IR 05000335/1979009
| ML17206A868 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/23/1979 |
| From: | Cantrell F, Webster E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17206A867 | List: |
| References | |
| 50-335-79-09, 50-335-79-9, NUDOCS 7906250375 | |
| Download: ML17206A868 (10) | |
Text
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UNITEDSTATES NUCLEAR REGULATORYCOMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30303 Report No.
50-335/79-09 Licensee:
Florida Power and Light Company 9250 West Flagler Street Miami, Florida 33101 Facility Name:
St. Lucie
Docket No.
50-335 License No.
DPR-67 Inspection at St. Lncie it ar. Miami, Florida Inspector:
E. H. Webster Approved by:
~r F.
S.
antrell, Acta g ion Chief, RONS Branch Date Signed s3 )
ate Signed SUMMARY Inspection on March 21-23, 1979 This routine, unannounced inspection involved 23 inspector-hours onsite in the areas of steam generator cleaning program, nonroutine event report program, plant procedures, IE Bulletins and Notices, LER review and previously identified noncompliance and open items.
Results Of the six areas inspected, no apparent items of noncompliance or deviations were identifie DETAILS 1.
Persons Contacted Licensee Em lo ees
- C. M. Wethy, Plant Manager
- J. H. Barrow, Operations Superintendent-J. E. Bowens, Maintenance Superintendent
- C. A. Wells, Operations Supervisor
+A.
W. Bailey, Quality Assurance Supervisor-R.
R. Jennings, Technical Department Supervisor R. K. Ryall, Reactor Engineering Supervisor A. J. Collier, Instrument Control Supervisor T. A. Dillard, Mechanical Maintenance Supervisor 0.
D. Hayes, Plant Supervisor, Nuclear-N.
G. Roos, Quality Control Engineer C. A. Moore, Chemistry Supervisor G. A. Ionghauser, Assistant Plant Security Supervisor Other licensee employees contacted included operators, and office personnel.
-Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on March 23, 1979 with those persons indicated in Paragraph 1 above.
3.
Licensee Action on Previous Ins ection Findin s a
~
(Closed)
Noncompliance (335/78-12-01):
Failure to follow procedure for documentation of liquid penetrant inspection.
The subject test forms, QI-10-PR/PSL-3-1 were filled out for the weld work done on relief valves MS8201 and MS8202 on May 16, 1978.
The inspector reviewed four more recent welding work orders and con-firmed compliance with the licensee Quality Instruction QI-10-PR/PSL-3.
The inspector had no further questions in this area.
b.
(Closed)
Noncompliance (335/78-17-01):
Failure to obtain proper approvals for a temporary change to a surveillance procedure.
The licensee reviewed and approved a permanent change to procedure OP 0420050,
"Containment Spray - Periodic Test" on August 3, 1978.
The inspector reviewed Quality Instruction OI-5-PR/PSL-1 and
interviewed several operators to assure procedure change controls were adequate.
The inspector had no further questions in this area.
Co (Open) Unresolved Item (335/78-15-04):
Upgrade requirements for evaluating instrument retest on a timely basis.
The licensee program to retest instrumentation after calibration equipment has been found out of calibration does not address guidelines to be used in evaluation, timeframe to complete the evaluation, nor policy toward retest of affected safety-related instruments.
Licensee management, subsequent to the inspection indicated that a
change to Quality Instruction QI-12-PR/PSL-1 is being made to cover these topics.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Plant Status The St. Lucie Unit 1 plant was at 100$ power during this inspection.
6.
Steam Generator Cleanin Pro ram Review The licensee has decided not to conduct the steam generator cleaning program during the upcoming refueling outage in April, 1979.
Licensee correspondence to confirm this fact is forthcoming, however, Office of Nuclear Reactor Regulation, NRC was informed by telephone on March 21, 1979 of this decision.
Licensee management explained that the final model boiler testing completed in early March was not successful in removing support plate crevice deposits to the extent necessary.
The licensee now plans to conduct a "rim-cut" of the steam generator tube supports during the 1979 refueling outage to preclude any support plate differential growth, and to continue development of the cleaning pro-cedure for use during the 1980 refueling outage.
7.
Nonroutine Event Re ortin Pro ram The inspector completed the review of corrective action controls and administrative controls of vendor bulletins and circulars referenced in IE Report 335/79-06 paragraph 12, and had no further questions.
8.
Plant Procedure Review The inspector reviewed a sampling of plant operating, maintenance, off-normal, emergency, and administrative procedures to verify that procedures are:
reviewed and approved in accordance with Technical
Specifications (T.S.)
changed in response to plant modifications and changes to T.S., were reviewed pursuant to 10 CFR 50.59, pere tech-nically adequate and met TS requirements for operations, and were properly distributed.
The inspector reviewed twenty-one procedures total, but completed the review for technical adequacy on only eight procedures.
Those procedures for which all review was completed were:
AP0005720 Licensed Operator Requalification Program AP0010124 Control and Use of Jumpers and Disconnected Leads in Safety Related Systems QI-5-PR/PSL-1 Preparation, Revision, Review and Approval gl-16-PR/PSL-1 Corrective Action OP 0030140 Blackout Operation OP 1220030 Linear Power Range Channel Malfunction OP 0030121 Plant Heatup - Cold to Hot Standby OP 0120020 Filling and Venting the RCS The review of gl-5-PR/PSL-1 included review of the licensee administrative controls of plant procedures which appear to meet the requirements of T.S. section 6.8 and
CFR 50.59.
In reviewing procedure distribution, the inspector noted that a copy of procedure AP0010124 is kept in the front of the Jumper Log, the document it governs, but that the distribution list does not include the log for receipt of changes to this procedure.
Licensee management indicated that there is no present policy requiring control procedures in their applicable logbooks and that they intend to review administrative procedures for distribution to logs to either delete the procedure from the log books or control distribution to them.
The inspector will review this area in future inspections (335/79-09-01).
The inspector shall complete the technical review of the remaining sampling of procedures in future inspections.
No items of noncom-pliance or deviations have been identified in the review completed at this time.
9.
IE Bulletins The following IE Bulletins were reviewed to determine whether they had been received by station management, reviewed for applicability and appropriate action taken or planned in accordance with the licensees written response.
a.
IEB 77-08 Assurance of Safety and Safeguards during an Emergency-Locking Mechanisms dated December 28, 1977.
As indicated in IE Report 335/78-09, Details I, paragraph 9, final review in this area was delayed until the licensee implemented the new security
-4-plan.
The inspector observed egress capability at ten doors to vital areas, all were designed to allow emergency egress while maintaining security during a loss of off -site power.
The in-spector had no further questions.
b.
IEB 78-04 Environmental Qualification of Certain Stem Mounted Limit Switches (SMLS) inside Reactor Containment dated February 12, 1978.
This IEB, formerly closed in IE Report 78-09 was reopened to investigate use of any non qualified SMLSs in the reactor containment for critical valve position indication.
The inspector reviewed a licensee internal memo dated March 22, 1978
. reporting an evaluation that no SMLSs are used on motor operated valves in containment.
Licensee management indicated that air operated valves will be analyzed for use of unqualified SMLSs as a
follow-on to this bulletin.
C ~
IEB 78-14, Deterioration of BUNA-N in ASCO Solenoids, dated December 19, 1978.
Although this bulletin is not directed to St.
Lucie for response, it was addressed to the licensee for informa-tion.
The licensee has forwarded IEB 78-14 to the applicable supervisors for evaluation at this time, and will be reviewed in future inspections.
10.
IE Notice 79-04, Degradation of Engineered Safety Features, dated February 16, 1979 The inspector verified that the licensee had received and reviewed IEN 79-04 for applicability.
The inspector had no further questions in this area.
ll.
Licensee Event Re orts Review The following LER's were reviewed to verify that reporting requirements had been met, causes had been identified, corrective actions appeared appropriate, generic applicability had been considered, and the LER forms were complete.
Additionally, for those reports identified by asterisk, a more detailed review was performed to verify that the licensee had reviewed the events, corrective actions had been taken, no unreviewed safety questions were involved, and violations of regula-tions or licensee/Technical Specification conditions had been identified.
a.
LER 78-33/03L-0 Dose Equivalent Iodine Greater than 1.0 micro-curies per gram.
b.
LER 78-45/03L-1* Digital Data Processing System (DDPS)
Malfunction.
This supplemental report more fully described the
DDPS program error and reprograming performed.
Since the program involved is for operator information only and does npt effect any required programs, the program change did not require the reviews required of a plant change or modification.
Licensee management agreed with the inspector that modifications to those DDPS programs required by T.S. would require documentation and review as a modification.
LER 79-01/03L-0* Two Control Element Assemblies (CEAs) Stuck During Shutdown.
The inspector reviewed the Facility Review Group (FRG) minutes where records are kept of FRG review and approval of various steps taken to free the CEAs.
Review of equality Control Reports (}CR 5864 dated January 28 and gCR 5858 dated January
indicated adequate quality controls were used and that subsequent CEA testing was satisfactory.
The procedures used by Combustion Engineering to set up, control and report results of the mechanical jacking operation which freed the CEAs conducted January 26, were not available, however.
The inspector shall review this procedure in future inspections to assure adequate controls were used in mechanically lifting two CEA's.
LER 79-02/03L-0 CEA 41 Dropped During Operations LER 79-03/01T-0* Two Safety Injection Tank (SIT) Boron Concentrations Low.
The inspector reviewed Chemistry Procedures C-09A Primary and Secondary Grab Samples and C-60, Maintaining Safety Injection Tank Limits, and discussed the event with licensee supervisory personnel.
Corrective action and procedures to preclude recurrence appeared adequate, and the inspector had no further questions.
LER 79-04/03L-0 CEAs Out of Alignment Due to Faulty Reed Switches LER 79-05/03L-0* Auxiliary Feed Water (AFW) Pump failed to Start.
The inspector examined the AFW pump, drawings, and the surveil-lance procedure OP 0700050.
Since the pump has only been run for surveillance purposes, the possibility exists that the pump has been inoperable since it was surveilled last.
A review of pro-cedure OP 0700050 revealed no supplementary steps, after the pump is tripped, to assure the trip mechanisms is relatched, making the pump ready for use.
Lic nsee management committed to change procedure OP 0700050 (
nclude such action to assure pump operability.
The inspect or will review this change in future inspections (335/79-09').
LER 79-06/03L-0 CEA
Dropped Due to Failed Power Supply
12.
Previousl Identified Item Review The inspector reviewed licensee action on the following cpncerns identified by IE inspectors in previous inspection reports:
a
~
(Closed)
Open Item (335/78-15-05)
Licensee to include record keeping requirements of 10CFR21.51 in Quality Procedures (QP).
QP 17.1, Retention of Quality Assurance Records, revision 2 dated November 15, 1978 included all 10CFR21.51 record retention re-quirements.
The inspector had no further questions in this area.
b.
(Closed)
Open Item (78-23-02) Attach warning signs to applicable limitorque valve operators.
This item was followup action to IEC 78-16.
The inspector observed signs in place on the four appli-cable valves and had no further questions.
c ~
d.
(Closed)
Open Item (335/78-26-04)
Licensee to revise AP0010124 to change Jumper I.og format.
Administrative Procedure AP0010124, revision 3 dated March 4, 1979 changed the format of the Jumper Log pages to more clearly describe the function of the jumper or disconnected lead for operations personnel.
The inspector had no further questions in this area.
(Open)
Open Item (335/79-01-05) Fire extinguisher inspection documentation deficiencies.
The inspector checked 15 mounted fire extinguishers in vital areas of the plant to assure monthly in-spection requirements were met and indicated on attached tags.
Three extinguishers, at stations A-l, A-7 and A-39 did not indicate completed inspections in March on attached tags although Plant Work Order 2109 indicated completion of the inspection on March 8 on these extinguishers.
Since all previous February inspections were documented on the tags affixed to the extin-quishers, the program appears to have improved, however, as noted in IE Inspection Report 335/79-01 paragraph 11.1.,
once the St.
Lucie Fire Protection Program is accepted by NRC, failure to
.complete the extinquisher tags will constitute noncompliance with the progra 'I I
I