IR 05000302/1988006

Insp Rept 50-302/88-06 on 880229-0311.No Violations or Deviations Noted.Major Areas Inspected:Plant Operations, Security,Radiological Controls,Lers & Nonconforming Operations Repts & Facility Mods

ML20151E376
Person / Time
Site:	Crystal River
Issue date:	04/05/1988
From:	Crlenjak R, Holmesray P, Stetka T, Tedrow J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20151E363	List: IR 05000302/1988006 ML20151E360
References
50-302-88-06, 50-302-88-6, NUDOCS 8804150208
Download: ML20151E376 (10)

Text

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Report No: 50-302/88-06 Licensee: Florida Power Corporation-3201~34th Street, South St. Petersburg, FL 33733 Docket No: 50-302 License No: OpR-72 , i Facility Name: Crystal River J Inspection Conducted: February 12 - March 11, 1988 Inspectors: faw> f)u d (lm') N6I$f Dat'e Signed l T.Stetka,SpiorResident nspector

  "l%d l J. Tedrow, RtGid'ntanspectorO~

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  'h1auu P. Holmed-IIue l A D, Senior Residen ' Inspector c/k/#
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Dete/ Signed ! Approved by: . A R. CrTenjik, Sp Won Chief

Odte/ Signed Division of Reactor projects j . SUMMARY i Scope: This routine inspection was conducted by three resident inspectors in l the areas of plant operations, security, radiological controls, Licensee Event i Reports and Nonconforming Operations Reports, facility modifications, and l licensee action on previous inspection items. Numerous facility tours were - conducted and facility operations observed. Some of these tours and observa- , tions were conducted on backshift Re t.ults : No violations or deviations were identifie hgg $$ g2

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l i i i i REPORT DETAILS [ t Persons Contacted t- 1 Licensee Employees  :

 *J. Alberdi, Assistant Director, Nuclear Plant Operations
 *P. Breedlove, Nuclear Records Management Supervisor

*M. Clary, Principal Nuclear Mechanical Engineer

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 *G. Clymer, Manager, Nuclear Waste    t
 *J. Colby, Manager, Nuclear Mechanical / Structural Engineering Services  !
 *M. Collins, Nuclear Safety & Reliability Superintendent
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 *E. Ford, Licensing Specialist
 *R. Fuller, Senior Nuclear Licensing Engineer   i
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 *D. Gulling, Nuclear Inservice Inspection Specialist G. Halnon, Nuclear Operations Technical Advisor
 *V. Hernandez, Senior Nuclear Quality Assurance Specialist B. Hickle, Manager, Nuclear Plant Operations   r
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 *S. Johnson, Manager, Site Nuclear Services

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 *A. Kazemfar, Supervisor Radiological Support Services   r i  *H. Koon, Assistant Nuclear Maintenance Superintendent   l 1  *G. Longhouser, Nuclear Security Superintendent   :

" Marshall, Nuclear Operations Superintendent j *P. McKee, Director, Nuclear Plant Operations

 *S. Robinson, Nuclear Chemistry & Radiation Protection Superintendent  l
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 *V, Roppel, Manager, Nuclear Operations Maintenance & Outages 7  *M. Williams, Nuclear Regulatory Specialist    t
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M. Wilson, Senior Nuc1(ar Maintenance Specialist j *W. Worley, Nuclear Chemistry Supervisor

Other licensee employees contacted included office, operations, engi-d neering, maintenance, chemistry / radiation and corporate personnel, i

 * Attended exit interview

'l Exit Interview (30703) j The inspector met with licensee representatives (denoted in paragraph 1) i at the conclusion of the inspection on March 11, 1938. During this l' meeting, the inspector summarized the scope and findings of the inspection , as they are detailed in this report with particular emphasis on the  !

  * Unresolved Item and Inspector Followup Item (IFI).   ;

l The licensee representatives acknowledged the inspector's comments and did { j not identify as proprietary any of the materials provided to or reviewed [ by the inspector during this inspection, i i

)  "Unresolved items are matters about which more information is required to determined whether they are acceptable or may involve violations or  j d

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' Licensee Action on Previously Identified Inspection Findings (92702 and 92701)
 (Closed) IFI 302/87-40-05: Review the modification to the containment hydrogen monitoring system to replace drain piping with seismically qualified pipin The licensee has installed and the inspector has reviewed modification MAR 87-11-19-01 to add additional pipe supports to enable this system to meet seismic requirement . Review of plant Operations (71707)

The plant began this inspection period in power operation (Mode 1). On February 28, 1988, at approximately 11:49 a.m., a reactor trip occurred due to high Reactor Coolant System (RCS) pressure (see paragraph 7.a for details on the reactor trip). Following troubleshooting activities performed on the main feedwater and turbine trip systems, a plant startup was performed and the reactor was taken critical at 10:05 p.m. on March 2, followed by the resumption of power operation at 11:05 p.m. On March 7, the plant was taken off line to perform additional maintenance activities on the main feedwater system. These maintenance activities were completed : on March 8 and power operation was resumed at 4:20 a.m. The plant ' remained in power operation for the remainder of this inspection period, Shift Logs and Facility Records (71707) The inspector reviewed records and discussed various entries with operations personnel to verify compliance with the Technical Specifications (TS) and the licensee's administrative procedure The following records were reviewed: Shift Supervisor's Log; Reactor Operator's Log; Equipment Out-0f-Service log; Shif t Relief Checklist; Auxiliary Building Operator's Leg; Active Clearance Log; Daily Operating Surveil-lance Log; Work Request Log; Short Term Instructions (STI); and Selected Chemistry / Radiation protection Log In addition to these record reviews, the inspector independently verified clearance order tagout No violations or deviations were identified, Facility Tours and Observations (71707) Throughout the inspection period, facility tours were conducted te observe operations and maintenance activities in progress. Some operations and maintenance activity observations were conducted during backshif ts. Also, during this inspection period, licensee meetings were attended by t'.e inspector to observe planning and managemer.t activitie =-

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The facility tours and observatiors encompassed the following areas: security perimeter fence; control room; emergency diesel generator room; auxiliary building; intermediate building; battery rooms; and, electrical switchgear room During these tours, the following observations were made:

(1) Monitoring Instrumentation -

The following instrumentation a nd 'o r indications were observed to verify that indicated parameters were in accordance with the TS for the current operational mode: Equipment operating status; area atmospheric and liquid

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radiation monitors; electrical system lineup; reactor operating parameters; and auxiliary equipment operating parameter No violations or deviations were identifie (2) Safety Systems Walkdown (71710) - The inspector conducted a walkdown of the Decay Heat Closed Cycle Cooling (DC) system to verify that the lineup was in accordance with license require-ments for system operability and that the system drawing and procedure correctly reflected "as-built" plant condition No violations or deviations were identifie (3) Shift Staffing (71707) - The inspector verified that operating shift staffing was in accordance with TS requirements and that control room operations were being conducted in an orderly and professional manner. In addition, the inspector observed shif t turnovers on various occasions to verify the continuity of plant status, operational problems, and other pertinent plant informa-tion during these turnover No violations or deviations were identifie (4) Plant Housekeeping Conditions (71707) - Storage of materials and components, and cleanliness conditions of various areas through-out the facility were observed to determine whether safety and/or fire hazards existe No violations or deviations were identifie (5) Radiological Protection Program (71709) - Radiation protection control activi+1es were observed to verify that these activities were in conformance with the facility policies and procedures and in compiiance with regulatory requirement These observa-tions included:

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Selected licenser conducted surveys;

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Entry and exit from contaminated areas including step-off pad conditions and disposal of contaminated clothing;

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Area postings and controls;

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Work activity within radiation, high radiation, and contaminated areas;

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Radiation Control Area (RCA) exiting practices; and,

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Proper wearing of personnel monitoring equipment, protec-tive clothing, and respiratory equipmen Area postings were independently verified for accuracy by the inspector. The inspector also reviewed selected Radiation Work Permits (RWPs) to verify that the RWP was current and that the controls were adequat The implementation of the licensee's As low As Reasonably Achievable (ALARA) program was reviewed to detqrmine personnel involvement in the objectives and goals of the progra No violations or deviations were identifie (6) Security Control (71881) - In the course of the monthly activities, the inspector included a review of the licensee's physical security progra The composition of the security organization was checked to insure that the minimum number of guards were available and that security activities were conducted with proper supervisio The performance of various shifts of the security force were observed in the conduct of daily activities to include: protected and vital area access controls; searching of personnel, packages, and vehicles; badge issuance and retrieval; escorting of visitors; patrols; and compensatory post In addition, the inspector observed the operational status of Closed Circuit Television (CCTV) mcnitors, . the Intrusion Detection system in the central and secordary alarm stations, protected area lighting, protected and vital area barrier integrity, and the security organization interface with operations and maintenance.

' No violations or deviations were identifie (7) Fire Protection (71707) - Fire protection activities, staffing and equipment were observed to verify that fire brigade staffing was appropriate and that fire alarms, extinguishing equipment, actuating controls, fire fighting equipment, emergency equip-ment, and fire barriers were operabl +

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. (8) Surveillance (61726) - Surveillance tests were 'observ?d to verify that approved procedures were being used; qualified personnel were conducting the tests; tests were adequate to

! verify equipment' operability; calibra*ed equipment was utilized; and TS requirements were fellowe Tha followir.g tests were observed atd/or data reviewed: 4 Sp-110, Reactor Drotection System Fupctkepal Testing;

 -SP-192,HighDensityRackPoisopSampling;     .
 -SP-317,RCSystdr.katerInventoryBalance;
 - SP-340A, "A" Train ECCS Pump & Valve Operability;   I
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 - SP-358B, Operations ES Monthly A;tuation Logic    :

) Functional Test #2;

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 - SP-433, In-Core NeutroniDetectors Channel    '
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 - PT-137, BSP-1A Alternate Seal Water Supply &  l,4 ff Cyclone Separator Flow Adjustmen ,
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No violations or deviations were identifie i t ? . * i' y I (9) Maintenance Activities (62707) - The inspector obstev vrid maintenance activities to vi;rify .that correct (qui p. tent

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clearances were in effect; fr'rK requests and fire ' prevention - ! work permits, as required, e,e re issued and being followed; l l quality control personnel were availtble for inspection  ! activities as required; and TS requirements were being followed.

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Maintenence was observed andidrk packages were reviewed for the followir.g maintenance activities: ,

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Troubleshoo d ing er the control switch for valve FWV-31; j .

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Troubleshoothgf ud ' repair of the Engiceered 3afeguards , i (ES),t$st status light for valve SWV-12 in accordancs with ! procedures MP-531, Troubleshooting Plant Equipment, and l l 4 SP-356, Operations ES Refueling Manual Actuatian Channel Functional Test for AB Isolation and Cooling; i

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! - Replacement and calibration of steem generator level  ; I trensmitter SP-30-LT in accordance with procedures MP-531,  ;

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SP-111, Valve Lineup Verification for Critical Instrumenta-tinn, and SP-193, EFIC Transmitters Channel Calibration; s  :

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Q  ! Mi; ' - Troubleshooting of Reactor Protection System (RPS) Channel !

/   "0" high power and power /flot; trips in accordance vith !
' 4t#   V procedures MP-531, and SP-110, Reactor Protective System 4    Functional Testing; and,   !
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Disassembly and reassembly of main feedwater block vake l

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   't FWV-29 in accordance with procedures MP-402, Maintenance ot N
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l (10), Pipe Hangers and Seismic Restraints (71707) - Several pipo :

   ' hangers and seismic restraints (snubbers) on safety-related systems were observed to insure that: fluid levels were

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adequate and no leakage was evident, . restraint settings were appropriate, and anchoring points were not bindin No violations or deviations were identifie P ' Review of Licensee Event Reports (92700) and Nonconforming Operations Reports P 1707) Licensee Event Reports (LERs) were reviewed for potential generic impact, to ' detect trends, and to determine whether corrective actions

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 'e reviewed as they occurred to determine if the TS were satisfied. LER
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88-03 was reviewed in accordance with the current NRC Enforcement ! policyandwijlremainope l (Open) LER 88-03: This LER reported that a surveillance procedure !

was not adequate to implement the 31 day containment integrity i

verification required by TS 4.6.1.1. During a quality programs r audit, the licensee discovered that four manual containment isolation ;

i valves were not being verified closed every 31 days as requirec. The r licensee maintains these valves in the locked closed posit %n, and [ the valvet have been documented to be in the correct position on a ;

quarterly basis by a separate surveillance orocedure. The licenree i has subsequently revired procedure SP-341, Monthiy Containment r Integrity Check, to include the four valves so that they are [ documented as locked closed on a monthly basi This matter is !

-   considered to be a licensee identified violation in which adequate ,
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corrective action was taken to prevent recurrenc ! ' The licensee is also considering enhancements to their TS amendment t . review process to help prevent recurrence of this even The LER !

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will reeain open pending completion of these enhancement ,,

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7 The inspector reviewed Nonconforming Operations Reports (NCORs); to <

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verify tne following: TS are complied with, corrective actions as identified in the reports or during subsequent . reviews have been accomplished or cre being pursued for completion, generic items are identified and reported as required by 10 CFR Part 21, and items are >

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reported as required by T /1 All NCORs were reviewed in accordance with the current NRC Enforce-ment Polic NCOR 88-37 reported that several safety related instruments and

j: instruments used in TS surveillance procedures had exceeded the required calibration frequency. The licensee identified this problem through the use of a computerized preventive maintenance program (PM-200) which schedules instrument calibration due dates and identifies which instrumentation has exceeded the due dat The licensee has performed a preliminary evaluation of this instru-mentation and has determined that although some of these instruments are located in safety related systems, they do not perform a safety function. The licensee is presently performing a detailed evaluation of this event to determine the effect this instrumentation may have on safety system function and corrective action necessary to prevent recurrence. This item is considered to be unresolved pending the inspector's review of the licensee's completed detailed evaluatio Unresolved Item (302/88-06-01): Review the licensee's detailed evaluation of the effect instrumentation which exceeded the required calfbration frequency may have on safety system functio . Design, Design Changes and Modifications (37700)

Installation of new or modified systems were reviewed to verif/.that the - changes were reviewed and approved in accordance with 10 CFR 50.59, that the changes were performed in accordance with technically adequate and , approved procedures, that subsequent testing and test results met ' acceptance criteria or deviations were resolved in an acceptable manner, and that appropriate drawings and facility procedures were revised as necessary. This review included selected observations of modifications and/or testing in progres The inspector reviewed modification TMAR 86-03-04-07, Temporary Modifica- * ' tion to Inverters-480 VAC Input, and observed the performance of func-tional test procedure TP#1 for this .77dificatio No violations or deviations were identified.

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8 Nonroutine Event Followup (93702)

         ' On February 28 at approximately 11:49 a.m., a reactor trip from approximately 55% power occurred due to high Reactor Coolant System (RCS) pressure. During a decrease in power, a feedwater transient occurred when the "B" main feedwater block valve (FWV-20) failed to close -properly. Although this block valve indicated closed, actual valve position was approximately 17% ope The feedwater flow through this partially open valve generated -a feedwater flow error signal in the Integrated Control System (ICS) which responded by closing the "B" side feedwater control valves to reduce feedwater flow. In an attempt to stop this feedwater transient, operators opened the feedwater crossover valve (FWV-28) to the "A" main feedwater train. This action resulted in the automatic full closure of valve FWV-29 and in conjunction with the already closed feedwater control valves, resulted in the underfeeding of the "B" steam generator and subsequent rapid increase in RCS temperature and
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pressure which was followed by the reactor tri During this event, the main turbine did not automatically trip as expected upon a reactor trip and attempts to manually trip the turbine from the control room were also unsuccessful. Control room operators opened the generator output breakers, shut the Main Steam Isolation Valves (MSIV) and dispatched an operator who .lly tripped the main turbine. .This action was effective in se ing the main turbine and prevented an excessive plant cooldow , The opening of the generator output breakers automatically closed the

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steam supply to the main feedwater pumps which secured feedwater flow to the steam generators. A low steam generator water level signal actuated the emergency feedwater system which supplied the necessary feedwater to stabilize plant condition The root cause for this event was the failure of a yoke nut on the motor operator for valve FWV-2 This failure allowed the operator limit switches and indication to be offset from actual valve positio The failure of the main turbine to trip was due to a faulty trip solenoi These failures were examined by the Regi.n II - Engineering Branch during a March 8-11, 1988 inspection, and will be detailed in NRC Inspection Report 50-302/88-0 < The inspector reviewed the licensee's post trip review and restart justification and also reviewed work packages associated with the

'"   replacement of the turbine trip solenoid and troubleshooting of valve FWV-2 L No violations or deviations were identified, On March 1,1988, prior to increasing reactor pressure to normal operating pressure, the Group 1 control rods were manually tripped from the main control board to prevent an automatic tri After

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clearing pressure limitations, an attempt to shut the Control Rod Drive (CRD) breakers was made. The "A" CRD breaker would not shu Troubleshooting of this problem revealed a faulty relay in the CRD power supply. This relay was subsequently replaced and the breaker functionally tested satisfactor This event was similar to an event which occurred on July 2,1987, discussed in NRC Inspection Report 50-302/87-17 (item IFI 302/87-17-03), in which the "B" CRD breaker could not be re-close Troubleshooting of the failure for this CR0 breaker to close did not identify the failure mechanism for this problem because the failure mode could not be recreate The inspector discussed these two breaker failures with licensee personnel who agreed to review this matter to determine if similar or generic causes were involve Inspector Fol l o.<up Item (302/88-06-02): Review the licensee's investigation into similar causes for failure of CRD breakers to re-close.

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