IR 05000302/1979040
| ML19260A229 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/26/1979 |
| From: | Martin R, Quick D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19260A225 | List: |
| References | |
| 50-302-79-40, NUDOCS 7911080200 | |
| Download: ML19260A229 (8) | |
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UNITED STATES
NUCLEAR REGULATORY COMMISSION g
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REGION 11
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101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA ?,o3o3 Report No. 50-302/79-40 Lice. ee: Florida Power Corporation 3201 34th Street, South St. Petersburg, Florida 33733 Facility Name: Crystal River Unit 3 License No. DPR-72 Inspection at C tal River site near Crystal River, Florida.
Inspectors:
dt/b G/3 /o/79
. R. K
Mte Signed Section Chief smgt./4v
G!79 ED.Magin U
Date ' Signed SUMMARY Date of Inspection September 4-7, 1979 Areas Inspected:
This routine, announced inspection involved 29 inspector-hours onsite in the areas of plant shutdown operations, maintenance activities, hurricane prepara-tions, followup on previously identified items, followup on IE Circulars and Notices, and a plant tour.
Results:
Of the seven areas inspected, no apparent items of noncompliance or deviations were identified.
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s DETAILS 1.
Persons Contacted Licensee Employees
- G. P. Beatty, Jr., Plant Manager
- P. F. ncKee, Operations Superintendent G. R. Westafer, Maintenance Superintendent W. A. Cross, Operations Engineer J. Cooper, Jr., Compliance Engineer G. M. Williams, Plant Engineer
- W. E. Kemper, Technical Specification Engineer S. W. Johnson, Intervice Inspection Engineer
- G. L. Boldt, Performance Engineering Supervisor
- J. E. Mack, Nuclear Maintenance Engineer Other licensee employees contacted included technicians, operators, maintenance, and office personnel.
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on September 7, 1979, with those persons indicated in Paragraph I above. The items described in these details were discussed, and the licensee acknowledged the inspector's comments.
3.
Licensee At tion on Previous Inspection Findings (Closed) Deviation 79-08-01 (Paragraph 3 of RII Report 79-08):
Inadequate fire rating on record storage vault doors. This deviation stemmed from an item of noncompliance originally identified as deficiency 78-08-01 which was closed in the above referenced report 79-08.
The deviation item 79-08-01 was then reinspected and found satisfactory during RII inspection 79-17 and should have been closed at that time; however, it was inadver-tently referred tc as 78-08-01 in that report. The inspector has no further questions at this time, and, therefore, both items are considered closed.
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(Closed) Unresolved Item 79-08-02 (Paragraph 5.a and 5.b of RII Report 79-08): Facility housekeeping / cleanliness controls. The licensee has developed and implemented Administrative Instruction AI-1000, Revision 6, dated 4/5/79, which establishes improved housekeeping requirements. This
- instruction establishes various cleanliness zones within the facility, designates responsibility for cleanliness, and provides for management inspection tours of the facility on a periodic schedule.
The inspector has no further questions at this time.
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Unresolved Items Unresolved items are matters about which more information is. required to determine whether they are acceptable or may involve noncompliance or deviations. New unresolved items identified during this inspection are discussed in Paragraph 6.
5.
Licensee Action on Previously Identified Inspector Followup Items The inspector reviewed licensee action on previously identified items of concern through discussions with licensee personnel, and verification of the implementation of applicable corrective action. The status on these items is indicated below:
a.
(Closed) IFI 77-17-03 Diesel Annunciators (See RII Report 77-17, 78-10, 78-21 and 79-08). The inspector verified that modification packages MAR 77-7-33 and MAR 77-7-33A had been completed and a functional test was performed by procedure. The inspector has no further questions on this item at this time however, it was identified as one of several examples constituting an item of noncompliance 79-04-08 during quality assurance inspection 79-04.
This item of noncompliance will be followed up during a future inspection.
b.
(0 pen) IFI 77-18-04 Heat Tracing Annunciators (See RII Reports 77-18, 78-21 and 79-08.
The modification package for this item, MAR 77-2-27, has not been released by corporate engineering as of this inspection.
They are awaiting the results of a study presently being performed by Gilbert Associates which is due by September 10, 1979.
c.
(Closed) IFI 77-21-03 Reactor Power Oscillations During State Opera-tion. The inspector verified through examination of operational records and direct observation of power operation at various times over the past year that no appreciable steady state power oscillation appears to exist at Crystal River. The inspector has no further questions at this time.
d.
(0 pen) IFI 78-06-04 Steam Rupture Matrix Modification.
The modifica-tion packages associated with this system were not completely installed at the time of this inspection, e.
(Closed) IFI 78-23-02 Decay Heat Closed Cycle Cooling Heat Exchanger Problem (See RII Reports 78-23 and 79-08). The inspector verified that the new carbon steel heat exchanger water box and the cathodic protection system have been installed. Discussions with plant personnel indicate operational results are satisfactory at this time
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and that similar modifications will be made to the other heat exchangers in this system as the need arises. The inspector has no further questions at this time.
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(0 pen) IFI 78-24-06 Vital Instrument Inverter Modifications. The inspector discussed this item with plant personnel and verified that modification package MAR 78-7-4 at.d MAR 78-7-4A had been installed on the "A" inverter. Plant personnel indicated significant improvement in the reliability of this inverter has been shown during subsequent load testing operation, and they have requested, from corporate engineering, approval to install these modifications on the other four inverters. This item will remain open pending complete installation and testing of all inverters.
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g.
(Closed) IFI 79-08-03 Management Plant Tours (See RII Report 79-08).
The inspector verified that the licensee has developed and implemented a program to provide for periodic tours of the facility by management personnel. This provision has been incorporated into Revision 6, of Administrative Instruction AI-1000, which requires weekly tours by the management individual on call. The inspector has no further questions at this time.
6.
Hurricane Preparedness The inspector reviewed the licensee's emergency plan EM-100 and abnormal procedure AP-104 which both deal with severe weather preparations to the facility. No particular concerns were noted in these procedures however, several potential concerns were identified during a tour of the outside areas surrounding the facility:
There is an excessive cmount of material surrounding fossil units 1 a.
and 2, in the form of stored material, small buildings, etc., which could possibly become missile material during heavy winds and threaten the reliability of the offsite power sources. This material should be minimized and substantial protection provided for that which is necessary to be stored outside.
b.
The amount of coal in the storage yard, as well as the transfer con-veyor system, could possibly pose a threat to the reliability of the cooling water systems during severe wind and torrential rain periods if it were to block the cooling water intake structure.
During periods of heavy wind, airborne coal dust could possibly c.
threaten the reliability of the emergency diesels, and/or the plant ventilation equipment, from the standpoint of blocking intake air filters.
The licensee agreed to evaluate these three concerns. This item designated as unresolved item 79-40-01 pending the results of this evaluation.
7. " Review of Plant Operations Plant operations were reviewed by the inspector to ascertain conformance with regulatory requirements and technical specifications.
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a.
Shift Logs The inspector reviewed the shift supervisor and control operator log books for the period August 31 through September 6 1979. No discre-pancies were noted.
b.
Control Room Operations The inspector observed portions of control room activities at various times during the inspection.
The inspector interviewed operations watchstanders, reviewed selected annunciators and plant instrumenta-tion, and verified compliance with Technical Specifications requirements.
During observations and discussions with operations personnel it was noted that instrumentation and control switch layout, as well as the type of instrumentation readouts utilized on some portions of the control board, can possibly lead to difficulties in effective and efficient operator evaluation of, and response to, a transient situation. Operations personnel indicated that relocation of indications of key parameters, coupled with a more readily apparent display of the information, would be helpful during transient situations requiring rapid operator response. This item was discussed during the exit interview at which time licensee management agreed to evaluate any potential problem areas identif ed by operations personnel.
It was also noted at this time that the possible installation of a new computer in the future would improve this situation since the computer would provide the capability to display the values of groups of key parameters on a cathede ray tube.
This item will be followed up during future inspections (IFI 79-40-02).
c.
Personnel Training on Plant Modifications Dieussions with operations personnel revealed a possible weakness and nonuniformity in the area of awareness and understanding of modifica-tions made to the facility.
Several examples of this problem were noted by the inspector as follows:
(1) Stream break matrix actuation and reset circuitry.
(2) Reactor coolant pump seal return valve automatic interlocks (MUV-253).
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(3) Pressurizer power operated relief valve indications and actuation circuitry.
(4) Emergency diesel generator auto start failure alarms.
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Apparently, a uniform timely method of providing operations personnel with a summary functional description of modifications does not exist at the present time. However, the inspector noted that some training has been conducted in this area. This area was discussed during the 1296 082
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-5-exit interview and licensee management agreed to resolve this problem with corporate engineering assistance. This item will be followed up during future inspections (IFI 79-40-03).
8.
Review of Maintenance Activities The inspector reviewed the progress of identification and repair of leaking tubes in the "B" steam generator on a daily basis. As of the close of this inspection the licensee bad identified and repaired a total of 31 leaking tubes. All of these leaks were in the tube to tube sheet weld area. No through wall tube degradation was identified. Weld repairs were apparently successful in 16 of these tubes however, due to difficulties encountered in the welding process it was necessary to plug 15 of the tubes to stop the leaks. All identified leaks have apparently been stopped at this time.
The large majority of the leaking tubes were among those tubes damaged during the failed burnable poison rod event in 1978.
The inspector has no further questions at this time; however, performance of this steam generator will be followed during future inspections.
9.
Review of IE firculars
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The inspector reviewed applicable IE Circulars with licensee persocnel to ascertain that they have been received on site and reviewed by cognizant supervisory personnel. Licensee's actions on the following IE Circulars were reviewed:
Circular No.
77-15 (0 pen) Degradation of Diesel Fuel Oil Procedural revisions to alleviate this concern are not complete at this tiee.
78-02 (0 pen) Small Turbine Lubricating Oil Problems Verification of correct lutricating oil has not been accomplished with the vendor at this time.
78-15 (Spen) Tilting Disc Check Valves Licensee review is not complete at this time.
78-16 (Closed)LimitorqueOpehators 78-17 (Closed) Guard Training / Qualification
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78-18 (Closed) UL Fire Test 78-19 (Closed) Bypass of Safety Injection Actuation Signals
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-6-79-02 (Closed) Inverter Failures 79-04 (Closed) Loose Limitorque Operator Locknuts 7.-05 (0 pen) Moisture Leakage in Electrical Conductora Licensee review not complete at this time 79-08 (Closed) Uranium Extortion 79-09 (Closed) Breathing Apparatus Diaphram Problems 79-10 (Closed) Unacceptable Pipefittings 79-12 (Closed) Emergency Diesel Generator Turbocharger Problems 79-13 (0 pen) Diesel Fire Pump Starting Contactor Problems Licensee review not complete at this time 79-15 (Closed) Breathing Apparatus Hose and Relief Valve Problems 79-17 (Closed) G.E. Circuit Breaker Problems 10.
Review of IE Notices The inspector reviewed applicable IE Notices with Licensee personnel to ascertain that they have been received on site and reviewed by cognizant supervisory personnel.
Nctice No.
79-01 (Closed) Snubbers 79-03 (Closed) Limitorque Limit Switch Lubricant 79-04 (Closed) Degradation of Engineered Safety Features 79-05 (Closed) Improper Materials in Safety Related Components
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79-06 (Closed) Stress Analysis 79-07 (Closed) Rupture of Radwaste Tanks
" 79-08 (Closed) Interconnection of Contaminated Systems 79-09 (Closed) Contaminated Resiu Spill 1296 084
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-7-79-10 (Closed) Nonconforming Pipe Supports 79-11 (Closed) Reactor Vessel Insulation Support Problem 79-12 (Closed) New Fuel Assembly Damage 79-15 (Closed) Deficient Procedures 79-17 (Closed) Damaged Source Assembly 79-18 (Closed) Skylab Reentry 79-19 (Closed) Pipe Cracks in Stagnant Borated Water Systems 79-20 (Closed) NRC Enforcement Policy - NRC Licensed Individuals
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