IR 05000302/1990021

Insp Rept 50-302/90-21 on 900602-0706.No Violations Noted. Major Areas Inspected:Plant Operations,Security,Radiological Controls,Ler,Facility Mods & Licensee Action on Previous Insp Items

ML20056A922
Person / Time
Site:	Crystal River
Issue date:	07/27/1990
From:	Bradford W, Crlenjak R, Holmesray P, Vias S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20056A920	List: IR 05000302/1990021 ML20056A919
References
50-302-90-21, NUDOCS 9008100108
Download: ML20056A922 (12)

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km neep UNITE 3 STATES ' l NUCLEAR REGULATORY COMMIS$10N

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Report No: ~ 50-302/90-21 i licensee: Florida Power Corporation 3201 34th Street, South St. Petersburg, FL 33733 Docket No: 50-302 License No.: DPR-72 l Facility Name: Crystal River 3

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Inspection Conducted:-June 2 - July 6, 1990 Inspectors: tb 7!2b 9D

..Ho1Mes-Ray, Senior Resident Inspector Dat.e - S' gned N 7f?4f9D a6 ford, Resident Inspector Dath Signed

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Approved by: ,/ . nN R. Cflenjak,5ecioh ChyT D6te 5fgiied DivisionofReactorProjects ,

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SUMMARY ,

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Scope: This routine inspection was conducted by two resident inspectors in the areas of plant operations, security, radiological controls, Licensee -Event

' Reports, facility modifications, and -licensee action on previous inspection

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items. . Numerous facility . tours were conducted and facility operations--

observed. Some of these tours and observations were conducted on back-shift l Results: . In the areas inspected, violations or deviations were not identifie !

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REPORT DETAILS Persons Contacted Licensee Employees

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• Boldt, Vice President Nuclear Production

• J. Brandely, Manager, Nuclear Integrated Planning

• M. Collins, Nuclear Safety and Reliability Superintendent

• L. Floyd, Nuclear Document Control Supervisor

• A. Geiston, Supervisor. Site Nuclear Engineering M rvices

• P. Genoa, Nuclear Support Specialist Chemistry and k#ation Protection Services

• B. Hickle Manager, Nuclear Plant Operations

• J. Holton, Senior Nuclear Results Engineer

• H Koon, Nuclear Maintenance Superintendent

• J. Kraiker, Nuclear Management Support Superintendent

• G. Longhouser, Nuclear Security Superintendent

• W. Marshall, Nuclear Operations Superintendent P. McKee, Director, Nuclear Plant Operations

• S. Robinson, Nuclear Chemistry and Radiation Protection Superintendent

• V. Roppel Manager, Nuclear Plant Maintenance

• W. Rossfeld, Manager, Nuclear Compliance

• F. Sullivan, Manager, Nuclear Plant System Engineering

• R. Widell, Director, Nuclear Operations Site Support

• M. Williams, Nuclear Regulatory Specialist

• K. Wilson, Manager. Naclear Licensing Other lice.isee employees contacted included office, operations, engineer'.ng, maintenance, chemistry / radiation and corporate personne * Attended exit interview Acronyms and initialisms used throughout this report are listed in the last paragrap . Review of Plant Operations (71707)

The start up from Refueling 7 commenced on June 20, 1990 and the reactor was critical at 0520 on June 21. After completion of scheduled testing, the generator output breakers were closed at 0541 on June 23. The plant was taken off line on June 25 to repair a turbine backup seal oil pump and returned to iower operations at 0321 on June 26 and continued power

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operation to toe end of this report period, Shift Logs and Facility Records 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 . .

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The following records were reviewed:

Shift Supervisor's Log; Reactor Operator's Log; Equipment Out-Of-Service Log; Shift Relief Checklist; Auxiliary Building Operator's Log; Active Clearance Log; Daily Operating Surveillance Log; Short Term Instructions (STI); and Selected Chemistry / Radiation Protection Log In addition to these record reviews, the inspector independently verified clearance order tag-oJts, b. Facility Tours and Observations Throughoui, the inspection period, facility tours were conducted to observe operations and maintenance , activities in progress. Some operations and maintenance activity observations were conducted i during back-shif ts. Also, during this inspection period, licensee L meetings were attended by the inspector to observe planning and management activitie The facility tours and observations encompassed the following areas:

security perimeter fence; control room; emergency diesel generator room; auxiliary building; intermediate building; battery rooms; and, electrical switchgear rooms.

l The inspectors also observed conditions in the following areas:

L (1) Monitoring Instrumentation

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The following instrumentation and/or indications were observed 1 to verify that indicated parameters were in accordance with the l TS for the current operational mode:

Equipment operating status; area atmospheric and liquid radiation monitors; electrical system lineup; reactor operating parameters; and auxiliary equipment operating parameters.

! (2) Shift Staffing I

l The inspector verified that operating shift staffing was in l accordance with TS requirements and that control room operations j were being conducted in an orderly and professional manner. In addition, the inspector observed shif t turnovers on various

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occasions to verify the continuity of plant status, operational L problems, and other pertinent plant information during these turnover (3) Plant Housekeeping Conditions i

Storage of material and components, and cleanliness conditions of various areas throughout the facility were observed to

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determine whether safety and/or fire hazards existed.

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A coordinated, all shops effort to clean up the plant has been

underway since the completion of the outage. A prioritized approach by plant area was developed to focus the cleanup efforts. The areas that have been worked are now in a much improved state of cleanliness. This cleanup program continue L (4) Radiological Protection Program

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Radiation protection control activities were observed to verify that these activities -were in conformarce with the facility policies and procedures, and in compliiance with regulatory requirement These observations included:

Entry to and exit from contaminated areas, including

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step-off pad conditions and disposal of contaminated clothing;

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- Area postings and controls;

- Work activity within radiation, high radiation, and L

contaminated areas;

- Radiation Control Area (RCA) exiting practices; an Proper wearing of personnel monitoring equipment, protective clothing, and respiratory equipmen Area postings 'were independently verified for accuracy by the-I inspector. The inspector also reviewed selected Radiation Work Permits (RWis) to verify that the RWP was current and that the l

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controls wert adequat (5) Security Contr)1  ;

In the course )f the monthly activities, the inspector included a review of the licensee's physical security program. The l

performance of various shifts of the security force was observed l 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 1 visitors; patrols; and compensatory posts. In addition, the inspector observed the operational status of Closed Circuit Television (CCTV) monitors, the Intrusion Detection system in the central and secondary alarm stations, protected area'

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lighting, protected and vital area barrier integrity, and the 1 security organization interface with operations and maintenance. l (6) Fire Protection Fire protection activities, staffing and equipment were observed to verify that fire brigade staffing was appropriate and that

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H 4 fire alarms, extinguishing equipment, actuating controls, fire fighting equipment, emergency equipment, and fire barriers were ,

operabl The inspectors, as a result of routine plant tours and various operational and outage observations, determined that the general plant and system material . conditions were being satisfactorily maintained, plant security program was being effective, and that the overall performance of plant operations was good. No violations or deviations were identifie . ReviewofMaintenance(62703)andSurveillance(61726) Activities Surveillance tests were' observed to verify that approved procedures were being used; qualified personnel were conducting the tests; tests were adequate to verify equipment operability; calibrated equipment was utilized; and TS requirements were followe '

i The following tests were observed and/or data reviewed:

- SP-103, Moderator Temperature Coefficient Determination at

Startup Following Refueling; l

- SP-145 EFIC Response Time Test;

- SP-157A Meteorological System Daily Check;

- SP-312A, Heat Balance Calculation; )

- SP-324, Containment Inspection;

- SP-333, Control Rod Exercises;

- SP-340D, B Train ECCS RWP-3B, DCP-1B and System Valve l Operability Test; L

- SP-343, MSIV Partial Stroke Test; I

- SP-347, ECC5 Flaw Path Operability Verification;

- SP-415, Rev. 7e Transfer From Preferred Offsite Power Source J to Alternate Offsite Source and Return to Preferred Offsite Source; l

- SP-417, Refueling Interval Integrated Plant Response to an l

Engineered Safeguards Actuation; l- - SP+419 Turbine Overspeed Trip; I - SP-421, Reactivity Balance Calculation;

- SP-640A, EFP-1 Full Flow Test;

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- SP-640B, EFP-2 Full flow Test; ,

- SP-902, 4.16 KV ES Bus Under Voltage Trip Relay Calibration; ,

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- PT-112, Rev. 6, Hot Zero Power Regulating Rod Group Worth and i I Differential Boron Worth Measurement; and

- PT-340 Voltage Drop Validatio In addition, the inspector observed maintenance activities to verify that .

l correct equipment clearances were in effect; work requests and fire

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preventien work permits, as required, were issued and being followed'

l-quality control personnel were available for inspection activities as l'

l required; and, TS requirements were being followe .

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Maintenance was observed and work packages were reviewed for the following maintenance activities: -

- PT-110 Controlling Procedure For Zero Power Physics Testing; j

- Energized new start up transformer; and, 1

- Main feedwater pumps turbine disassembly and reassembl l For the surveillance and maintenance activities observed and listed above, ;

the inspectors determined that the work was performed in a satisfactory manner in accordance with procedural requirements and met the requirements of the Technical Specificatio No violations or deviations were identifie Safety Systems Walkdown (71710)

The inspector conducted a walkdown of portions of the Raw Water (RW) and Sea Water (SW) system'., to verify that the lineup was in accordance with license requirement * fu system operability and that the system drawing and procedure correctly reflect "as-built" plant condition l ReviewofLicenseeEventReports(92700) Licensee Event Reports (LERs) were reviewed for potential generic impact, to detect trends, and to determine whether corrective actions appeared appropriate. Events that were reported imediately were ;

reviewed as they occurred to determine if the TS were satisfie .l LERs were reviewed in accordance with the current NRC Enforcement i Policy. LERs 88-20, 88-22, and 88-23 are close (1) (Closed) LER 88-20: Indeterminate cause renders safety related snubber inoperable longer than allowed by technical specification The licensee's corrective action consisted of reinstallation of the hydraulic snubber under WR-102020. Maintenance Procedure (MP-120) was revised and is documented under Corrective Action Assignment form (CAA) N-88-125-01 dated 11/3/8 Other procedures which could have similar requirements for remove: and replacement of interferences were reviewed under CAA N-88-425-03 dated 11/3/8 (2) (Closed) LER 88-22: Failure to revise procedures to reflect a ,

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change in actuation setting leads to isolation of the cecay heat removal syste The licensee initiated corrective actions which includes, (1)

revision to operating procedures to accurately incorporate the Automatic Closure Initiation (ACI) setting, (2) evaluation by

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system engineering to determine ACI instrument string error, (3)

l evaluation by engineering to detemine the need for an alarm when pressure approaches the ACI setting, and (4) counseling of l personnel involved in this event. This corrective action is documented on CAA N 88-134-01, CAA N 88-134-02 CAA N 88-134-03, i and letter from Marshall to Rossfeld dated 11/18/8 !

(3) (Closed) LER 88-23: Miscomunication of requirements resulted j in technical specification violation and failure to satisfy NRC- ;

requirement I The licensee has completed a modification (MAR-88-11-05-01, ;

i Upgrade pressurizer heater power supply). This MAR moved the I

back up power supply for 480V reactor auxiliary bus 3A from the l' 480V plant auxiliary bus to the 480V engineered safeguards bus

! 3A. This modification provides the capability to manually align l up to three 126KW groups of "on-off" pressurizer heaters to each ,

i redundant emergency power sources for natural circulation .

cooling during loss of offsite powe j No violations or deviations were identified.

I Evaluation of Licensee Self-Assessment Capability (40500)

l j On June 13, 1990, the inspector attended a Plant Review Committee (PRC)

meeting. A properly qualified quorum was present plus several engineers were there to make presentations on subjects on the agenda. The meeting was conducted in an orderly manner with each topic thoroughly discussed.

l The short term resolution of the high energy line break in the ,

i intermediate building and the short term resolution _of the reactor building flooding issue were presented to the PRC by Florida Power '

Corporation (FPC) licensing personne ;

The overall impression of the PRC meeting was one of a professionally conducted meeting that properly covered the agenda topics, t On May 5,1990, the inspector attended meeting Number 195 of the Nuclear General Review Committee (NGRC). Subcomittee reports were presented on

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significant events and LERs, safety evaluation, audit program, technical specification changes, environmental monitoring, violations, and corporate review, l

The committee reviewed 12 LER's, 3 security event reports, 2 rpecial

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reports to the NRC, 2 unplanned operating event reports, 7 revisions to LER's and the meeting minutes of a risk assessment team. The comittee

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ascertained that there were no unreviewed safety questions. Corrective l

actions for the above items were determined to be adequate with no adverse l-trends were identified.

The plant manager reviewed 27 " Readiness for Restart" items with the L comittee. These items were discussed in detail.

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- 7 PlantStartupFromRefueling(71711)

The inspectors reviewed documentation and inspected selected reactor plant systems which had received modifications and/or maintenance activities during the refueling outage. The inspectors observed and reviewed startup tests, heatup tests, approach to criticality and core physics tests to detemine that testing was in accordance with technically adequate and approved procedures, technical specification requirements were met, and that test personnel were qualified to perform the tests. System inspections were conducted to verify proper return to service prior to startu The following systems were observed:

- 3A and 3B diesel generators upgrade;

- Anticipated Transients Without Scram (ATWS) Diverse Scram System (DSS) and ATWS Mitigation System Actuation Circuitry (AMSAC);

- New offsite pcwer transformer; and

- 3A and 3B battery replacemen The testing observed included the following:

- SP-102, Control Rod Drop Time Tests;

- SP-103, Moderator Temperature Coefficient Determination at Startup Folicwing Refueling Outage;

- SP-421 Reactivity Balance Calculation; and

- SP-333, Control Rod Exercis Results:

The inspectors found tive systems to be in compliance with the plant modification packages and post modification testing was satisfactor The above testing activities were performed in a satisfactory manner and met the requirements of the technical specificatio The meeting was conducted in a professional manner with adequate time allowed for addressing staff questions and concern . Licensee Action on Previously identified Inspection Findings (92702 &

92701) (Closed) IFI 88-31-02, Review the Licensee's Testin Pressu'e 6 cross the Emergency Diesel Generator (EDG)g of Differential Fan Blade The modification to strengthen the power take off that drives the Emergency Diesel Generator fan was completed during Refuel 7 by MAR 80-01-61. The history of the cooling fan and its drive components shows no failure ..

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, (Closed) IFl 302/88-34-03, Follow-up of RECA Resolution for SWV-10 Check Valve Slammin The-check valve in question (SWV-10), was again opened and inspected during Refuel 7 and no significant damage was observed. A MAR has been written to install an adjustable back stop in SWV-10 as an upgrad This MAR (8906-21-01) provides a tracking vehicle therefore this IFI is close (Closed) IFI 302/88-34-02, Torque switch electrical bypass circuit for safeguard service valve motor This item was scheduled for completion in L fuel 7 but was rescheduled into Refuel 8. MAR 87-03-13-02 was written to perform

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the work and also to remove the space heaters from the valve operators. This item is closed since this MAR provides a tracking ,

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vehicl (Closed) Violation 50-302/89 2003, Plant Operations With Station Battery 'B' Inoperabl The 1989 problem concerned a discrepancy in the 'B' battery load profil The problem was caused by an incorrect anal) is assumption

'for load turn-on times used in the original development of load profile In the licensee's response to the violation, dated-December 28, 1989 FPC stated that they have re-validated the timing i sequences and duration of all major loads on both ' A' and 'B' train The battery 'B' loads were redistributed to a more balanced condition. The 'A' battery loads were already in a balanced condition. TBP-10 was removed from the 'B' battery to ensure that the test profile enveloped the installed configuration. Full compliance was achieved prior to the start up from the October 1989, outage. FPC ba', increased the emphasis on attention to detail and

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the need fu niidation of assumptions in the performance of design .

cctivitie The inspector reviewed and inspected this event in the follow-up of LER 89-32, Design Engineering Deficiency Results in Station Battery i Inoperability and Operation Prohibited by Plant Technical Specifications, issued September 29, 1989. The event was discussed-and the LER was closed in Inspection Report 50-302/89-25, issued on December 12, 1989. In the review of the event the licensee committed to replacing both banks of Station Batteries during Refuel The inspector verified that the batteries were installed and that Surveillances SP-522 and SP-523 were completed on May 15, 1990. This item is closed, (Closed) Violation 50-302/89-24-01, Plant Operations with One Inoperable Raw Water Pump, and (Closed) Violation 50-302/89-24-02, Inadequate RWP-2B Post Maintenance Test

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The above two issues were discussed in LER 89-30; Delivery, Installation, and Acceptance of Incorrect Impeller Leads to Engineering Safeguards Pump Inoperability. Operation Outside Plant Design Basis, and Plant Shutdown, issued on September 26, 1989, and supplemented on December 22, 1989. The Resident Inspector reviewed and closed the LER in Inspection Report 50-302/90-09. The licensee's corrective actions consisted of installation of the repaired and refurbished original impeller. This work was documented under WR 250311. The pump was satisfactorily tested under SP-344B, Rev.13, NSCC B-Train Quarterly Operability Surveillance, and returned to service. All purchases of safety related equipment is now receipt inspected under QPSR 89-40. Pump impellers stored in the warehouse have been verified to be the correct impellers with proper dimensions and physical characteristic The above two items in conjunction with items identified in Inspection Report 50-302/89-200, issued on August 14, 1989, were considered for Escalated Enforcement Actio An Enforcement Conference was held in Region 11 on September 28, 1989. A Severity Level !!! Violation in two parts, with a Proposed Imposition of Civil Penalty of $50,000 was issued on December 1, 1989, (EA 89-172). Part

'B' of the Notice of Violation pertained to the above two issue The Licensee respondeo to the Severity Level 111 violation on January 26, 1990. FPC denied both parts of the violation, asking that the Notice of Violation be withdraw '

Based on further review of Licensee submittals by the Commission, it was determined that no further actions were deemed appropriate. In a J letter dated April 27, 1990, from the Comission to Florida Power Corporation, the Notice of Violation and Proposed Imposition of Civil Penalty (EA-172) were witNrawn. Therefore, this matter, to include the above two items, is considered closed, (Closed) Tl 2500/20, inspection to Determine Compliance with ATWS Rule, Rule 10 CFR 50.6 To mitigate an Anticipated Transient Without Scram (ATWS) two functional subsystems were installed. The Diverse SCRAM System (DSS)

provides a reactor trip signal on high reactor Mitigation System Actuation Circuitry (AMSAC) pressure limits the and the ATWS pressure rise in the event that the control rods do not insert when require Installation and functional testing of both subsystems was 4 accomplished in Refuel 7 (1990). During startup from Refuel 7 the system was placed in bypass and monitored for unwanted trip signal None were observed and the system was armed. The system is currently operationa Prior to startup, plant modification training was held for all operator This training included the ATWS systems. Also the drawings in the control room were updated to shcw the system .

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The DSS and the AMSAC both have the design flexibility that provides for channel testin Also AMSAC is automatically bypassed below a nominal reactor power of 25 percent. Indication of OSS or AMSAC in bypass is provided in the main control roo Af ter a trip of DSS or AMSAC, operator action is required to reset the system. This function is achieved through seal in contact All new equipment installed for DSS or AMSAC is in a mild environment with no high energy line break concern The ATWS system is classified as Non-Safety with a special code key established to designate that it is ATWS equipment subject to the QA guidance of Generic Letter 8S-06. Diversity from the reactor trip system is require No violations or deviations were identifie . ExitInterview(30703)

The inspector met with licensee representatives (denoted in paragraph 1)

at the conclusion of the inspection on July 9, 1990. During this meeting, the inspector summarized the scope and findings of the inspection as they are detailed in this repor The licensee representatives acknowledged the inspector's comments and did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspectio . Acronyms and Abbreviations ACI - Automatic Closure Initiation AFW - Auxiliary Feedwater System AMSAC - ATWS Mitigation System Actuation Circuitry ATWS - Anticipated Transient Without Scram CAA - Corrective Action Assignment CCTV - Closed Circuit Television CFR - Code of Federal Regulations ECCS -EmergencyCoreCoolingSystem(s)

EDG - Emergency Diesel Generators EFIC - Emergency feedwater Initiation and Control EFP - Emergency Feedwater Pump ES - Emergency Safeguard FPC - Florida Power Corporation FSAR - Final Safety Analysis Report IFl - Inspector Followup Item ISI - Inservice Inspection IST - Inservice Test KV - Kilovolt KW - Kilowatt

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LER - Licensee Event Report MAR - Modification Approval Record MP - Maintenance Procedure MSIV - Main Steam Isolation Valve NGRC - Nuclear General Review Committee NRC - Nuclear Regulatory Commission PM - Preventive Maintenance PRC - Plant Review Committee PT - Performance Testing QC - Quality Control QA - Quality Assurance RCA - Radiation Control Area RCS - Reactor Coolant System RO - Reactor Operator RW - Raw Water RWP - Radiation Work Permit

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S/G - Steam Generator SP - Surveillance Procedure STI - Short Term Instruction SW - Sea Water TBP - Turbine Back-up Pump TS - Technical Specification V - Volt WR - Work Request l