ML20034A685

Amend 128 to License DPR-40,changing Tech Specs to Provide Limiting Conditions for Operation & Surveillance Requirements Re Mods That Will Be Made to Control Room Air Treatment Sys

ML20034A685
Person / Time
Site:	Fort Calhoun
Issue date:	04/12/1990
From:	Hebdon F Office of Nuclear Reactor Regulation
To:
Shared Package
ML20034A684	List: ML20034A683 ML20034A685 ML20034A688
References
NUDOCS 9004240122
Download: ML20034A685 (13)

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UNITED STATES g.

g NUCLEAR REGULATORY COMMISSION' ti,

l-WASHINGTON, D. C,20055 '-

%, *.4+l' OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285

. FORT CALHOUN-STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE 1 Amendment No.128' License No. DPR,-40" 1.

The Nuclear' Regulatory.Comission-(t_he. Comission) has.found thati-A. _

The: application for amendment by the Omaha Public Power District (the licensee) dated February 1,1990, complies with the standards.

and requiren*nts of the Atomic Energy. Act of 1954,- as amended (the Act), and the Comission's rulesiand regulations. set forth in 10 CFR _

Chapter I;-

B.

Thefacilitywilloperateinconformitywithshe' application,as amended, the provisions'of the Act, and the rules and regulations-of_ the Comission; C.

There is reasonable assurance:

(1)thatthe-:activitiescauthorized

-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 license amendment will not be inimical to the comon defense and_ security or to the health' and: safety of the public; and

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E.

The issuance of this amendment is in accordance with 10 CFR Part 51-of the Comission's regulations and a11' applicable -requirements have been satisfied.

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9004240122 900412 fDR ADOCK 03000283

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'Accordingly, Facility Operating License No. DPR-40 'is amended by changes-.

to the.Technica1' Specifications as indicated in the attachment to-this license amendment, and paragraph.3.B. of Facility Operating License No'.

DPR-40 is hereby ' amended to read as follows:

B.

Technical Specifications-1 The Technical Specifications contained in Appendix A,-as revised through Amendment No.128, are hereby incorporated -

in-the license. -The licensee-shall operate the facility in-accordance with the Technical Specifications.-

3.

The license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION I

i lY mb 2.

Frederick J. Heb n, Director i

Project Directorate IV Division of Reactor-Projects - III, IV, V and Special Projects Office of. Nuclear Reactor Regulation q

Attachment:

Changes to the Technical Specifications Date of Issuance: April 12, 1990 i

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ATTACHMENT TO LICENSE = AMENDMENT NO.128 FACILITY OPERATING LICENSE NO. DPR DOCKET NO. 50-285 Revise Appendix "A" Technica1' Specifications as -indicated below. The revised.

i pages are identified by. amendment' number and contain. vertical' lines' indicating the area of change.-

' j Remove Pa.ges~

Insert Pages-

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2-59 i

2-90 2-90 3-17

'3-17 3-17a'

~3-17a 3-20~

3-20 t

3-20a-3-20a-

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3-20b 3-20c 3-20c 3 -3 3-85 3-85 q

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2.0 LIMITING CONDITIONS FOR OPERATION 2.12 Control Room Systems-Aeolicability Applies to the control room air conditioning and filtering systems.

Obiective To limit -the environmental conditions in the control room, under normal'

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and post DBA conditions.

Specifications (1)

If. the control room air temperature reaches.120'F, immediate action shall be taken to reduce this temperature.

If the-1 temperature cannet be reduced.to below 120'F in four hours, the i

reactor wili be placed in a hot. shutdown condition.

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(2)

A thermometer must be in the control room at all times.

(3)

All areas of the plant which have safety related instrumentation will be observed during hot functional testing to determine local temperatures and monitored during operation if normal plant ventilation is not available.

-(4)

With one control room air filtration system inoperable, restore the inoperable system to operable status within / days or be in at least cold shutdown condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.-

Basis The reactor protective system and the engineered safeguards system were designed for and the instrumentation was tested at 120*F.

Therefore, if the temperature of the control room exceeds 120'F, the reactor will be shut down and the conditions corrected to preclude failure of components o

in an untested environment.

If the control room air treatment system is found to be inoperable, there is no immediate threat to the control raom and reactor operation may continue-for a limited period of time wl.

the. system cannot be repaired within.sevea (7) pairs are being made.

If

. re days, the reactor is shut down and brought to cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2-59' Amendment No. 15.128' V

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,7, TABLE 2-7 FIRE DETECTION ZONES:

a Zone No.

Location i

1 Auxiliary Building, Elevations 971 and 989 West

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2 Auxiliary Building Elevation 989 East.

3 Auxiliary Building, Elevation 989, Lower Electrical Penetration Room (Room 20) 4 AuxiliaryBuilding,-Elevation 989,AirCompressorRoom(Room'19) 5

,suxiliary Building, Elevation 1007, Corridor 26, Rooms 58,-59;and 60 6

Auxiliary Building, Elevations 1007-and 1011, Uncontrolled 7

Auxiliary Building, Elevation-1013, Upper. Electrical-Penetration Room (Room 57) 8 Auxiliary Building, Elevations 989 and.1007, Boric Acid Tank:

Area, Drumming Area, New Fuel Area 9

Auxiliary Building, Elevation'1036, Control Room Complex, Control Room Hallways' 10 Containment, Elevation 1013, RC Pump Cavities 11 Containment, Elevation 994 12.

Containment, Elevation 1045 13 Auxiliary Building, Elevation 1025 (Rooms 69 and 71) 14 Turbine Building, Elevation'990 15 Turbine Building, Elevation 1011-16 Turbine Building, Elevation 1036 17 Containment Fans VA-38 and-VA-70 18 Containment Fans VA-3A and VA-7C 19 Containment Fans'VA-2A and VA-2B 20 Control Room Panels CB-1/2/3 Return Air 21 Containment NDWC Fans VA-12A and VA-128 22 Containment Purge Discharge Fans VA-32A and VA-328 23 DG-2 Room Exhaust L n, VA-52B 24 Containment Purge Supply Fans VA-24A and VA-248 25 Control-Room and Hallway Ventilation Ducts L

26 Auxiliary Building (Controlled) Supply Fans,-VA-35A'and VA-35B 27 Auxiliary Building (Controlled)~Exhaustfans,VA-40A,VA-408,and VA-40C '

28 Auxiliary-Building (Uncontrolled)' Supply Fans, VA-45A and VA-45B 29 Auxiliary Building (Uncontrolled)' Exhaust Fan, VA-41 30 Auxiliary. Building Elevator Shaft Fan, VA-51 r

31 Control Room Air Conditioning Fans, VA-46A and VA-46B 32 DG-l' Room Exhaust Fan, VA-52A 33 Auxiliary Building, Elevation 1036 (Room 81) 34 Plant Sprinkler Flow 35 AuxiliaryBuilding,DG-2(Room 64) 36-Auxiliary Building, DG-1 (Room 63)

.;7 Intake Structure Including Raw Water Pump Room 38 Auxiliary Building Open Stairwell 39 Auxi1iary Building 0 pen-Hatchway 40 Control Room Outside Air filter VA-64A Room 81 41 Control Room Outside Air Filter VA-648 Room 81 2-90' Amendment No.. 38, 69,128-

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. 3.0 SURVE1LLANCE RE001REMENTS-3.2 Eauipment'and Samolino Tests-Acolicability AppliesLto plant equipment and conditions related to safety.-

Obiective

t To-specify the minimum frequency-and type of. surveillance to'be app'ied l

to critical plant equipment and conditions.:

Soecifications

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t Equipment-and sampling ' tests shall be conduct'd as specified;in Tibles:

e 3-4 and 3-5.

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t The equipment testing and system sampling frequencies specified in Tables-3-4 and 3-5 are considered adequate. based upon experience, to maintain the status of the equipment and' systems so'as to assure safe operation.-

Thus, those systems where changes might occur relatively rapidly'are sampled frequently and those -static systems:not subject to changes are-sampled less frequently.

The-control room air treatment' s of. redundant-high' 1:

airfilters-(ystem-consists:HEPA) and charcoal adsorbe HEPA efficiency particulate filters are installed before and-~ after> the' charcoal adsorbers.

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charcoal adsorbers are installed to reduce'the-potential-intake of iodine to the control room.

The in-place _ test-results will confirm system integrity.and performance ~.

The laboratory carbon sample test results should indicate methyl iodide removal efficiency of_ at least 99.825

l percent for expected accident conditions.

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The spent fuel storage-decontamination areas air treatment system is designed to filter the building atmosphereito the auxiliary building vent during refueling operations.

The charcoal adsorbers are installed to reduce the potential release of radiciodine to the environment.

In-place-testing is performed to confirm the integrity of the filter system.- The charcoal adsorbers are periodically sampled to insure capability for the removal of radioactive iodine.

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3-17 Amendment No.' g 67,122

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- 3.0-SURVEILLANCE RE0VIREMENTS 3.2 Eouioment and Samolino Tests (continued)

The Safety Injection (SI)- pump room, air treatment system consists of; charcoal adsorbers which are installed in'normally bypassed ducts. -This:

system is. designed to reduce.the potential. release of-radiciodine in SI pump rooms during the, recirculation period following a DBA.

The'in-place 1

i and laboratory testing of charcoal adsorbers will assure system' integrity!

't and performance.

Pressure drops across the ce?hined HEPA filters and' charcoal-adsorbers, of less 'than'.9 inches of water for the control room filters-(VA-64A:&

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VA-648).and of: less 'than -Si inches of water for each of the other-air-treatment systems will indicate! that the filters and adsorbers are not

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clogged by amounts = of_ foreign: matter that. wou'd interfere with-performance to established levels.

0)eration of each' system for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />,

-every month -will~ demonstrate opera)ility and remove excessive moisture-buildup in the adsorbers.

If significant painting, fire; or chemical release. occurs such that1the-HEPA filters or charcoal adsorbers could become: contaminated from the i

fumes, -chemicals or forei confirm system performance. gn materials, testing willL be per30cmad.to l

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Demonstration of the automatic and/or manual initiation capability.will assure the system's availability.

References USAR,.Secticn 9.10

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3-17a Aanendment No.15, 67,

128, l

TABLE 3-5 MINDM FRE00ENCIES KR BOUIHerr TESPS Test Freauency ESAR M on Referen

'1.

Control Element Dwp tiiies of all full-Each refueling operation 7.5.3 Assemblies length CEA's 2.

Control Element Partial movenent of all Every two weeks 7

Assemblies CEAs (Minima of 6 in) 3.

Pressurizer Safety Set Ibint Choe each refueling outage 7

Valves 1

4..

Main Steam Safety Set Point Each refueling outage 4

Valves 5.

Refueling Systen Functioning Prior to refueling outage Interlocks 9.5.6

( 6.

Raw iMter Systen Functioning Each refueling outage 9.8 Valve Actuation

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' ' 7.

Fire Protectim functioning Monthly 9.11 Pumps & Power Supply 8.

Reactor Coolant Evaluate.

Leily*

4-Systen Loakage

- i 9.

Diesel Fuel-Supply:

Puel Inventory Daily; 8.4 t

70a. Charoaal and HEPA-

1. In-Place Testina**

t 9.10 Filters for Omrcoal adbbs and HEPA. Each refueling shutdown not.to exceed 18 e

ccntrol Roan filter banks shall be leak months or after every 720. hours of systen tested and'show > 99.95%.

operation or after each complete or partial -

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Freon '(R-11' or R-112) and replacement of the charcoal arhrbr/HEPA

'j cold DOP particulates filter banks, Lor after any major structural removal, respectively.

maintenance _on the oysi.se housing and following significant painting, fire or'-

chemical releases in a ventilation zone ommunicating with the systen.-

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'* _ menever the systen is at or above operating tauperature and pressure.

• • Tests shall be perfooned in su.memce with agplicable sectiod(s) of ANSI N510-1980.

. Amendment No.E 15,:26,128 l e

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'mBIE 3-5 (Continued)

Test Freauency FSM Section Refermce 10a.

(continued)

2. Laboratory Testiro*

• Prior to initial loading in filter unit.

a.

Initial batch tests of activated charcoal shall snow 99.825% radimetive methyl l

iodide removal when tested under conditions of 2 70%

relativehumidip,nletmethyl 2 176'F (80*C) 1.5 to 2.0 ng/m i iodide concentration at a face velocity of 401 1.6 FPM (12.2 10.5 m/ min) and at a bed depth of 4 inches (101.6 nm).

b.

Activated charcoal 11s Each refueling shutdown not to exceed 18 shall be replaced or tested.

months or after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system

'Ihe test results shall show operation and following significant painting, 2 99.825% nethyl iodide fire or chemical relwse in a ventilation I

renoval when tested under zcne oczemunicating with the systen.

Y conditions of 2 70% relative I

y humidity, 2 176*F (80 C), at a o

face velocity of 401 1.6 FPM (12.2 1 0.5 m/ min) and at a bed depth of 4 inches (101.6 nun).

3. Overall Systen operation a.

Each circuit shall be Ten hours every nonth operated.

b.

'1he pressure drop across At least mce per plant operating cycle.

the cxinbined HEPA filters and charcoal adsorber banks shall be denonstrated to be less than 9 inches of water at systen l

design flow rate.

c.

Fan shall be shown to At least cn per plant operating cycle.

operate within i 10% design flew.

4. Automatic and nenual At least mee per plant operating cycle.

initiation of the systas shall be demcmstrated.

• o Tests shall be perfooned in accordan with applicable aar+!<m(s) of ANSI N510-1980.

Amendment No. 15, 26,128

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Test Frequency FSAR Section Reference m.-

'10b.

G arcoal Adsorbers 1.

In-Plam Testim **

Each refueling shutdown not to exceed

.6.2~

for Spent Fuel Charcoal adsorbers shall-be 18 months or after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> 9.10 Storage Pool Area leak tested and shall-show of system operation,jor after each

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2 99% Frean (R-11 or R-112) complete or partial,replamment of. the rearal.

charcoal admu.W bank, or afteriany major strw+nrnl maintenance on the system hoaaing and following significant painting, fire or chemical release In a -

ventilation zone communicating with'the systen.

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2.

Tahmitory Testim

a. Initial batch tests of all Prior to initial loading in the filter unit.

charcoal adsorbers shall show

2. 99% elemental iodine remmral den tested unoer conditions of 2 95J R.H., 2 125 F, ' 5 : to 10 mg/m inlet elemental iodine concentration and at the Y

face velocity within,1 20% of g

system design.

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b. The carbon sanple test Fan refueling shutsh=1 not to exceed 18 results shall show 2 90%

sonths or after every. 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of.systen elemental iodine removal, operation, and following significant' under canditions of 2 95%

painting, fire or chemical release in any 3 :.

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R.H., 2 125*F, 5 to 10 m/m zone cxamunicsting with the'systen.

inlet. elemental concentration and within 20% of design; face-velocity.

3.

Overall' Systen Operatica

a. Operation of each circuit Ten honr3 every sonth shall be denonstrated.

' b. Voltme flow rateMunugh

. At least once.per plant operating cycle.

charcoalLfilter shall be shown

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to be between 9000 and 12,000 g

cfm.

4.- Manual' initiation of the At least cmoe per plant operating cycle.

systen shall be dencmstrated.

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7 60 Tests shall be perfoomed in accordance with applicable section(s) of ANSI N510-1980.

L Amendment No. l15, 26, 57 1

128; L -

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Test Freqpecy FSAR

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-(Continued)

Section Refermoe J-

10c. Charcoal Ainarbers 1.

In-Place Testing **

Each refueling shutdom not to exceed 9.10 for S.I. Pump Room Charcoal adwrim.s shall be 18 months or after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of 6.2 leak tested and shall show systen operation or after each canplete.

2 99% Freon (R-11 or R-112) or partial replacessent of the charcoal removal.

adwtim. bank, or after any major.

structural maintmance m the systen housing and following significant-painting,' fire or chemical release in any ventilation zone ammunicating with the systen.

2.

T A yahn.y Testina Prior to initial loading in the filter unit.

a.

Initial batch tests of

-all chirocal adsorbers shall show 2 39% elenental ioduw rartnral when : tested under

. conditions of 2 95% R H.~,

3

_y 2 125'F,-S to 10 mg/m inlet w

elenental iodine concentration

.E and at a fa

' velocity within

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i 20% of systen design.

b.

'1he cartrn sanple test Emdt refueling shutdoun not to armarf 18 results for the S.I. Pump Rocus amths or after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system charcoal filters shall show no operation and following significant painting-less thw 90% elenental'iodire 1 fire or chemical release in any ventilatim.

x removal,.under conditions ofi zone connunicating with the systen.

2 95) R.H., atj 125'F, 5 to 10 mg/ar:17tiet elenental' iodine concentration and within f 20%-

of design face velocity.

' 3.

Overall System Operation"

a.. Operation of each circuit.

Ten hours every nonth..

shall be denonstrated.

b.

vb1tane flow rate shall At least once per plant operating cycle.

..be shown to be between:3000

- and 6000 cfm.-

oo Tests shall be perfooned in awui.demce with applicable section(s) of ANSI N510-1990.

Amendment No.15. 2#r 52.

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a 3.0 SURVEllLANCE RE0VIREMENTS 3.16 Recirculation Heat-Removal System inteority Testina' Aeolicability-1 Applies to determination,of the integrity of the shutdown cooling system.

and associated components.

)

Obiective -

To. verify that the leakage from:the recirculation heat removal system-components is within acceptable-limits.-

-Soecifications q

(1) a.

The portion of' the' shutdown' cooling' system that,1 ts-outside the containment shall be testedtat 250 psig on a lo refueling interval.

b.

Piping from valee; HCV-383-3 and HCV-383-4 to; the discharge isolation valves of the-safety injection pumps'-

and containment spray pumps shall be hydrostatically-

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tested at no less than 100 psig at the testing frequency specified in (1)a..above.

c.

Visual inspection of the system's1 components shall be performed at the frequency specified.in(l')a..above.to.

uncover. any significant: leakage.

?The;1eakage.shall be measured by collection and weighing; or by any other.

equivalent method.

(2) a.

The maximum allowable leakage from the. recirculating heat removal system's components (which1 include valve stems,

flanges, and pump seals) shall' not' -exceed,1243 cc/hr.

.l under the test conditions given in (1)a. and (1)b. above.

i b.

Repairs shall be made as _ required to maintain leakage within the acceptable limits.

1 Basis The limiting leakage rates from the shutdown cooling system are judgment 1

values based primarily on assuring-that the components could operate without mechanical failure for a period-on the order of 200; days after'a design basis accident as well -as limiting the potential' post acc-ident; l,i airborne radiciodine concentrations in the control ~ room.

The' test pressure (250 psig) achieved either by normal syste.a operation or; by j

hydrostatic testing gives an adequatemarginovercp'highestpressure J

within the syste.a after a design basis accident Similarly,3the

)

hydrostatic test pressure for the return lines,from the containment to the shutdown cooling system (100 psig) gives an adequate margin over=.the

' highest pressure within the lines after a design basis' accident.

3-84 Amendment No'. 97, J22 128 O

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i 3.0 SURVEILLANCE REOUTREMENTS

-3,16 Recirculation Heat Removal System Inteorit.v Testina (Continued)

A shutdown cooling-system leakage oi 1243 'cc/hr will limit off-site

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exposures due to leakage to insignificant ~. levels relative to those-casculated for dirret

.eakage from.the containment in the design basis

-accident.

The safety injection = system-pump-rooms are equipped with-

-individual charcoal filters which are placed into operation by means'of' switches in -the control room.

The radiation detectors in the auxiliary building exhaust duct are used to detect high radiation level. The 1243-

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cc/hr leak. rate is sufficiently high. to allow for reasonable leakage through the-pump seals-and valve packings, and-yet smal1~enough to be readily handled by the - pumps and radioactive waste system. Leakage to?

the safety injectj g-system pump room sumps will be returned to the spent-

.,l regenerant -tanks.

3 Additional makeup water to the containment sump.

inventory can be readily accommodated via the charging pumps from either 1

the SIRW tank or the concentrated boric acid storage tanks.

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in case of failure to meet the acceptable criteria for leakage from the shutdown cooling system or the associated: components, it may be possible i

to effect repairs within a short time. ' If so, it-is considered unnecessary and unjustified to shut down the reactor.

The times allowed for repairs are consistent with the times developed for other engineered safeguards components.

References i

(1) USAR, Section 9.3 i

(2) USAR, Section 6.2 y

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i 3-85 Amendment No. 97,128,

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