IR 05000302/1979042
| ML19210E458 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/24/1979 |
| From: | Dyer J, Quick D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19210E451 | List: |
| References | |
| 50-302-79-42, NUDOCS 7912050068 | |
| Download: ML19210E458 (6) | |
Text
'o UNITED STATES
',,
NUCLEAR REGULATORY COMMISSION o
$
I REGION 11 a
o 141 MARIETTA ST., N.W., SylTE 3100 o
ATLANTA, GEORGIA 303o3
Report No. 50-302/79-42 Licensee: Florida Power Corporation 3201 34th Street, South St. Petersburg, Florida 33733 Facility Name:
Crystal River Unit 3 Docket No. 50-302 License No. DPR-72 Inspection a. Crystal River Site naar Crystal River, Florida Inspected by: WmN[ Y [ af M -2Y-77 D. R.
uick
/
Date Signed
'
Approved by 21/
/C 6/ M y A. Dypf, Acting Section Chief, RONS Branch Date Signell SUMMARY Inspection on October 1-5, 1979.
Areas Inspected This routine unannounced inspection involved 33 inspector-hours onsite in the areas of review of operati.ons, review of licensee event reports, followup on previously identified items, and a plant tour.
Results Of the 4 areas inspected, no apparent items of noncompliance or deviations were identified.
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O LETAILS 1.
Persons Contacted Licensee Employees
- G. P. Beatty, Jr., Plant Manager
,
P. F. McKee, Operations Superintendent G. R. Westafer, Maintenance Superintendent W. A. Cross, Operations Engiteer
- J. Cooper, Jr., QA/QC Manager W. E. Kemper, Technical Specif2 cation Engineer
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S. W. Johnson, Inservice Inspeccion Engineer
- R. W. Kennedy, Compliance Supervisor
- L. A. Hill, Compliance Auditor Other licensee employees contacted included technicians, operators and office personnel.
- Attended enit interview.
2.
Exit Interview The inspection scope and findings were summarized on October 5, 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 Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Licensee Action on Previously Identified Inspector Followup Items The inspector reviewed licensee action on one previously identified item of concern through discussions with licensee personnel, and verification of the implementation of applicable corrective action. The status on this item is indicated below:
(Closed) IFI 79-24-04, Exhaust Manifold Fire on "B" Emergency Diesel (See RII Rpt.
79.94, Paragraph 10). The inspector reviewed Work Request #9840 to verify that additional recommended maintenance had been accomplished on the diesel.
The inspector has no further questions at this time.
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6.
Plant Operations Plant Operations were reviewed by the inspector to ascertain conformance with regulatory requirements and technical specifications.
a.
Daily Activities The inspector maintained daily awareness of plant status and signifi '
cant activities through discussions with members of the plant staff and operating personnel.
Selected portions of the various daily log books and control room data sheets were examined on a daily basis during the report period. The inspector made several plant tours in selected areas of the turbine and auxiliary buildings. The control room was visited on a more frequent basis than other portions of the plant. Observations included instrument readings and recordings, housekeeping and status of operating systems and components.
Informal discussions were held with operators and other personnel on work activities and status of equipment.
Questions developed by the in-spector were satisfactorily answered.
Interviews with a number of plant operations personnel were held on the day and night shifts.
Supervisors and control operators actions were observed. Their actions and activities were responsive to the activities in progress.
Operator's were responsive to annunciator alarms and appeared to be cognizant of plant status.
b.
Plat' Jumper Log Th. inspector reviewed the Plant Jumper Log Book to verify that jumpers placed on equipment were controlled and that a safety evaluation had been performed on each jumper. There is still a relatively large number of active jumpers being maintained in the log, and the licensee is continuing to purge this log of unnecessary jumpers. No discrepancies were noted at this time.
Plant Equipment Clearance and Switching Orders c.
The inspector reviewed the Plant Equipment C).earance and Switching Order logs to verify that equipment or components, required for the plant mode of operation at the present time (Mode I), were available for operation as required by Technical Specifications and that the clearance logs were properly filled out and completed as per CP-115, "
"In-Plant Equipment Clearance and Switching Orders". No discrepancies were noted at this time.
d.
Plant Tours As part of the plant operations review, the inspector toured acces-sible portions of the plant. During the tour, observations were made regarding the general plant housekeeping and cleanliness and radiation control practices.
In general, these areas were found to be satis-factory.
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Seizmic Restraint Problems On October 4, 1979, the licensee reported, to the inspector, that during a review of seizmic restraints, in accordance with IE Bulletin 79-14, it was determined that seven restraints located inside the reactor building did not meet the criteria of having a design safety factor of greater than two.
These restraints are located on Nuclear Services Closed Cycle Cooling water lines associated with cooling the reactor coolant pumps. After discussion-with regional and headquarters NRC management, a determination was made to allow continued operation of the facility until the next cold shutdown, at which time these restraints would be repaired. This determination was made after consideration of the following facts:
a.
Accessiblility of the restraints b.
Personnel exposure c.
Impact of failure on plant operation d.
Impact of failure during an accident e.
Capability for both, automatic and remote manual isolation in event of failure The licensee will submit a written report, to include planned corrective action, within fourteen days in accordance with Technical Specification requirements. Regional inspectors will evaluate this report and followup on corrective action as part of the planned review of the required actions stipulated in IE Bulletin 79-14.
The next planned cold shutdown of the facility is currently scheduled for mid-December 1979.
8.
Review of Licensee Event Reports The inspector reviewed selected LER's for consistency with the requirements of the Technical Specifications and Regulatory Guide 1.16 (Reporting of Operating Information - Appendix A Technical Specifications). The inspec-tor examined the licensee's analysis of the event, the corrective action taken, and discussed the LER's with licensee representatives. The followinj LER's were reviewed:
(Closed) LER 79-046, Decay Heat Valve (DHV-4) Inoperable.The inspector a.
determined that modifications to the drive motor torque control system has been completed as recommended by an engineering evaluation.
b.
(Closed) LER 79-059, Containment Leakage Test Frequency Exceeded.
The inspector closed this LER without comment.
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-4-t (Closed) LER 79-061, Inoperable Pipe Supports.
c.
Detailed review of these problems will be accomplished in connection with IE Bulletin 79-02.
d.
(0 pen) LER 79-063 and 79-082, Inoperable Makeup Pump "B" Due to Piping Leaks.
This problem has been tentatively attributed to cyclic fatigue of the piping and an engineering evaluation of the problem is. currently underway by the licensee.
Since a third event of a similar nature has recently occurred, these LER's will remain open pending review of tite engineering resolution.
(Closed) LER 79-069, Exhaust Manifold Fire on "B" Emergency Diesel e.
Generator.
This event was evaluated previously in RII Report 79-24.
f.
(Closed) LER 79-070, Reactor Building Monitor (RMA-6) Inoperable.
The inspector closed this LER without comment.
g.
(Closed) LER 79-071, Reactor Building Isolation Valves Inoperable.
Request for Engineering Information 79-7-5 has been initiated to investigate and correct cause.
The inspector has no further questions at this time.
h.
(Closed) LER 79-072, Mode Changes Made While in Technical Specification Action Statements.
The inspector verified that a " Shift Turnover Checklist" is presently being developed and that all operations personnel have been cautioned in this area. The inspector nas no further questions at this time.
i.
(Closed) LER 79-073 and 79-079, Control Rod Position Indication Reed Switch Problems.
These LER's are closed without comment.
j.
(Closed) LER 79-078, Auxiliary Building Exhaust Fans (AHF 14-B and D)
This LER closed without comment.
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(Closed) ER 79-080, Inoperable Cooling Water Containment Isolation Valve (SW-79).
This ER closed without comment.
1.
(Closed) ER 79-081, Fire Service Valve (FSV-89) Inoperable.
L.e inspector verified that this valve had been opened and ::ealed to prevent inadvertant closure.
(Closed) E R 79-083, Failure to Comply With Most Restrictive of Two m.
Technical Specification Action Statements The inspector verified that procedure changes are presently being implemented to prevent recurrence and that operations personnel have been instructed to adhere to the requirements of the most restrictive action statement applicable. The inspector has no further questions at this time.
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