-11 3/4 7-12 3/4 7-17 3/4 7-31 3/4 9-8 3/4 10-5 B 3/4 7-2 s

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lPLANTSYSTEMS MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.7.1.5 Each mein steam line isolation valve shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

MODE 1 With one main steam line isolation valve inoperable, 4

POWER OPERATION may continue provided the inoperable valve is either restored to OPERABLE status or closed

~ *'

witnin 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; otherwise, be in H0T SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

' MODES 2 With one main steam line isolation va?ve inoperable, sub-and 3 sequent operation in MODES 1, ? or 3 may proceed provided:

a.

The isolation valve is maintained closed.

b.

The provisions qf Specification 3.0.4 are not applicable.

1 Otherwise, 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 t

,4 7.1.5 Each main' steam line isolation valve shall be demonstrated

' OPERABLE by verifying full closure within 3.6 seconds when tested pursuant to Specification 4.0.5.

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=

PLANT SYSTEMS a

I N

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

3. 7. 6.1 The control room emergency ventilation sys' tem shall be OPERABLE with:

a.,[hAd filter trains.

. b.

Two af g_, conditioning units,

~

Two.isolatkon valves in each control room outside air intake c.

duct, d.

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

1 and e.

One isolation valve in the toilet area exhaust duct.

APPLICABILITY: MODES 1, 2, 3 and 4.

O 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 t'ne 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 inoperabli 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 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 i

inoperable, 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 SHUTDOWN within the following 30- hours.

d.

With one common exhaust to atmosphere duct isolat' ion valve in-l operable, restore the inoperable valve' to-OPERABLE status within 1

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 wi, thin the follow'ng 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

2:- With the toilet area. exhaust' duct isolation' valve inoperable, restore the.inopcrable valve to OPERABLE status within 24 hcurs or be in at leas

40T STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN witi.

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

I

~

~

CALVERT CLIFFS - UNIT 2 3/4 7-17 Amendment No. 41 i

l 4

1

1 PLANESYSTEMS

~

l SURVEILLANCE-REQUIREMENTS i

4.7.6.1 The control room emergency vatilation system shall be demon-l strated OPERABLE:

i 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.< 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.

At least once per 18 months or (1) after any structural c.

maintenance on the HEPA filter or charcoal adsorber housing, i

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 e en they 4

are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 2000 cfm i 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 iate 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 teshd in accordance with ANSI N510-1975 (130*C, 95%

R.H.).

The carbon samples not obtained from test canisters.

shall be prepared by either:

a)

Emptying one ent' ire bed from a removed adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a

. length equal to the thickness of the bed, or s

b)

Emptying a longitudinal sample from an hdsorber tray, mixing the adsorbent thoroughly, and obtaining s

samples at least two inches in diameter and with a length equal to the thickness of the bed.

CALVERT CLIFFS - UNIT 2 3/4 7-18

>e-

--, - - - - n

-w

- e

-p-.

.r,,--w, w

t,--,

y

-+-

o

3,.

, TABLE 3.7-4

.t.

SAFF1i RELATED HYDRAULIC SNUBBERS

4

s SNUBBER SYSTEM SNUBBER INSTALLED,

ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT ~

NO.

ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **

TO REMOVE p

(A or I)

(Yes or No)-

(Yes or No),

s 4

2-15-5 COMP. C00LIN'G PUMP #22 DISCH.

I T

18'-6" A

No Yes C

b 2-15-6 COMP. COOLING PUMPS DISCH.

m HEADER 14'-5" A

No Yes 2-15-7 COMP. COOLING PUMPS DISCll.

HESDER 14' 5" A

No Yes 2-15-8 COMP. COOLING TO -LIQUID WASTE EVAP. 64' A

fio No 2-15-9 COMP. COOLING TO LIQUID WAST.EVAP. 64' A

No No I

w1 2-36-1 STEAM SUPPLY TO #22 AUX. SGFP 12

o No Uo S

2-36-1A STEAM SUPPLY TO #22 AUX. SGFP 12' A

No No s

2-36-2 STEAM SUPPLY TO #21 AUX. SGFP l

12' A

No No 2-36-2A STEAM SUPPLY T0.#21. AUX. SGFP I ?. '

A No No 2-36-4 AFW INLET TO #21 STEAM GENERATOR j

65' I

Yes No 2-36-4A AFW INLET TO #21 STEAM GENERATOR

,3 g

65' I

Yes No 2-36-5 AFW INLET TO #22 STEAM GENERATOR 65' I

Yes No'

=

2-38-2 RCS AUX. PIPING TO SAMPLE COOLER

=

54'1"-

- I Yes No.

~~

f

^~

v v

E 4

i 4

TABLE 3.7-4 ff SAFETY RELATED llYDRAULIC SNUBBERS *

/,

n, n

SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR llIGil RADI ATION ESPECIALLY DIFFICULT c,

E-

~~-NO.

ON, LOCATION AND ELEVATION INACCESSIBLE ZONE **

TO REMOVE e

?

~~

(A or I)

(Yes or No)

(Yes or No) v,

$i 2-41-1 CitARGING LINE OUTLET OF REGEN

1 HEAT EXCilG 40' I

Yes No m

2-45-1 F.'W.

INLET TO #21 STEAM GENERATOR 40'-4" I

Yes No 2-45-1A F.W. INLET TO #71 STEAM GENERATOR 40'-4" I

Yes No 2-45-2 F.W. INLET TO #22 STEAM GENERATOR

'w if 55' I

Yes No n

2-45-3 F.W. INLET TO #22 STEAM GENERATOR ki 55' I

Yes No 2-52-1

21 S.I. PUMPS SUCTION FROM CONT.

SUMP E'-7" A

No No 2-52-2 LPSI PUNP #21 SUCTION O'-6" A

No

<o 2-52-2A LPSI PUMP #21 SUCTION O'-6" A

No No 2-52-3

'LPSI PUMP #22 OISCllARGE 4'-0" A

No No 2-52-3A LPSI PUMP #22 DISCHARGE 4'-O'.'

A No No i

2-52-4 HPSI PUMP #22 SUCTION 5'-10" A

No No 2-52-5 HPSI PUMP #23 SUCTION 4'-9" A

No No W

REFUEEIrg OPERATI0t{S CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING LIMITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 1600 pounds shall be prohibited from travel over fuel assemblies in the storage pool.

APPLICABILITY: With fuel assemblies in the storage pool.

ACTION:

itth the requirements of the above specification not satisfied, place the crane load in a safe condition.

The provisions of Specification 3.0.3 are not applicable.

9 SURVEILLANCE REQUIREMENTS 4.r 7 The weight of each load, other than a fuel assembly and CEA, shall be verified to be < 1600 pounds prior to moving it over fuel assemblies.

l l

CALVERT CLIFFS UNIT 2 3/4 9-7

REFUELJNG OPERATIONS SHUTDOWN COOLING AND COOLANT CIRCULATION LIMITING CONDITION FOR OPERATION

3. 9. 8.1 At least one shutdown cooling loop shall be in operation;*

l APPLICABILITY: MODE 6 at all reactor water levels.

ACTION:

a. -With less than one shutdown cooling loop in operation *, suspend l

all operations involving an increase in the reactor decay

heat load or a reduction in boron concentration of the Reactor Coolant System and, specifically, the charging pumps shall be de-energized and the' charging flow paths shall be closed. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere.within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

The shutdown cooling pumps may be de-energized during the time intervals required for local leak rate testing of containment

~

penetration number 41 pursuant to the requirements of Specifica-c, tion 4.6.1.2.d and/or to permit maintenance on valves located in the commen shutdown cooling suction line, provided (1) n_oo operations are permitted which could cause dilution of the reactor coolant system boron concentration and, specifically, the charging pumps shall be de-energized and the charging flow paths shall be closed. (2) all CORE ALTERATIONS are suspended.

(3) all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere are main-tained closed, and (4) the water level above the top of the irradiated fuel is greater than 23 feet.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILL ANCE REQUIREME!GS 4.9.8.1 A shutdown cooling loop shall be determined to be in operation and circulating reactor coolant at a flow rate of 1 3000 gpm** at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

The s'hutdown coolin'g l'oop may be removed from operation for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per

~

8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.

- 1 1500 gpm when the Reactor Coolant System is drained to a level below the midplane of the hot leg.

CALVERT CLIFFS - UNIT 2

3/4 9-8 Amendment No. 37. 38, 41

4 SPECIAL TEST EXCEPTIONS COOLANT t!RCULATION LIMITING CONDITION FOR OPERATION 4

~

3.10.5 The reactor coolant circulation requirements of Specification 3.4'.1 may be suspended and all reactor coolant pumps and shutdown cooling pumps may be 1

de-energized during the time intervals required 1) for local leak rate testing of containment penetration number 41 pursuant to the requirements of Specifica-tion 4.6.1.2.d and 2) to permit maintenance on valves located in the cmnmon shotdown cooling suction line or on the shutdown cooling flow control valve (CV-306) provided:

a.

No operations are permitted which could cause dilution. of a

the reactor coolant system boron concentration, and specifically, the charging pumps shall be de-energized and the charging flow paths shall be closed,-

~

b.

The xenon reactivity is <;0.1% ak/k and is approaching stability, and

+

c.

The SHUTDOWN MARC'N requirement of Specification 3.1.1.2 is verified at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when no shutdown cooling or reactor coolant pumps are in operation.

l APPLICABILITY: MODES 4 and 5.

ACTION:

With the requirements of the above specification not satisfied, suspend all operations involving local leak rate testing of containment penetration number 41, maintenance on valves located in the common shutdown cooling i

suction line, and maintenance on valve CV-306.

i SURVEILLANCE RE0dJIREliENTS 4.10.5.1 The charging pumps shall be verified de= energized and the charging flow paths shall be verified closed at least once per hour'.

4 4.10.5.2 The xeon reactivity shall be determined to be < 0.1% Lk/k and approaching stability within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months prior to suspending reactor coolant circulation.

CALVERT CLIFFS - UNIT 2 3/4 10-5 Amendment No.6. 4I

~

.,~,_i-,,m,,

y.<

e,

.,- ~ -., -,

3,,.

-w

.,w4,-.

-.,-,e...~

3/4.7 _ PLANT SYSTEMS BASES 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 SAFETY VALVES I

The OPERABILITY of the main steam line code safety valves ensures that the secondary system pressure will be limited to within its design pressure of 1000 psig during the most severe anticipated system opera-tional trans'ient. The maximum relieving capacity is associated with a, turbine trip from 100% RATED THERMAL POWER coincident with an assumed loss of condenser heat sink (i.e., no steam bypass to the condenser).

The specified valve lift settings ar.d relieving capacities are in accordance with the requirements of Section III of the ASME Boiler and Pressure Code, 1971 Edition. The tota' relieving capacity for all valves on all of the steam lines is 12.18 x 106 lbs/hr which is 108 percent of the total secondary steam flow of 11.23 x 106 lbs/hr at 100% RATED e

THERMAL POWER. A minimum of 2 OPERABLE safety valves per steam generator ensures that sufficient relieving capacity is available for removing decay heat.

STARTUP and/or POWER OPERATIO Fis allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction in secondary system steam flow and THERMAL POWER required by the reduced reactor trip settings of the Power Level-High channels.

The reactor trip setpoint reductions are derived on the following bases:

For two loop operation SP = (X) - (Y)(V) x 106.5 For single loop operation (two reactor coolant pumps operating in the same loop)

SP = ( } ~X( }("} x 46.8 where:

3P reduced reactor trip setpoint in percent of RATED

=

e THERMAL POWER V

maximum number of inoperable safety valves per steam

=

line CALVERT CLIFFS-UNIT 2 B 3/4 7-1 4

1

e:

r

~

PLANT S,YSTEMS, I

BASES

~

1 maximum number of inoperable safety valves per i

U

=

operating steam line 106'.5 =

Power f.evel-High Trip Setpoint-for two loop operation 46.8 =

Power Le-tel-High Trip Setpoint for single loop.

operation with two reactor coolant pumps operating *

~

in the same loop Total relieving capacity of all safety valves per t

X

=

steam line in lbs/ hour '

i

~

Y Maximum relieving capacity of any one safety valve

=

in lbs/ hour 3

+

3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM I

The OPERABILITY of the auxiliary feedwater system ensures that the Reactor Coolant System can be cooles'down to less than 300*F from i

normal operating conditions in the event of a total loss of off-site i

power.

Each steam driven auxiliary feedwater pump is capable of delivering a total feeddater flow of 700 GPM at a Total Dynamic Head of 2490 ft to the entrance of the steam generators. A capacity-of 450 gpm, however, is sufficient to ensure that adequate feedwater flow is available to remove l

decay heat and reduce the Peactor Coolant Systen temperature to less than

~

300'F when the shutdown coolir.g system may be placed into operation.

3/4.7.1.3 CONDENSATE STORAGE TANK The OPERABILITY of the condensate stcrage tank with the minimum water volume ensures that sufficient water is available to maintain the 3-RCS'at HOT STANDBY conditions for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months with steam discharge to a^_mos-phare with concurrent with tots 1 loss of off-site power. The contained water v61ume limit include: an allowance for water not usable because of tank dfscharge lin'e Tocetion or other physical characteristics.

3/4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant off-s'te radiation dose will he limited to a small fraction CALVERT CLIFFS-UNIT 2 B 3/4 7-2 Amendment No. 41

.

ML20032D426

Text

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