IR 05000335/1981008
| ML17209B222 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/27/1981 |
| From: | Bibb H, Dance H, Elrod S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17209B221 | List: |
| References | |
| 50-335-81-08, 50-335-81-8, NUDOCS 8106120438 | |
| Download: ML17209B222 (11) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTAST., N.W., SUITE 3100 ATLANTA,GEORGIA 30303 Report No. 50-335/81-08 Licensee:
Florida Power and Light Company 9250 West Flagler Street Miami, FL 33101 Facility Name:
St. Lucie Unit 1 Docket No. 50-335
'icense No. DPR-67
Inspection at St Lucie site near Ft. Pierce, Florida Inspectors:
C'~
,n S. A. Elrod C
H. E.
ibb Approved by:
H. C. Dance, Section Chief, Divi,sion of Resident and Reactor Project Inspection SUMMARY 4>>gy ate igned D te Signed
s.7 f'I D te igned Inspection on March 11, - April 10, 1981 I
Areas Inspected This routine inspection involved 74 resident inspector-hours on site in the areas of 'Followup of IE Bulletins, Circulars, and Information Notices; Licensee Event Report review; followup of Management Appraisal; and plant operations review.
Results Of the four areas inspected, no.violations or deviations were identifie DETAILS
,Persons Contacted Licensee Employees
"C. M.
"J.
H.
"J. E.
"D. A.
"N. G.
R. J.
C.
F.
P. L.
R. R.
H. F.
J.
G.
0.
D.
A. W.
L. W.
N. D.
C. L.
M. B.
"A. W.
"W. J.
Wethy, Plant Manager Barrow, Operations. Superintendent Bowers, Maintenance Superintendent Sager, Operations Supervisor Roos, guality Control Supervisor Frechette, Chemistry Supervisor Leppla, Instrument and Control Supervisor Fincher, Training Supervisor Jennings, Technical Department Supervisor Buchanan, Health Physics Supervisor West, Security Supervisor Hayes, Nuclear Plant Supervisor Marvin, Nuclear Plant Supervisor Pearce, Nuclear Plant Supervisor West, Nuclear Plant Supervisor Burton, Nuclear Plant Supervisor Vincent, Assistant Plant Superintendent - Electrical Bailey, equality Assurance Supervisor Barrow, Fire Protection Site Coordinator.
Other licensee employees contacted included technicians, operators, and shift technical advisors.
"Attended exit interview Exit Interview The inspection scope 'and findings were summarized on Apri 1 10, 1981 with those persons indicated in Paragraph 1 above.
A list of, inspector followup and unresolved items resulting from a previous management inspection was presented to plant management.
Licensee Action on Previous Inspection Findings Not inspected.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or deviations.
New unresolved items identified during this inspection are discussed in paragraph.
IE Bul 1 etins The following IE Bulletin was reviewed to determine whether it had been received and reviewed by appropriate management, responses, where necessary, were accurate and complete, and that required action taken was complete.
(Closed)
IEB 79-17 Pipe Cracks in Stagnant Borated Water Systems at PWR Plants.
This IE Bulletin is closed based on review by the Region II staff of Florida Power and Light Co.
response L-80-269 dated August 14, 1980 and on-site inspection documented in inspection report 50-335/80-13.
6.
IE Circulars The following IE Circular was reviewed to determine whether it had been received by station management,.
reviewed for applicability and -appropriate action had been taken or planned:
(Closed)
IEC 81.-01 Design Problems Involving Indicating Push Button Switches Manufactured by Honeywell Incorporated.
This IE Circular is closed based on licensee review that indicates that:
(a) the subject switches are not "used at St.
Lucie and (b) the switches used do not seen to be subject to the short circuit and inadvertent operation problems attributed to the subject"switches.
7.
IE Information Notices The following IE Information Notices were reviewed to ensure their receipt
- and review by appropriate management.
IE Information Notices are considered closed upon receipt and review.
IEN"81-03 Checklists for Licensees Making Notifications of Significant Events in Accordance with 10'CFR 50.72 IEN-81-04 IEN-81-05 IEN"81-06 IEN-81-07 IEN-81-08 Cracking in Main Steam Lines Degraded DC System at Pal i sades Failure of ITE Model K-600 Circuit Breaker Potential Problem with Water-Soluble Purge Dam Materials Used During Inert Gas Welding Repetitive Failures of Limitorque Operator SNB-4 Motor-to-Shaft Key
IEN-81-09 Degradation of Residual Heat Removal (RHR) System U
IEN-81-10 Inadvertent Containment Spray Due to Personnel error 8.
Licensee Event Reports Review The following LER's were reviewed to verify that reporting requirements had been met, cau'ses had been identified, corrective actions appeared appro-priate, 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 action had been taken, no unreyiewed safety questions were involved, and violations of regulations or Technical Specification conditions had been identified.
LER 77-22 (Update No. 1)
"LER 81-09
- LER 81-11
"LER 81"12
"LER 81-13 Undersized atmospheric steam dumps Digital data process system damper in the line printer failed Engineered safety features actuation system setpoint drift Chlorine detector out of commission
"B" Reactor Coolant Loop Hot Leg RTD Power supply failed 9.
Fol 1 ouwp of Management Apprai sal As a result of visits to the site and Corporate office by various NRC personnel during the months of November and December 1980, certain licensee activities that possibly do not comply with NRC regulations were identified to the Resident Inspector.
Those items were discussed in Inspection Report 50-335/81-02.
The report written by those NRC inspectors (PAS 80-4),
received subsequent to inspection 81-02, contained other potential viola-tions and also areas, identified as
"weak", which may or may not have a
regulatory basis.
The additional potential violations are listed below as Unresolved Items (UNR) and the
"weak" areas as Inspector Follow'up Items (IFI). All items will receive further attention and. resolution by IE Region II personnel, either resident or regional office-based:
b.
(IFI 335/81-08-01)
Establ i shment of a
written corporate training program including management controls, training records, and evaluation of training effectiveness.
PAS 335/80-4 paragraph 3.b.(1).(a),(b),(c)
and (d).
(IFI 335/81-08-02)
Lack of Facility-Review-Group approved training programs for Department, General Employee, Contractor, and Management training.
PAS 335/80-4 paragraph 3.b.(2).(a)
page 1 (IFI 335/81-08-03)
Formal methods not used to evaluate training.
This includes the observation that management is not normally involved in the evaluation of training.
PAS 335/80-4 paragraph 3.b.(2).('c)
and (u).
(IFI 335/81-08-04)
Florida. Power and Light Co..mechanical maintenance apprentice program did not include activities related to nuclear plants.
PAS 335/80-4 paragraph 3.b.(2). (e).
(IFI 335/81-08-05)
The He'alth Physics Manual and procedures do not address programs for complying with 10 CFR 19.12 instruction require-ments.
PAS 335/80-4 paragraph 3.b.(2).(d).
(UNR 335/81-08-06)
Failure of plant management to provide dire'ction and guidance for various departmental training programs.
PAS 335/80-4 paragraph 3.b.(2).(b).
(IFI 335/81-08-07)
Failure to develop a program to document and account for on-the-job training.
PAS 335/80-4 paragraph 3.b.(2).(r).
(UNR 335/81-08-08)
Inadequate involvement by the equal ity Control Department in plant change/modification activities.
PAS 335/80-4 paragraph 4.b. (31) and (37).
(UNR 335/81-08-09)
The guality Assurance Department did not review all plant change/modification packages to ensure that all quality require-ments were addressed.
PAS 335/80-4 paragraphs 4.b.(32)
and 10.b.(5).
(UNR 335/81-08-10)
Failure to ensure.that all associated procedures, instructions and drawings were revised as required at the time of plant change or modi ficati on implementation.
PAS 335/81-'04 paragraph 4.b.(34) and (35).
(IFI 335/81-08-11)
Inadequate procedures for training the non-operating staff upon completion of a plant change/modification and for communi-cating plant change/modification activity to the-operating staff at shift turnover.
PAS 335/80-04 paragraph 4.b.(17)..'IFI 335/81-08-12)
Design-control administrative documents did not reference controlling documents in all cases.
PAS"335/80-04 paragraph 4.b.(21).
(UNR 335/81-08-13)
Inadequate instructions for the jumper log.
AP 0010124 (Jumper Log) did not control mechanical jumpers, bypasses, or flanges.
PAS 335/80-04 paragraphs 4.b.(32)
and 5.b.(31).
(IFI 335/81-08-14)
Design document (plant change/modification package)
review by Power Plant Engineering Department was limited to the Field Engineer's signature.
PAS 335/80-14 paragraph 4.b.(36).
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(IFI 335/81-08-15)
480 volt fixed and magnetic trip devices were not included in established preventive maintenance/test programs.
.PAS 335/80-04 paragraph 5.b.(35)
page 49.
(IFI 335/81-08-16)
The system protection. group two-man rule does not appear to provide independent inspection.
PAS 80-4 paragraph 5.b.(35)
page
'IFI 335/81-08-17) Administrative procedures and Qual'ity Instructions implementing safety-related maintenance did not reference the Quality Procedures in all cases.
PAS 335/80-4 paragraph 5.b.(29).
(IFI 335/81-08-18)
NRC Headquarters follow up the question of using commercial grade items in safety grade equipment, PAS 335/80-4 para-graph S.b.(25).
(IFI 335/81-08-19)
Evaluation of equipment problems.
and failures not repotable to the NRC was not always documented.
There was no record review past the supervisor level.
PAS 335/80-04 paragraphs 5.b.(23)
and (28); 9.(b).(l).(f).
(IFI 335/81-08-20),Lack of routine failure or personnel er'ror trending program.
PAS 335/80-4 paragraph 5.b.(22) and 6.b.(9).
(IFI 335/81-08-21)
Update technical specification 6.2.1 concerning the corporate organization.
PAS 335/80-4 paragraphs 6.b.(3) and (4).
(IFI 335/81-08-22)
No written requirements for corporate visits to the site.
PAS 335/80-4 paragraph 6.b. (11).
-(IFI 335/81-08-23)
The corporate program for identifying and assigning responsibility for all reports to the NRC appears fragmented.
The Power Resources Department procedure did not address submittal of items from other departments.
PAS 335/80-4 paragraphs 6.b:(12) and'(13).
(IFI 335/81-08-24) Quality Instruction QI 1-PR/PSL-.2 did not identify the responsibilities and qualifications of the, Auxiliary Equipment Operator nor did it require the Nuclear Watch Supervisor.to hold an NRC Senior Reactor Operator permit.
PAS 335/80-4 paragraph 6.b:(15).
(IFI 335/81-08-25)
Lack of a
method for reviewing',, approving, documenting, and tracking temporary procedure changes.
PAS 335/80-4 paragraph 6.b.(17).
(IFI 335/81-08-26)
AP 0010119 places overtime restrictions on only licensed operators.
PAS 335/80-4 paragraph 6.b.21.
(IFI 335/81-08-27)
Failure to retain check sheets for valve lineups and quarterly review of valves, locks, and switches.
PAS 335/80-4 para-graph 6.b.(25).
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(IFI 335/81-08-28)
The guality Control Operations Surveillance Group had no written program to identify the selection process or sample size of activities inspected.
PAS 335/80-4 paragraph 6.b;(27).
(IFI 335/81-08-29)
The plant corrective action system did not include IE Information Notices.
PAS 335/80-4 paragraph 7.b.(3).
(IFI 335/81-08-30)
The corrective action system did not address
CFR
'9.
11(a)(4)
requirement to post notices to workers.
PAS 335/80-4 paragraph 7.b.(8).
(IFI 335/81-08-31)
The requirements and controls applied to storage of material by individual maintenance sections appears to be of a lower quality level than that applied by the stores department.
PAS 335/80-4 paragraph 8.b.(8).
(IFI 335/81-08-32)
The guality Assurance Department annual suppliers review did not always include nonconformances, staff comments, and the vendor history file.
The program was not in written form; PAS 335/80-4 paragraphs 8.b. (14) and (16).
(IFI 335/81-08-33)
The company Nuclear Review Board charter did not provide quidance to members regarding review responsibilities.
PAS 335/80-4 paragraph 9.b.(2).(a).
(IFI 335/81-08-34)
IE Headquarters evaluate generic problem concerning
CFR 21 reports being sent to individual plants rather than to the General Office.
PAS 335/80-4 paragraph 8.b.(17).
(IFI 335/81-08-35)
The Facility Review Group Chrter does not include all Technical Specifications requirements.
PAS 335/80-4 paragraph 9 b (1) (b).
(LII 335/81-08-36)
Facility Review Group to review all Technical Specifications violations identified by guality Assurance Audits.
PAS 335/81-04" paragraph 9.b. (1). (c).
(IFI 335/81-08-37)
Lack of training on Facility Review Group respon-sibilities for new Facility Review Group members or alternates.
PAS 335/80-4 paragraph 9.b. (1). (g).
(IFI 335/81-08-38)
The Facility Review Group Charter did not include review of operating logs, maintenance and other records.
PAS 335/80-4 paragraph 9.b.(1).(e).
(IFI 335/81-08-39)
The Company Nuclear Review Board was not parti-cipating in Audits nor Facility Review Group meetings.
PAS 335/80-4 paragraphs 9.b.(2)
~ (b) and (f).
an.. (IFI 335/81-08-40)
The Company Nuclear Review Board had not reviewed many items in a
timely manner.
PAS 335/80-4 paragraphs.
9.b.(2).(c),(d),(e)
and (h).
ao.
ap.
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as.
at.
au.
av.
(IFI 335/81-08-41)
The position of Executive Secretary for the Company Nuclear Review Board had not been permanently filled for several years.
PAS 335/80-4 paragraph 9.b.(2).(c).
(IFI 335/81-08-42)
There was no written program to describe the Company Nuclear Review Board Item-Tracking System.
PAS 335/80-04 paragraph 9.b.(2).(c).
(IFI 335/81-08-43) guality Procedure 2.3 did not describe the policy for periodic review of quality procedures nor the mechanism for can-cellation of quality procedures.
PAS 335/80-4 paragraph 10.b.(2).
(IFI 335/81-08-44)
The guality Assurance Department organization manual has not been updated since 1974.
PAS 335/80-4 paragraph 10.b.(4).
(IFI 335/81-08-45) guality Assurance Committee meeting minutes were not preserved for two meetings in 1980.
PAS 335/80-4 paragraph 10.b.(1).
(IFI 335/81-08-46) Failure to provide training requested by an auditor.
PAS 335/80-4 paragraph 10.b.(27).
(IFI 335/81-08-47)
Failure-of management to review guality Assurance audit checklists.
PAS 335/80-4 paragraph 10.b.(23).
(IFI 335/81-08-48)
Failure to use auditors experiences in areas audited.
PAS 335/80-4 paragraph 10.b.(26).
aw.
(IFI 335/81-08-49) Insufficient audit independence between the guality Assurance Department and the Company Nuclear Review Board.
PAS, ax.
ay.
az 335/80-4 paragraph 10.b. (13).
(IFI 335/81-08-50)
Power Resources Department staff. procedures had not been reviewed by the guality Assurance Department.
.PAS 335/80-4 paragraph 10.b.(7).
(IFI 335/81-08-51)
Changes in the guality Assuranc'e organization were implemented prior to individuals involved becoming. familiar with their new responsibilities.
PSA 335/80-4 paragraph 10.b.(8).
(IFI 335/81-08-52)
The guality Assurance Audit supervisor was not-always informed when audits were completed by other guality Assurance groups.
PAS 335/80-04 paragraph 10.b.(25).
10.
Review of Plant Operation The inspector kept informed on a daily basis of the overall plant status and significant safety matters related to plant operations.
Discussions about
planned safety-related activities were held frequently with various members of the plant management and operations staff.
Selected portions of current plant operating logs and data sheets were reviewed during this report period.
The inspector conducted several tours of plant areas.
Observations were made of work in progress, plant housekeeping, and vital area controls.
No violations or deviations were note I
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