ML20062D945
| 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: |
| References | |
| 50-302-90-32, NUDOCS 9011190141 | |
| Download: ML20062D945 (28) | |
Text
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o ENCLOSURE '
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 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 Dated at' Atlanta, Georgia this 7th day of November 1990 9011190141 901107
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'l MEETING AGENDA--
ENFORCEMENT CONFERENCE.
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INTRODUCTIONS P;M. (PAT) : BEARD
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SENICR.VICE PRESIDENT NUCLEAR' OPERATIONS:
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ai DHV-43
.G.H.
(GREG)<HALNON)
NUCLEAR: OPERATIONS 1 ENGINEER-
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DECAY'~ HEAT GUARD PIPE F. V. 4 (FRANK)~ FUSICK, 4
MANAGER, DESIGN 4. MODIFICATION CONCLUSION
/ALL
BREAK---------------------------------
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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 PRINCIPAL HUCLEAR' MECHANICAL ENGINEER-
.r B. J.-~(BRUCE) HICKLE 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 G.uH. Holnan, Operations Engineer t
-H. Koon Maintenance Superintendent.-
K. R. Wilson, Manager,? Nuclear Licensing-
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STROKING UNDER ADNIN CONTROL-Al-500. CONDUCT Or' OPERATIONS =
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Valve-ID: DHV 43
.st Date: 05/01/90:
Test Type:- AS LEFT 1
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- TIME PARAMETERS,
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Open'to Close Close to Open--
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. Stroke time 105.300 Sec .104;800 Sec 1
Bypass Time 0.650 Sec
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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:
IMMEDIATE ACTION FOR OPERATORS ON-SHIFT.
O RE-TRAIN PRESENT LICENSED AND o
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l STUDY THE DETAILS 0F THIS: EVENT-i FIRST REQUAL CYCLE 1991 1
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l REVISE AND EMPHASIZE LESSON PLAN DEALING WITH MOV'S.
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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
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CORRECTIVE ACTION:
IMMEDIATE AND CONTINUED TRAINING 0F OPERATORS i
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INDUSTRY EXPERIENCE:.
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RECIRCULATION PIPING GUARD PIPING i
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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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l the intent of. the guard pipe is to prevent excessive. quantities of fluid escaping from the
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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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ANSI.N271-1976 3.6.4 Sinale valve-and closed system outside l
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shall be enclosed l
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protective leak.. tight-or controlled leakace housino to' prevent leakage to the i
atmosphere."
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r 1989.FSAR REVISION l
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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". -
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" match" -the perceived
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