IR 05000302/1989023
| ML19325E978 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/25/1989 |
| From: | Bradford W, Crlenjak R, Holmesray P, Tedrow J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19325E975 | List: |
| References | |
| 50-302-89-23, NUDOCS 8911130134 | |
| Download: ML19325E978 (11) | |
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p ath UNITED ST ATES
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'o NUCLEAR REGULATORY COMMISSION I
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REGION H g
101 MARIETTA STREET,N.W.
ATLANTA, GEORGI A 30323 h
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Report No.:
50-302/89-23
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Licensee:
Floriaa Power Corporation 3201 34th Street, South
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St. Petersburg, FL 33733
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Docket No.:
50-302 License No.: DPR-72 Facility,Name:
Crystal River 3 Inspection Conducted: September 9 - October 6, 1989
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'O to ka9 Inspectons:
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f.HolmeT-Ray,SeniorResidentInspector Date Signed S3.Vi43 iolzsist J. Tedrow, Resident Inspector Date Signed E
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- p.Bradford,ResidentInspector
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Approved by:
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_/0b,.r!9at R. Crlenjak, Section Chief Date'. Si cfned Division of Reac';or Proje::t=
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SUMMARY
Scope:
i This routine inspection was corducted by three resident inspectors in the areas of plant operations, securitv, radiological controls, Licensea Event Reports and Nonconforming Operations Reports, facility modifications, and licensee action on previous inspection items.
Nur.ierous facility tours were co:ide.ted and facility operations observed.
Some of these tours and observations were conducted on backshifts.
Results:
f One violation of inadequate procedures was identified in paragraph 2.b.
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i REPORT DETAILS 1.
Persons Contacted Licensee Employees J. Alberdi, Manager, Nuclear Site Support
- W. Bandhauer, Superintendent, Nuclear Operations
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"G. Becker, Manager, Site Nuclear Engineering Services
- G. Boldt, Vice President Nuclear Production
- P. Breedlove, Nuclear Records Management Supervisor
"M. Collins. Manager, Technical Support, Acting
- J. Cooper, Superintendent, Technical Support R. Fuller, Senior Nuclear Licensing Engineer B. Hick 19, Manager, Nuclear Plant Operations
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- M. Jacobs, Area Public Information Coordinator
- A. Kazemfar, Supervisor, Radiation Support Services
- L. Kelly, Director, Nuclear Operations Training
- G. Longhouser, aoperintendent, Nucicar Surveillance
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W. Marshall, Nuclear Operations Superintendent
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- P. McKee, Director, Nuclear Piant Operations W. 'Neuman, Supervisor, Inservice Inspection (ISI)
- E. Renfro, Director, Nuclear Operations Materials and Controls
- S. Robinson, Superintendent, Nuclear Chemistry and Radiatic.
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Protection
- V. Roppel, Manager, Nuclear Plant Maintenance
- W. Rossfeld, Manager, Nuclear Compliance
- J. Russell, Senior Nuclear Fire Protection Specialist P. Skramstad, Superintendent, Nuclear Chemistry / Radiation Protection l
E. Welch, Manager, Nuclear Electrical / Instrumentation and Control
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Engineering Services i
- R. Widell, Director, Nuclear Operations Site Support
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- M. Williams, Nuclear Regulatory Spacialist
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"K. Wilson, Manager, Nuclear Licensing
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Other licensae employees contacted included office, operaticas, l~
engineering, maintenance, chemistry / radiation and corporate personnel.
l NRC Resident Inspectors
- P. Holmes-Ray, Senior Resident Inspector
- J. Tedrow, Resident Inspector
- W. Bradford, Resident Inspector Accompanying Personnel
- M. V. Sinkule, Chief, Reactor Projects Branch 2, Division of Reactor Projects l
- Attended exit interview l
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a, Shift Logs and Facility Records The inspector reviewed records and discussed various entries with optrations personnel to verify compliance with the Tecnnical Specifications (TS) and the licensee's administrative procedures.
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The following reccrds were reviewed:
f Shift Superviaor's Log; Reactor Operator's Log; Equipment Out-Of-Service Log; Shift Relief Checklist; Auxiliary Building Operator's Log; Active Claarance Log; Daily Operating Surveillance Log; Short Term Instructions (STI); and Selected Chemistry /Fe.diation Pratection Logs.
In addition to these record reviews, the inspector independently L
verified clearance order tagouts.
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No violations or deviations were identified.
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Facility Tours and Observations l
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Throughout the inspection period, facility tours were conducted to I
observe operations and maintenance activities 'in progress.
Some I
operations and maintenance activity observations were conducted
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during backshifts.
Also, during this inspection period, licensee l
meetings were attended by the inspector to observe planning and management activities.
.he 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.
On September 14, 1989, the inspector noted the manual sliding door was open leading from the auxiliary building compactor ronm on elevation 119 f t.
This door serves as one of the auxiliary 'uilding o
outside isolation doors.
The auxiliary building ventilation system is described in FSAR Section 9.7.2.1.f.
The design criteria states that filtered, and tempered outside air is supplied with a n.Inimum temperature of 60 degrees Fahrenheit (F).
The exhaust du:t system is designad to exhaust areas of low activity to higher activity.
The air is then directed through the auxilisry building main exhaust filter system.
If any outside doors in the auxiliary building are open the design criteria of the ventilation system is negated and the system may not fenction as designed.
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The inspector observed several people pass through the open door w thout closing the door even though the door is marked to "Closa the Door".
There are other doors leading from the Auxiliary Beilding which are clearly marked. The marking on these doors indicate that i
the door must not be 1 I' open' because the air flow will interfere with the auxiliary bcilding ventilation system.
The licensee's Radiation Pr -+s tion Procedure RSP-110
" Control of /uxiliars Building Rollup Jem s" addresses the control of large rollup doors. The control of cnis sliding door is not addressed.
Procedure RSP-110 " Control of Auxiliary Buildina Pollup Doors" is
inadequate in not addressing control of this noor.
This is the first example of a precedural deficiency, Viciation i
50-302/89-23-01:
Failure to Have Adequate Procedures.
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The licensee has initiated the following corre-tive action:
RSP-110 " Control of Auxiliary Building Rollup Doors" will be
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changed to include control of the sliding door;
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A sign has been placed at the sliding door to remind personnel
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that the door is to remain closed; Control of this door and the auxiliary building ventilation
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system has been discussed in Plant Monagement Meetings; Plant personnel have been cautioned concerning the sliding door;
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The hourly roving fira watch and the roving security officers
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are to pay particular attention to this door; and, l
A note will be placed in the Shift Supervisors log to remind
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I shift personnel of the importance of maintaining control of the sliding door.
r On September 18, 1989 the inspector found several aerosol cans which L
were marked as "fiammable to extremely flammable". There were other
- containers of materials which were markrx as flammable. The aerosol cans did not have the protective cap on the cans. This matcrial was found in the auxiliary building on elevation 95 ft. in the Sea Water Room.
The auxiliary building is safety related.
Two flammable aerosol cans were on a tool / work area bench by 2B Raw Water Pump.
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The other containers were in a large open metal tool chest or the west wall by nuclear service water heat exchanger. There was no work
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in progress in the area t' d the flammable material was found unattended.
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The program to control combustibles at CR-3 was identified as deficient in previous Quality Programs Audits. Each of these audits identify the r9 curring probitm.
In each case the understanding of the root cause by the licensee as well as corrective action to preclude recurrence of the violation has not been effective.
Nonconformance Report 02849, dated July 14, 1989 states "The
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Administrative measures for the control of transient combustibles are weak and previous activities to strengthen these controls through corrective action implementation have failed. The program to control transient combustibles appears to have been left to the Nuclear ' ire
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Protection staff when, in reality, there must be a plant wide program similar to that of the As Lou As Reasonably Achievable (A' ARA)
program."
In a response to NCR 02849 dated July 28, 1989, the licensee stated that a root cause analysis and a corrective action plan to pr9 vent recurrence will be completed by September 30, 1989 The inspectors will review this plan and the corrective action implementation.
Administrative Instruction AI-2200, "Guic'elines for handling, Use and Control of Transient Combustibles", dated September 11, 1987 describes the policies for handling and control of transient combustible materials, liquids and gases at Crystal River Unit 3.
The above procedure is deficient in that the violation was found to l
be recurring during the licensee Quality Programs Audits and also on l
September 18, 1989 by the Resident Inspector.
This is the second example of a procedural deficiency, Violation l
50-302/89-23-01, Failure to Have Adequate Procedures.
The inspectors also observed conditions in the following areas:
e (1) Monitoring Instrumentation
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The following instrumentation and/or indications were observed to verify that indicated parameters were in accordance with the TS iar the current operationa; mude:
Equipment operating tatus; area atmospheric and liquid radiation monitors; electricci system lineup; reactor operating parameters; and auxiliary equipment operating parameters.
No violations or deviations were identified.
(2) Shift Staffing The inspector verified that operating shift staffing was in accordance with TS requirements and that cor. trol room operations were t,eing conducted in an orderly ano professional manner.
In addition, the inspector observed s'ii f t turnovers on various
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i occasions to verify the cuntinuity of plant status, opvational
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problems, and other pertinent phnt information during these turnovers.
No violations or deviations were identified.
(3)' Plant Housekeeping Conditions
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Storage of niaterial and componer,ts, and cleanliness conditions of varicus areas throughout the facility were observed to determine whether safety and/or fire hazards existed.
Housekeeping was less than desirable. during this peried. The licensee is awcre and is actively correcting this problem.
In order to assure continued effort to maintain the plant in good physical condition, the licensee has assigned " Area Mothers". These persons are assigned a specific small area for
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which they are responsible.
Plant management will conduct periodic walkdowns and hold the Area Mother responsible for the condition of their area.
A training session was held which included picturer a: examples of unacceptable conditions.
No violations or deviations were ident'fied.
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(4) Radiologi.:al Protection Program Radiation protection control activities were cbserved to verify that these activities were in conformance with the facility policies and procedures, and in complianco with regulatory requirements. 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
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contarinated areas; Radiation Control Area (RCA) exiting practices; and,
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Proper wearing of personnel monitoring equipment,
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protective clothing, and respiratory equipment.
Area postings were independently verified for accuracy by the inspectnr. The inspector also reviewed selected Radiation Work Permits (RWPs) to verify that the RWP was current and that the controls were adequate.
No viciations or deviations were identified.
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b (5) 3ecurity Control
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r In the course of the monthly activities, the inspector ir.cluaed a review of the licensee's physical security program.
The performance of various shifts of the security force was 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 posts.
In addition, the inJpector observed the operational status of Closed Circuit Television (CCTV) monitors, the Intrusion Detection system in the central a r.d secondary alarm stations, protected area lighting, protected and vital area barrier integrity, and the security organization interface with operations and maintenance.
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No violations or deviations were identified.
(6)
Fire Protection 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 equipment, and fire barriers were operable.
No violations or deviations were identified.
3.
Review of Maintenance (62703) and Seeve111ance (61726) Activities Surveillance tests were observed to verify that approved procedures were being used; qualified personnel were conducting the tests; tests were adequate to veri fy equipment operability; calibrated equipment was utilized; and TS requirements were foilowed.
The following tests were cbserved and/or data reviewed:
- SP-301, Shutdewn Daily Surveillance Log;
- SP-3408, "B" Train ECCS Pump and Valve Operability;
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- SP-344A, Nuclear Services Cooling System "A" Train Operability;
- SP-345, Auxiliary Building Ventilation EFhaust System Monthly Test;
- SP-35-iB, Monthly Functional Test of the Emergency Diesel Generator EGDG-1B;
- OP-705, Emergency Power - DC System; and,
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- FP-302, New Fuel Assembly Unioadino, Inspection, Storage, and Container Reclosing.
In addition, the inspector observed maintenance activities to verify that correct equipment clearances were in effect; work requests and fire prevention work permits, as required, were issued and being followed; quality control personnel were available for inspection activities as required; and, TS requirements were being followed.
Maintenance was observed and we % packages were reviewed for the following maintenance activities:
WR 250311 in accordance with MP-150, Maintenance of Raw Water Pumps;
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MP-211, Installation of Diamond II Annubar and Eagle Eye Flow Meters;
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EQ' Inspection of Target Rock Valves in accordance with WR 114392, Tag
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- WSV-38; Main Feed Water Pump 3B impeller replacement; and,
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Condenser steam dump /alve MSV-14.
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No violations or deviations were identified.
4.
Safety Systems Walkdown (71710)
The inspector conducted a walkdown of the core flood tank syttem inside the containment building to verify that the lineup was in accordance with l
license requirements for system operability and that the system drawing
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and procedure' correctly reflect "as-built" plant condisions.
No violations or deviations were identified.
5.
Review of Licensee Event Reports (92700) and Nonconforming Operations r
Reports (71707)
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Licensee Event Reports (LERs) were reviewed for potential generic l
impact, to detect trends, and to determine whether corrective actions appeared appropriate.
Events that were reported immediately were reviewed as they occurred to determine if the TS wet e satisfied.
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LERs were reviewed in accordance with the current NRC Enforcement
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Policy.
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(1) (Closed) LER 87-17:
Tnis LER reported the TS t equired forced entry into the hot shutdown condition (Mode 4) due to the
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inoperability of the steam driven emergency feedwater pump.
This LER was previously discussed in NRC Inspection Report 50-302/87-28 and a supplemental LER was issued nn September 5, 1989.
The licensee has completed an analysis of this pump's
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capabilities et low steam system pressures and has issued a
l change to the TS (TSCR #171) to reflect this information.
(2)
(Closed) LER 89-11: This LER reported that the main sttam line containment wall penetration was not as described in the (FSAR).
The licensee has revised the FSAR (revision 12 dated July 1, 1989) to reflect the new steam generator tube rupture analysis.
b.
The inspector reviewed Nonconforming Operations Reports (FCORs) to verify the following:
TS arc complied with, corrective actions as identified in the reports or during subsequent reviews have been accomplished or are being pursued for complction, generic items are identified and reported as required by 10 CFR Part 21, cnd itams are reported as required by TS.
I All NCORs were reviewed in accordance with the current NRC Enforcement Policy.
No violatiores or deviations were identified.
6.
Resident Action Item 89-34 Reactor Operator License Verification (42700, 71707)
The inspectors reviewed the licensee's administrative Procedures to determine how the licensee controlled the work status of licensed I
operators who became disqualified to perform his work.
L The licensee's " Licensed Operator Requalification Training Program" l
TOP-203 Rev. 10, states in paragraph 4.7 that "the nuclear Operatians
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l Superintendent must be notified within eight hours of detcrmining that a licensed operator becomes disqualified for:
(1) failure of the annual l
written requalification exam; (2) unsatisfactory performance on Annual l'
Performanr1 Evaluation; (3) Overall unsatisfactory performance during the annual simulated operating exam; (4) overall unsatisfactory performance on annual walk through exam; and, (5) not performing licensed duties during the last calendar quarter. There is no administrative procedure j
stipulating that the Shift Supervisor on shift will be informed of the
disqualified operator.
There 6re no records kept in the control oom files that the oa duty shift supervisor could refer to for current status of licensed and non-licensed shift personnel.
The shif t crews at Crystal River 3 work together and train together.
These crews are a close knit group and may be aware of the status of each
member of the operating crew.
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Administrative Instruction AI-500, " Conduct of Operations", states that all licensed operators are required to inform the Nuclear Operations Superintendent of all prescribed medications that they are currently using.
This information will be supplied to the Site Medical Services
whicu will evaluate the use of the medications and will apprise plant management of any potential adverse effects.
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i The Nuclear Operations Superintendent will immediately notify Site Health
Services of any apparent illness or disability which may af fect licensed operatcrs performance.
The Nuclear Operations Superintendent will immediately notify Site
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Licensing if:
An operator has been permaner.tly reassigned and the operator holds a
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license or application has been made with the NRC,
A licensed operator is no longer employed;
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Notification has been received that a licensed operator has been
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convicted of a felony; and, Illness or disability of a licensed operator.
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The licensed operator physical examinations are conducted on site by a company medical doctor. These examinations appear to be thorough and, in L
cases of medical disqualification, the Nuclear Operations Superintendent is notified. There is no procedural stipulation as to when and how the shift supervisor in notified.
During this reporting period a senior reactor operator disqualified L
himself because of inadequate time in performing licensed dutie: in the L
last quarter. This was by notation in the shift supervisor log book. The i
10spector found no other notations of operator status in the log book (s).
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In summary, it appears the on duty shift supervisor may not know for at l
1 east 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> if a operator became disqualified and there are no up-to-l date records in the control room which the shift supervisor could access to determine the immediate qualifications of shift per;onnel. With this report, RAI 89-34 is complete.
7.
Licensee Action on Previously Identified Inspection Findings (92702 &
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i 92701)
a.
(Closed) Violation 302/89-08-04:
Failure to take adequate corrective action to establish correct radiation monitor trip setpoints.
The inspector reviewed and verified implementation of the corrective actions stated in the FPC response letter dated June 9, 1989.
b.
(Closed) Violation 302/89-11-01:
Failure to adhere to plant procedures.
The Inspector reviewed and verified implementation of the corrective actions stated in the FPC response letter dated August 4, 1989.
c.
(Closed) Violation 302/89-11-03:
Failure to declare an emergency classification.
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The inspector reviewed and verified implementation of the corrective actions stated in the FPC response letter dated August 4,1989.
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Exit Interview (30703)
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The inspector vet with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on October 6, 1989.
During this l
meeting. the inspector summarized the scope and findings of the inspection
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as they are detailed in this report with particular emphasis on the violation.
The licensee representatives acknowledged the inspector's comments and did not identify as propriety any of the materials provided to or reviewed by the inspectors during this inspection.
I; a Number Gescription and Reference 50-302/89-23-01 Violation - Failure to Heve Adequate Procedures, (two examples).
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Acronyms tnd Abbreviations i
ALARA - As Low As Reasonable Achievable CCTV- - Closad Circuit Television CFR
- Code of Federal Regulations
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ECCS - Emergency Core Cooling System (s)
F
- Fahrenheit
- Florida Power Corporation FSAR - Final Safety Analysis Report ft
- Feet
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- Instrumentation and Control LER
- Licensee Event Report NCOR - Nonconforming Operation Report NCR
- Nonconformance Report NRC
- Nuclear Regulatory Commission PM
- Preventive Maintenance RCA
- Radiation Control Area RWP
- Radiation Work Permit SP
- Surveillance Procedure STI
- Short Term Instruction
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TS
- Technical Specification VIO
- Violation
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