IR 05000335/1978026
| ML17206A586 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 11/27/1978 |
| From: | Robert Lewis, Webster E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17206A584 | List: |
| References | |
| 50-335-78-26, NUDOCS 7901020436 | |
| Download: ML17206A586 (7) | |
Text
~gS IIK00, P0 Report No.:
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30303 50-335/78-26 Docket No.:
50-335 License No.:
DPR-67 Licensee:
Florida Power and Light Company P.
O.
Box 013100 9250 West Flagles Street Miami, Florida 33101 Facility Name: St. Lucie
Inspection at:
St. Lucie Site Inspection conducted:
October 31 - November 3, 1978 Inspector:
E.
H. Webster Approved by: E. C.
R.
C. Lewis, Chief Reactor Projects Section No.
Reactor Operations and Nuclear Support Branch
/l',p Date Ins ection Summar Ins ection on October 31-November
1978 (Re ort No. 50-335/78-26)
able occurrences, and diesel generator systems.
The inspection involved 22 inspector-hours by one NRC inspector.
Results:
Within the three areas inspected, there were no noncompliance items or deviations identified.
qg04 O'Q 0%34
RII Report No. 50-335/78-26 DETAILS I yi g
Prepared by:
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E. H. Webster, Reactor Inspector Reactor Projects Section No.
Reactor Operations and Nuclear Support Branch Date Dates of Inspection:
October 31 - November 3, 1978 r
Reviewed by:
. C R. C. Le is, Chief Reactor Projects Section No.
Reactor Operations and Nuclear Support Branch Date 1.
Persons Contacted Florida Power and Li ht Com an-C. M.
-J. H.
- J. E.
-C. A.
-G.
M.
R. R.
G. J.
T. A.
L. W.
N. D.
- N. G.
+W. F.
J.
P.
- F. W.
C. L.
L. AD C.
LE T. L.
- A. W.
- A. E.
- D. A.
Wethy, Plant Manager Barrow, Operations Superintendent Bowers, Maintenance Superintendent Wells, Operations Supervisor Vaux, Jr., Quality Control Supervisor Jennings, Technical Department Supervisor Boissy, Assistant Superintendent, Electrical Dillard, Assistant Superintendent, Mechanical Pearce, Plant Supervisor, Nuclear West, Plant Supervisor, Nuclear Roos, Plant Supervisor, Nuclear Kitchens, Plant Engineer II Lewis, Senior Plant Technician Gross, Plant Technician Burton, Nuclear Watch Engineer Spaulding, Nuclear Control Center Operator Wilson, Plant Supervisor II Hill, Mechanic Bailey, QA Engineer Siebe, Assistant Manager of QA Operations Sager, Senior Plant Engineer
- Denotes those present at the exit interview.
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2.
Licensee Action on Previous Ins ection Findin s
Licensee action on previous inspection findings was not reviewed during this inspectio RII Report No. 50-335/78-26 I-2 3.
New Unresolved Items No new unresolved items were disclosed during this inspection.
4.
Hang ement Interview A meeting was held with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on November 3, 1978.
The inspector summarized the scope and findings of the inspection.
5.
Licensee Event Re orts (LERs)
a.
'Writ.ten Report Review The following thirty-day LER's were reviewed to determine whether
. reporting requirements had been met, the report assessed the event and identified the cause, and corrective action was appro-priate:
(1)
LER 78-23 letter (2)
LER 78-26 letter (3)
LER 78-27 letter (4)
LER 78-28 letter (5)
LER 78-31 letter (6)
LER 78-32 letter (7)
LER 78-35 letter (8)
LER 78-36 letter PRN-LI-78-189 PRN-LI-78-236 PRN-LT-78-243 PRN-LI-78-244 PRN-LI-78-259 PRN-LI-78-267 PRN-LI-78-274 PRN-LI-78-275 dated July 13, 1978 dated August 28, 1978 dated August 30, 1978 dated September 12, 1978 dated September 15, 1978 dated September 22, 1978 dated September 27, 1978 dated September 27, 1978 b.
No items of noncompliance or deviations were identified.
Written Report Review Plus Followup Onsite In addition to performing a report review as defined in a.
above, site followup was performed for these LERs to determine whether corrective action specified had been taken, the licensee had reviewed the event, whether it involved an unreviewed safety question or violation of regulations, or whether a corrected LER had been submitted, if required:
(1)
LER 78-25 letter PRN-LI-78-219 dated August 7, 1978.
This event involved discovery of an analytical error in the cask drop analysis for the spent fuel pool.
The licensee corporate office is evaluating a Technical Specification change request based on a
FPM. Power Plant Engineering reevaluation of a
double pendulum swing of the cask over the spent fuel pool.
The inspector reviewed the analysis with licensee personnel
~nd noted several changes in methodology from that used in the Final Safety Analysis Report (FSAR).
One assumption,
RII Report No. 50-335/78-26 I-3 concerning Radial Peaking Factor of the spent fuel deviates significantly from Regulatory Guide 1.25 and therefore requires review by Office of Nuclear Reactor Regulation (ONRR),
NRC prior to acceptance.
This item is open pending ONRR review (open item 78-26-01).
(2)
LER 78-29 letter PRN-LI-78-237 dated August 25, 1978.
This event involved vendor notification of a potential problem with motor operated valve steam bushing locknuts not being
"staked."
The licensee expanded the listing of 37 Velan valves supplied by Combustion Engineering to include all Velan valves used in safety functions in the plant; a total of 69 valves.
The inspector witnessed the inspection of one such valve and reviewed the completed work packages on all valves.
Of the 69 valves checked, only two were found to be properly staked, all others required staking by licensee maintenance personnel.
The inspector had no further ques-tions in this area.
(3)
LER 78-37 letter PRN-LI-78-282 dated October 2, 1978.
This event involved the discovery of
seismic braces on
safety-related ventilation systems missing.
The inspector reviewed the work packages for installation of the braces conducted September 22 - October 3, 1978, and inspected the three ventilation systems; there were no deficiencies noted.
In discussing the occurrence with licensee personnel as to cause, the inspector reviewed an EBASCO letter serial 9952 dated October 16, 1978, which evaluated the problem as being due to subcontractor drawings and quality control errors.
The licensee has accepted this explanation, but is still exploring corrective action to be taken to insure that:
(1) no other such problems exist from records of Unit
construction; and (2) this does not occur with Unit 2, still under construction.
In accordance with the licensee event report, a supplemental report concerning the cause of the occurrence and these corrective actions will be forwarded.
This item is open pending that report (open item 78-26-02).
6.
erations Lo Review The inspector reviewed the following plant operating'ogs for the period October 10-30, 1978, for completeness, indications of unreported incidents, proper supervisory reviews, or any entries violating or indicating violations of Technical Specifications:
a.
Nuclear Plant Supervisor Log b.
Nuclear Control Center Operator Log
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RII Report No. 50-335/78-26 1-4 c.
Nuclear Operator Log d.
Equipment Out of Service Log e.
Night Order Log f.
Operating Guidelines Book g.
Completed Check Sheets from Administrative Procedure (AP) 0010125
"Schedule of Periodic Tests and Checks" (1)
Check Sheet j/1 - "Survellance Performed Each Shift" for November 2, 1978.
(2)
Check Sheet j/2 - "Surveillance Performed Daily on the Midnight Shift" for November 2, 1978.
(3)
Check Sheet j/6 - "Surveillances Performed on Thursday" for November 2, 1978
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Shutdown Margin Determination per Operating Procedure 0110056 for November 2, 1978 i.
Valve, Lock Deviation Log j.
Disconnected Lead and Temporary Jumper Log.
From discussions with operations personnel, and from personal review, this log appeared to be properly maintained, but did not provide sufficient information for operating supervisors to determine specific components effected by a disconnected lead or jumper.
Licensee manage-ment committed to revise this log and AP 0010120, the procedure which governs this log, accordingly.
(Open item 78-26-03)
With the exception of the open item noted above, the inspector had no further questions in this area.
7.
Plant Tour The inspector toured the plant during a scheduled maintenance outage to check for equipment status and control, maintenance safety and supervision, fire suppression equipment status, housekeeping conditions, radiation controls, proper control room manning, proper equipment alignment, and remote meter readout.
a.
The inspector noted two carbon dioxide portable fire extinguishers and five fire hose station inspection tags did not indicate inspections had been conducted on them in October,1978.
However,
RII Report No. 50-335/78-26 I-5 further review revealed that the fire extinguishers had been inspected on October 8, 1978, and were so documented on Plant Work Order (PWO) 2236 and the hose stations had been inspected on October 10 and were documented in PWO 2221.
The inspector discussed the surveillance procedures with licensee staff and noted the requirement in Mechanical Maintenance procedure (MM) 1830, step 1.2 for the tag on each portable fire extinguisher to be filled out by the person conducting the inspection (surveillance).
The surveillance procedure (MM 1850) for hose stations, does not require a tag to be completed on the hose station.
There is no regulatory requirement for tags to be on fire hose stations and the licensee is not committed to the National Fire Prevention
'Agency (NFPA) Code 10.
The inspector noted that the Fire Protec-tion Program being, reviewed by NRR will commit the licensee to
, NFPA codes.
b.
The inspector observed that the manual isolation valves in the air start piping to the emergency diesel generators were installed-in accordance with the FSAR.
The inspector also determined that the four valves (two per diesel in the tandem diesel design), if shut would isolate air to the air start motors and prevent the diesels from starting, making one emergency generator inoperable.
Licensee management was not sure that a
low air pressure alarm would result, if these valves were shut.
Pending further evalua-tion by NRC, this item is open (open item 78-26-05).
No items of noncompliance or deviations were identified.