ML20245F647

Amend 118 to License DPR-72,increasing Containment Leakage Test Pressure from 49.6 Psig to 53.3 Psig

ML20245F647
Person / Time
Site:	Crystal River  (DPR-72-A-118)
Issue date:	06/22/1989
From:	Berkow H Office of Nuclear Reactor Regulation
To:
Shared Package
ML20245F636	List: ML20245F632 ML20245F647 ML20245F656
References
NUDOCS 8906280201
Download: ML20245F647 (11)

Text

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og UNITED STATES f

g NUCLEAR REGULATORY COMMISSION 5

e E WASHINGTON, D. C. 20E55 kg... 4,/

FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINE5VILLE CITY OF KISSIMMEE CITY OF LEESBURG CITY OF NEW SMYRNA BEACH AND UTILITIES COMRTESION, CITY OF NEW SMYRNA' BEACH CITY OF OLALA ORLANDO UTILITIES COMMISSION AND CITY OF ORLANDO SEBRIhG UTILITIES COMMISSION SEMlkOLE ELECTRIC COOPERATIVE, INC.

CITY OF TALLAHA55EE DOCKET NO.'50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT l

AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 118 License No. DPR-72

1..

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

A.

The application for amendment by floride Power Corporation, et al.

(the licensees) dated November 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 I; j

(

B.

The facility will operate in conformity with the application, the I

provisions of the Act, and the rules and regulations of the Commission; l

C.

There is reasonable assurance (i) chat the activities authorized by

)

i this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in cornpliance 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 1

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 I

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

i 8906280201 8906'22 ADOCK 0500{gC]2 PDR u____

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. l 2.

Accordingly, the license is amended by changes to the Technical 3

l Specifications as indicated in the attachment to this license amendment,

{

and paragraph 2.C.(2) of Facility Operating License No. 'DPR-72 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.118, are hereby incorporated in the license. Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of. issuance and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY C0ttilSSION yf { bb Herbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 22,1989

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4

- ATTACHMENT-TO LICENSE AMENDMENT NO.118 FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50-302 4

Replace the following pages of-the Appendix "A" Technical Specifications with the' attached pages. The revised pages are identified by amendment number and contain vertical' lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

Remove Insert 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 3/4 6-4

'3/4 6-4 3/4 6-5 3/4 6-5 B3/4 6-l' B3/4 6-1 B3/4 6-2 B3/4 6-2 j

, -5.

..' 1 e

t 3/4.6 crNDdNMENT SYSTINE 3/4.6.1 PRD9JCI CEtTDlNMENT CDRDINMDC DCIGR17f inermr: crmmen mm errpxrren 3.6.1.1 Primary CDUAINMDC INIIGRITY ahall be maintainsd, APPLTCABILTW: MXIS 1, 2, 3 aM 4.

EII2!:

Withcut primary CCNDdNMDC DCIGRTPI, restore CENmINMDC INIIGRITY vithin one hcur or be in at least Icrr SDEEfY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> aM in CDID SHUITU@i within the following 30 hcurs.

serrTT ANcr MrmREMENrs 4.6.1.1. Prinary CDCAINMDC INTERITY ahall be demonstrated:

-a.

At least once per 31 days by verifying that:

1.

All p-i-Laticms* not capable of being closed by CPDABIZ containment autenatic isolation valves and reqpired to be closed during acx:ident coMitions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, % i those valves that may be opened under administrative controls per Specification 3.6.3.1, and 2..

All v4M hatdes are ciceed and saaled.

b.

By verifying that encis ccritairment air lock is OPDUEZ par M 4ficatien 3.6.1.3.

• Despt valves, blind flarsfes, aM deactivated automatic valves which are located inside the ocntainment ard are locked, seale:1, or otherwise secured in the closed positicm. 'Ibese F-r-L ticrs shall be verified ciceed during i

each CDID SHUIDOWW %L that verificatial of these pic-kations being closed need ncrt be perfcrmed nors often than onos per 92 days.

l CRYSIM., RIVDL - EMIT 3 3/4 6-1 Amendment No. II4

e 4

OMIADMENT SYS'IBE OMIADMENT IEMUGE I2MITDC ENrnTrCN PCR OREATICN 3.6.1.2 Centalment leakage rates shall be limited to:

a.

An overall integrated leakage rate of < La, 0.25 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at > P, 53.3 psig.

l a

b.

A cmbined leakage rate of 5 0.60 Ig for all perduations and valves subject to Type B ard C tests, een pressurized to 2 Pa*

5 APPLICMIILTIY: MXES 1, 2, 3 and 4.

ACITCH:

With either (a) the measured overall integrated contaiment leakage rate exaceding 0.75 Ig or (b) with the measumd cmbined leakage rate for all penetrations and valves subject to Type B and C tests =Wbg 0.60 Ig, restore the leakage rate (s) to within the limit (s) prior to increasing the Reactor Coolant System temperature above 200*F.

SURVFrTIANCE mm_uJueriENIS 4.6.1.2 The contaiment leakage rates shall be de_m.uduated at the following test schedule and shall be determined in conformance with the criteria specified in Apperdix J of 10 CFR 50 using the methods and provisions of ANSI N45.4 - 1972:

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

shall be conducted at 40 i.10 month intervals during shutdown at 2 Pa, 53.3 psig, during each 10-year service period.

The third l

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

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GNIKDBEENT SYEMBE gmymr4Ntg marumlinsENis tomtiW)

b. 'If any periodic Type A test _ fails - to amet.75' Ig -the test schedule ~ for sutamquant Type - A'. tests shall be zwiewed and apprw ed by the n = 4=mion.

If two consecutive Type A tests fail to mest.75 In a Type A test shall be performed at least every 18 months until two omisecutive Type A tests most.75 Ig at idhi&

time the above test schedule may be resumed.

c.

'Jhe accuracy of an& Type A. test shall be verified by a supplanantal test idli&:

l.

Cbnfirms the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within 0.25 Ig.

2.. Had a duration sufficient to establish accurately the change in leakage between the Type A test and the supplemental tast.

3.

Raquires the quantity of gas. injected into the containment.or blad fran the containment during the supplemental test to be equivalent.to at-- least 25 pm

d. ' of the total maannrad lankage rate at 2 Pa, 53.3 psig.

I.

d.

Type B and C tests shall be _ conducted with gas at 2 Pa, 53.3 psig l

.at intervals no greater than 24 amiths except for tests involvirg:

1.

Air locks, and 2.

Fs-Lations usirg contiraxus leakage monitoring systems.

e.

Air locks shall be tasted and demonstrated.OPERABIE per Surveillance Requirement 4.6.1.3.

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• 118 i

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1 CCMDdWIENT SYS'IBES suRVmIANCE perYUREMENIS (Omitir=M) f.

Deleted.

g.

All test leakage rates shall be calculated usirq observed data carwertad to absolute values.

Error aralyses shall be performed j

to select a balanced integrated leakage measurement syste.

I l-l 118 i

CRYSTAL RIVER - UNIT 3 3/4 6-4 Amendment No.

l ONIADMNT SYSTDE OWIXDMNT AIR IDOS LIMITI}G CCNDITICH KR OPIPATICN 3.6.1.3 Each otrrtaiment air lock shall be OPERAEE with:

Both doors closed except when the air lock is being used for norml a.

transit entry and exit through the contalment, then at least one air lock door shall be closed, and b.

An overall air lock leakage rate of 5 0.05 In at 2 Pa, 53.3 psig.

APPLIQEZI'Y: 100ES 1, 2, 3, and 4.

ACTICN:

With an air lock inoperable, restore the air lock to OPERABIE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least ICT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> arri in COID SIUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SUmTTT.TANCE Nwum4PRIS 4.6.1.3 Each containment air lock shall be demonstrated OPERABIE:

a.

By verifyirry seal leakage $ 0.01 Ig when the volume between the door seals is pressurized to 2 8 psig for at least 30 seconds after stabilizing pressure for at least 15 minutes:

1.

After each opening, (in Modes 1, 2, 3, or 4) except when the air lock is being w.ai frca m21tiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

2.

• Prior to establishing COtTIADNff DTfD3RITY when mintenance has rut been performed on the air lock.

(Reperfomarx:e of this test is not required prior to entering Mode 4 if the air lock has not been opened since the previous test.)

b.

By ocnducting overall air lock leakage tests at not less than Pa (53.3 psig), and verifying the overall air lock leakage rate is l

within its limit:

1.#At least cnce per 6 months, and

2.

• Prior to establishing CCtfIADMTf DTfDIRITY when maintenance has been performed on the air lock that cou) 4 affect the air lock sealing capability.

At least once per 6 ronths by verifying that only one door in each c.

air lock can be cpened at a tine.

l

• Exemption to Appeniix "J" of 10 CTR 50.

1. 'Ibe provisions of Specification 4.0.2 are not applicable.

CRYSTAL RIVER - OfIT 3 3/4 6-5 Amendment No. 70E,118

w D

s CONTAINMENT SYSTEMS s

INTERNAL PRESSURE LIMITING CONDITION FOR OPERATION 3.6.1.4 - Primary containment internal pressure shall be maintained between 17.7 and 12.7 psia.

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

ACTION:

With the containment internal pressure outside of: the limits above, restore the internal pressure to within the limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN.

within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

i A

SURVEILLANCE REQUIREMENTS 4.6.1.4 The primary containment internal pressure shall be determined to within the limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

CRYSTAL RIVER - UNIT 3 3/4 6-6

________.____m___.___.___

3/4.6 CI2EILDGENT N BILM 3/4.6.1 PRIMM& G2GhDGENT 3/4.6.1.1 CDEILDDENT IkmauiY Primary CORIADEENI' IkihduTt ensums that the release of radioactive materials frtxn the containment atmosphere will be restricted to those leakage paths'and '

associated leak rates n=*

in the safety analyses.

'Ihis restriction, in cxmjunction with the leakage rate limitation, will limit the site boundary radiation dnaam to within the limits of 10 CFR 100 during so::ident conditions.

. 3/4.6.1.2 CDEADDENT IEM3M

'Ihe limitations on containment leakage rates ensure that the total containment leakage volume will not eynaad the value assumed in the safety analyses at the peak accident pressure of 53.3 psig, Pa.

As an - added conservatism, the measured overall integrated leakage rate is further limited to 5 0.75 Ig during performance of the periodic tests to account for possible degradation of the containment leakage barriers between leakage tests.

'Ibe surveillance testing for measuring leakage ratas are consistent with the requirements of Appendix "J" of 10 CFR 50.

3/4.6.1.3 CINIKDNENT AIR IDCKS

'Ibe limitations on closure and leak rate for the containment air locks are requiInd to meet the restrictions on CUTIADMENf IhmiuiY and containment leak rate given.

Surveillance testing of the air lock seals provide assurance that the overall air lock leakage will not hamna excessive due to seal damage during the intervals between air lock leakage tests.

i i

l Amendment No.118 CRYSIAL RIVER - INIT 3 B 3/4 6-1

1 N SEBE Bre:

3/4.6.1.4 pm!seRL PREEEEE

'Ihe lin$taties en ccmtaiment internal preneure ensure that 1) the ocmtainment structure is prevented fran Wing its design negative pressure differential with respect to the cetside atzsphere of 3.0 psig and 2) the containment peak pressure does not h the design presame 'of 54.6 psig during IDCA ocmditions.

'Ihe==vi= = peak pressure obtained fran a IDCA event is 50.3 psig. 'Ihe limit

[

of 3.psig for initial positive contalment pressure will limit the total

==v4== peak pressure to 53,3 psig W11d1 is less than the design pressure and l~

1s ocnsistant with the safety analyses.

3/4.6.1.5 AIR TEMPERMGE

'Ihe limitations on ocmtainment average air t-g ture ensure that the everall contalment average air taperature does not W the initial tanperature i

l condition===ad in the accident analysis for a IDCA.

J/4.6.1.6 GNIEDMENT im0CIURAL Dm!rMJY l

'Ihis limitation ensures.that the structural integrity of the contaiment will be maintained cxmparable to the original design standards for the life of the facility. Structural integrity is required to ensure-that the ocotaiment will withstand the nav4== ' pressure of 53.3 psig ' in. the event of a ' IDCA.

'Ihe.

masurernent of containment tardon lift off force, the tensile tests of the tendon wires or strands, the visual examination of tendons, ard u..:,. and EW_ interior and exterior surfaces of the containment, the naasurement of dcne elevation differences and cracks, the general visual inspection of the dans and the Type A leakage test are sufficient to d=iier-bute this capability.

l S

mYSIAL RIVER - INIT 3 B 3/4 6-2 Amendment No. U, 'il8 L

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