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Notice of Violation from Insp on 900918-1005.Violation Noted:On 900918,containment Integrity for Unit Not Maintained While in Mode 1 in That Valve Dhv 43 Did Not Fully Shut After Performing Cycling & Disabling Evolution
	ML20062D945
Person / Time
Site:	Crystal River
Issue date:	11/07/1990
From:	Reyes L; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	;
Shared Package
ML20062D941	List: IR 05000302/1990032; ML20062D945;
References
	50-302-90-32, NUDOCS 9011190141
	Download: ML20062D945 (28)
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, a. . 1

o ENCLOSURE l i

NOTICE OF VIOLATION' 1

l Florida Power Corporation Docket No. 50-302 l Crystal . River Unit 3 -

License No. DPR-72 During the Nuclear Regulatory Commission -(NRC) inspection con' ducted; on September 18 - October 5, 1990, a violation-- of NRC requirements' was' .

identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appandix C (1990), the violation is listed below:

Technical Specification 3.6.1.1 states that containment integrity .shall- .I be maintained in modes 1, 2,'3, and 4. The action statement requires that without containment integrity restore contair, ment integrity'within one -

hour or be in at least hot standby within the next six hours.

Contrary to the above, on. September .18,' 1990', from- about '4:30 a.m. to 7:00 p.m., containment integrity for Crystal River Unit :3 was- .not maintained while- in Mode 1 in that a flow path existed between the containment sump and vent / drain valves in the decay heat (DH) system through containment isolation valve.DHV 43. ' Valve DHV:43 had been cycled at 4:30 a.m. to prepare'for maintenance on the DH system.--Unknown to the licensee, DHV 43 did not fully shut after- performing. the: cycling and disabling evolution.

This is a Severity Level -IV Violation. (Supplement I).

Pursuant to the provisions of 10 CFR 2.201, Florida Power Corporation is hereby required to submit a written statement or explanation to'the Nuclear -

Regulatory Consnission, ATTN: Document Control: Desk,, Washington, DC 20555, with a copy to the Regional Administrator, Region /II, and a copy to the NRC Resident-Inspector, Crystal River 3, .within: 30 days of the date of the letter-transmitting this Notice. This reply should be clearly marked 1as a " Reply to a Notice of Violation: .and should" include for each violation: 1(1) admission or- denial of the alleged violation, (2) the reason- for the violation 'if-admitted, (3) the corrective -steps which have been: taken -andithe results achieved, (4) the corrective steps which will be taken .to' avoid further violations, ' and (5) the date when full compliance will.' bel achieved. Where good cause is shown, consideration.will _be given to: extending the response -l

. -time. If an adequate reply,is not received within the time'specified in this '

Notice, an order may be issued- to show cause whylthe license.should not be I

modified, suspended, or revoked or why such other action'as may be proper should not be taken.

FOR THE-NUCLEAR REGULATORYJCOMMISSION

/

fo: Luis'A. Reyes,-Direc Division of Reactor Projects i

Dated at' Atlanta, Georgia this 7th day of November 1990 9011190141 901107 PDR 's O ADOCK 05000302 PDC p

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J ENCLOSURE 2-

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MEETING AGENDA--

ENFORCEMENT CONFERENCE.

I 1

l l-INTRODUCTIONS P;M. (PAT) : BEARD

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SENICR.VICE PRESIDENT .i NUCLEAR' OPERATIONS:

~ - ;

ai DHV-43

.G.H. (GREG)<HALNON) .

NUCLEAR: OPERATIONS 1 ENGINEER- )tl DECAY'~ HEAT GUARD PIPE F. V. 4 (FRANK)~ FUSICK, 4 MANAGER, DESIGN 4. MODIFICATION CONCLUSION /ALL

BREAK--------------------------------- i 4

MANAGEMENT DISCUSSION-1 OPENING REMARKS -

G. : L.r -(GARY)) BOLDT VICE: PRESIDENT' NUCLEAR. OPERATIONS-OIL COLLECTION SYSTEM H. '(HOYT) . KOON '-.

NUCLEARfMAINTENANCE' SUPERINTENDENT CIASING REMARKS s

P.M. . (PAT)IBEARDI

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.OTHERS: ATTENDING:

T. V. (TERRY) AUSTIN

.r B. J.-~(BRUCE) HICKLE PRINCIPAL HUCLEAR' MECHANICAL ENGINEER-DIRECTOR,-QUALITY' PROGRAMS K. R. (KEN) NILSON MANAGER, NUCLEAR: LICENSING-6

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-ENCLOSURE 3- !

j LIST OF ATTENDEES l

U. S. Nuclear Regulatory Consnission -

G. A. Belisle, Chief. Test Programs Section,= Division of Reactor. Safety (DRS),_RII r H. N. Berkow,. Director, Project: Directorate 11-2, NRR R. V. Crienjak, Chief,: Division of Reactor' Projects (DRP), Section 2B, RII' S. D. Ebneter, Regional. Administrator, RII' l A. F. Gibson, Director, DRS, RII .

4 P. Holmes-Ray,-Senior Resident Inspector, Crystal River 3 <

F. Jape, Chief. Engineering Assessment Section, DRS' G. R. Jenkins, Director, Enforcement andEInvestigation Coordination Staff'(EICS).

F. W. Merschoff, Deputy Director, DRP .

J. L. Milhoan Deputy Regio 1al Administrator-R. P. Schin, Project. Engineer, DRP H. Silver, NRC Project Manager.1 Crystal- River 3 ,

M. V. Sinkule,' Projects Branch. Chief 1DRP :

H. L. Whitener, Reactor Inspector, Test Programs Section, DRS .

B. Uryc, Senior Enforcement Specialist, EICS--

T Florida Power' Corporation a l

l T. V. Austin, Principal Mechanical Engineer _

P. M. Beard, Senior Vice President, Nuclear Operations G. L. Boldt, Vice President -Nuclear Production' ;

F. V. Fusick, Manager, Design and _ Modifications B. J. Hickle, Director, Quality Programs 1 .

t G.uH. Holnan, Operations Engineer

-H. Koon Maintenance Superintendent.- '

K. R. Wilson, Manager,? Nuclear Licensing- ;

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STROKING UNDER ADNIN CONTROL- !

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7 CLEARANCE ORDERED-TO ENSURE INDEPENDENT. VERIFICATION OF-POSITION l- , i OTHER CONSIDERATIONS CONTINGENCIES:'ANOAhBREAKERLIF.UNEXPECTEDRE i

- UPPER ELEVATION VENTS SOLID WITH' WATER'- N0 RB AIR CONTACT NSS STATIONED AT SUNP LEVEL: RECORDER FOR,1NMEDIATE DECISION-b

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CALCULATION ASSUMPTIONS:

WORST CASE. ACCIDENT PRESSURE - 53.9 PSIG'(FSAR)=

PRESSURE ESCALATES TO 53.9 PSIG'IN 10;SECONOS (FSAR)

AIR FLOW IS SONIC (>l3.2: PSIG)-

LIMITING ORIFICE 15 DNV ' AREA 0F VALVE-OPENING CALCULATED FROM ACTUAL DATA i

RESULTS: AREA =. 11 sq in-AIR FLOW. 119 scfm WATER-FLOW =tl8.8 gpa ACTUAL VALVE POSITION:' '

2< TURNS.0UT 0F 850 0FF SEAT-1 1

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Low PoputATxoN 0.2 ram 1.6 ram ZONE i..

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t connnevrva Aerrow PLAN CAusa: .

OPERATOR WAS UNAWARE OF DLLAY TIME IN DE-ENERGIZING MOV BY TOROUE SWITCH arm:

ENSURE DETAILS'ARE GIVEN APPROPRIATE EMPHASIS IN LESSON PLANS Raournas:

O IMMEDIATE ACTION FOR OPERATORS ON-SHIFT.

o RE-TRAIN PRESENT LICENSED AND NON LICENSED OPERATORS o

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EVENT: DHv-43 LEFT PARTIALLY OPEN l ;

RESULT: CONTAINMENT BREACHED FOR 14 HRS i

a CAusE: OPERATOR UNAWARE 0F SWI 2H OPERATION !

! SAFETY: REALISTIC LOCA WELL. BELOW PART-100 LIMI' l d

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CORRECTIVE ACTION: IMMEDIATE AND CONTINUED !

TRAINING 0F OPERATORS i i

L INDUSTRY EXPERIENCE:. NETWORK ENTRY- ,

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ENCLOSURE 4 l

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CRYSTAL RIVER UNIT'S l

) RECIRCULATION PIPING GUARD PIPING i

1. Guard piping designed to control leakage to-prevent drainage of. the Reactor Building.

sump. !

2. Engineering deficiency during initial design. :

3. Inaccurate 1989 FSAR change.

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1971 B&W CORRESPONDENCE -

L l ... the intent of. the guard pipe is to prevent excessive. quantities of fluid escaping from the :

) Reactor Building sump:in the unlikely event a LOCA (

) and subse to occur.quent ' rupture of this. Decay Heat line were- i 1

i i . i l 1987-B&W CORRESPONDFNCE "The function of the piping jacket is to prevent drainage of the Rt sump in:the event of: failure or breakage of the: piping.between.the RB penetration- .

and the isolation valves."

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3.6.4 Sinale valve- and closed system outside l containment:

"The single valve and pi ,

containment and the valve; ping tatween the' i

in a protective leak. . tight- or controlled shall be enclosed !

l leakace housino to' prevent leakage to the :

i atmosphere."

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GUARD PIPE DESIGN .

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1989.FSAR REVISION !

' )

l A Type. Il penetration with a single valve was !

i previously undefined in the FSAR. 1 Engineering researched this issue and revealed: -

compliance with Standard Review Plan 6.2.4 compliance with ANSI N271-1976- 1 Response inaccurately. described the guard pipe as ;

" leak tight". - j

~

The FSAR was revised to " match" -the perceived plant configuration. . {

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-se-wa-g-epp y-m wew= we g e g-y.r-* w y _,g-=aebe,eg 99 .ege.,w.,,- g v.,y.,..., ,+,gt,., ,, .g.- rww . wag ee

we e w's Tv4-0 %e% -wh+4 m *=- -74M m-w-w -es+-esve*d

ML20062D945

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