IR 05000335/1981002
| ML17266A417 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/12/1981 |
| From: | Bibb H, Dance H, Elrod S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17266A415 | List: |
| References | |
| 50-335-81-02, 50-335-81-2, NUDOCS 8103240743 | |
| Download: ML17266A417 (18) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTAST., N.W., SUITE 3100 ATLANTA,GEO RG IA30303 Repor t No.
50-335/81-02 Licensee:
Florida Power and Light Company 9250 West Flagler Street Miami, FL 33101 Faci lity Name:
St. Lucie
Docket No.
50-335
't" 'c'ents'e No.".
DP-R'""67'nspection at St. Lucie site near Ft. Pierce, Florida sp inspector's: 'P)
S. A. Elrod H. E.,Bibb Approved by:
,.-
H. C. Dance,'Section Chief, Projects Branch ¹2 Date Signed Date igned Dlte Signed SUMMARY Inspection on January 2-30, 1981 Areas Inspected This routine inspection involved 133 resident inspector-hours on site in the areas of plant operations review, followup of IE Bulletins, Circulars, and Information Notices,followup of items. from previous inspections, followup of licensee event reports, and followup of management appraisal.
Results Of the five areas inspected, no apparent violations or deviations gpre identified
, in two areas; three'apparent.ViolatiotIS were found In tht'ee at'eas (ViolatlOn Failure
.to post roving fire watch patro'I'or open cable penetrations.
-':paragraph 11; Vi:olation. -., Failur'e.:to.have'-adequate procedure for,ordering
.
material -'aragraph 9'.a
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- Violation -'n'adequate receipt inspection - paragraph 9.b.).
DETAILS 1.
Persons Contacted Licensee Employees
"C. M. Wethy, Plant Manager
"J. H. Barrow, Operations Superintendent
- J. E. Bowers, Maintenance Superintendent
"C. A. Wells, Operations Supervisor
"N, G. Roos, Quality. Control Supervisor G.'" M,...VaujQuality Control..Supervisor,'.
'C'.'; Leppla', Instrument a'nd 'Control Supeiv'i'sor'"" '
P.
L. Fincher, Training Supervisor
- R. R. Jennings, Technical Department Supervisor
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-.B., W..Mikell, Outage'.Coordinator..
J.
H. Ruby, Administrative Supervisor J.
G. West, Security Supervisor 0. D. Hayes, Nuclear Plant Supervisor A. W. Marvin, Nuclear Plant Supervisor L. W. Pearce, Nuclear Plant Supervisor N. D. West, Nuclear Plant Supervisor C. L. Barton, Nuclear Plant Supervisor
~D. A. Sager, Operations Supervisor M. B. Vincent,. Assistant Plant Superintendent - Electrical
- A. W. Bailey, Quality Assurance Supervisor J. Krumins, Engineer G.
E. Walling, Technical Staff P
Other licensee employees contacted included technicians, technical advisors, mechanics, and secur'ity force members.
operators, shift
- Attended at least one management interview.
2.
Management Interviews The inspection scope and findings were summarized on January 16, and February 2,
1981, with those persons indicated in Paragraph 1 above.
The inspector presented a list of items closed.
The apparent violations listed ia.the. report. were di.scussed..
r L'icens'ee".Acti on en:Prev'ious"Insyecti onindi ngs ';
(Closed)
Followup. I'tern (80-01-02). Inclusion of Source Standard Preparation.
for Calibration of The GeLi Counting System.
Chemistry Operating Procedure C-48, Rev.
was reviewed by IE Region II technical staff with no comment.
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4.
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 9.
5.
IE Bulletins 0,
a.
(Closed)
IEB-78-12, 12A, 12B -
A Typical Weld Material in Reactor Pressure Vessel Welds... This Bulletin is closed based on IE:HQ review
- .
- .. of.. l.icensee Combu'stion Engineering,Co...submittals.'..
.
b.
(Closed)
IEB-80-18, Maintenance of Adequate Minimum Flow Through Centrifugal Charging Pumps Following Secondary Side High Energy Line
...: Rupture.-
The. inspector.. verified the.;licensee.'s.response.
L-.80-311. that.
St.
Lucie 1 doesn't use centrifugal charging pumps and that the High Pressure Safety Injection Pumps have a designed minimum flow system that meets the Bulletin requirements.
c.
(Closed)
IEB-80-23, Failures of Solenoid Valves Manufactured by Valcor Engineering Corporation.
Licensee response L-80-397 indicates that St. Lucie 1 doesn't use the subj'ect solenoid valves.
IE Circulars The following IE Circulars were reviewed to determine whether they had been received by station management, reviewed. for applicability and appropriate action had.been taken, or planned:
a.
'(Closed) 'IEC-80-03, 'Protection From Toxic Gas Hazards.
The licensee has performed the evaluations requested by the Circular and concluded that St. Lucie 1 control room meets the referenced requirements, FLorida
'Power and Light Co..letter L-81-4, en'closure 5,
summarizes this review for TMI Task Action Plan (NUREG-0737)
Item 111.0.3.4 which supersedes Circular 80-03.
Any further inspector reference to thi s subject will be with respect to the Task Action Plan.
b.
(Closed)
IEC-80-17, Fuel Pin Damage Due to Water Jet. From Baffle Plate Cor'ner.: This'ircular is closed. based on =previous inspection report, 80-36 and subsequent review by the licensee of Combustion Engineering
". 'Co, -1ettep 'F.-GE-7376.
".-;.."':-
.
c-.
(Closed)
IEC'-80-21, Regulation of-. Refueling Crews.
Closure is based on review of Operating Procedure 1600022, Rev.
IE Information Notices The following IE Information Notice was reviewed to ensure its receipt and review by appropriate management.
IE Information Notices are considered closed upon receipt and review.
IEN-81-01 Possible Failures of General Electric Type HFA Relays The following IE Information Notice was not sent to St. Lucie. It is closed as "Not Applicable".
/
- LER 80-06 Containment Isolation Valves Stuck Open by Boric Acid
., TEN.-.83,-02,
=-".',.
....Transportation..of.'Radiography. Devices 8.
Licensee Event Reports Review The following LER's were reviewed to, verify that reporting requirements had been met, causes 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 unreviewed safety questions were involved, and violations of regulations or Techncial Specification conditions had been identified.
HLER 80" 12
.
and Update
B-Emergency Diesel Generator Failed to Reach Rated Speed
"LER 80-30 Control.,Element Assembly Block Circuit Disabled
- LER 80-60 LER 80-61 Administrative Control of Unit 1 Unit 2 Interface Design t,
Component Cooling Water Control Power Provided from Non-Independent Sources.
HLER 80-62 Missed Surveillance Personnel Air Lock Leak Test
."LER 80-65
.,
Failed Fire.Detector Element In Containment
..:"LER'80-.6'6 ":.. '..,Component.;CooT.ing Water,Heat Ekchangej Isolated; for Repair to Intake Cooling Water Line LER 80-67 Trip Circuit Breaker Undervoltage Coils Failed to Update
Functi on.
Update Corrected Type of Circuit Breaker
- LER 80-69 Containment Radiation Monitor Channel MD Failed Cold. Leg Temperature, Above 542~ LER 80-70 Steam Generator Level Indication at Remote Shut Down Panel Failed No violations or items of deviation were identified in the above areas.
9.
Followup of Management Appraisal 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..These activities, listed in the paragraphs that
.','..:,,...'.. ;.follow...'were,':,identified.. to,the....licensee.'t, a...managem'ent'. i.nterview'n
..'.:,','. ",.",,
- ':: 'Januar'y 16," 1981:"
'Th'o'se items shown-'as 'unr'es'ol'ved"will,bei'rivesti'ga'te'd
'a'nd::::-:
resolved by the Resident Inspector.
a.. " (Violation 335/81:-02-..01),,Failure.to Assure that Technical Requirements....
are Included iri Purchase Orders/Requisitions.
Turkey Point personnel are allowed to order safety-related material for St. Lucie.
Turkey Point QC/QA are allowed to review and approve these orders/requisitions.
No formalrequirements exist to require or provide a means for Turkey Point personnel to assure that all appli-cable St.
Lucie technical requirements are included on the purchase order/requisition.
- Pacific Scientific mechanical snubbers were ordered, reviewed, and approved by. Purchase Order No. 65255-22070C by Turkey Point personnel for St.
Lucie.
The purchase order does not require compliance with applicable,FPL specifications for mechanical snubbers nor... does it require cer tificstion of compliance with applicable functional test-requirements of FPL snubber specifications.
QI-4. PR/PSL-1 governs the above activities and has various requirements
'for assuring that all"techn'ic'al requirements ar'e included. i'n purchase..
orders and requisitions.
The above activity violates
CFR
Appendix B Criterion V as implement by FPL Topical Quality Report, TQR 5.0.
b.
(Violation 335/81-02-02)
Failure to Conduct Proper Receipt Inspection
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~.....of Qual'i.ty:.Controlled Material.
"::.: '.-.,:.:." '.:, " The'-.receivi,rig;;inspecti'on.
check. 1'iit::.for.,Pacif'ic.'..'S'cienti:fic..snubbers'"::.
.purchased.
on. Purchase..Order Nos. 71059.-63078P and 65255-06810W.requires documentation/certification, of compl.iance
- with purchase-orders-"
specified functional tests.
in accordance with procedure EPP-MS-276.
Certification for the above snubbers verify conformance with the purchase order and Pacific Scientific functional tests using Pacific e
Scientific procedure 524L rather than EPP-MS-276.
No record was
'vai'lable that showed that Pacific Scientific procedure.
524L was
'ompared to FPL specification EPP-MS-276 or that Pacific Scientific
',-: :',.:,;. Procedure'52L was even..availabl,e to'QC.'lso.,
no record was available.'..
\\
to show that QC receiving inspection had questioned the situation.
The QC supervisor stated that the cause was inspector err or.
QI-7 PR/PSL-2 paragraph 5.6 requires that QC material shall be receipt inspected using acceptance criteria included in applicable receiving inspection check lists.
The above activity violates
CFR 50 Appendix B Criterion V as implemented by FPL Topical Quality Report TQR, 5.0.
c.
(Unresolved 335/81-02-03)
Failure to Have an Adequate Program for Storage of Quality Controlled Material.
The program at St.
Lucie was compared to (a)
CFR 50, Appendix B, Criterion XIII, (b) ANSI N18.7
...'.;, '.:].977...and (c).:ANSI'...N45.:2.2
. 1971,',, Specifi.c, conditi.ons
,or,'.program el'ement's" believe'd"d'efi'cient incl'ude:
(1)
QI-7 PR/PSL-1 does not provide for separation of hazardous
.material. as. required. by paragraph 6.3..3 of reference (c) above.
d (2)
QI-13 PR/PSL-1 does not provide for access to plant stores ware-houses as required by paragraph 6.2. 1 of reference (c) above.
Although, it appears that it is being informally controlled.
(3)
QI-13 PR/PSL-1 does not provide for shelf life as required by paragraph 5.2. 13.4 of reference (b) above.
(4)
QI's do not identify storage. preventative maintenance requirements as required'by paragraph 6.4.2 of reference (c) above.
(5)
RCP case to cover studs stored next to herbicide (prometon)
marked hazardous and,: corrossive in bulk storage warehouse.
Drain cleaner containing sulfuric acid stored in sam'e area where safety-related
'aterial are stored. 'hemical deodorant containing approximately 5% ammonia is stored in same area where safety-related material are stored.
'
(Unresolved 335/81-02-04)
Failure to'ither Establish nor to Implement Adequate Non-licensed Training Programs:
(1)
Implementation of Journeyman Mechanical Maintenance Training Program as required by Procedure M-001 and Technical Specification
.6.8..
,'-:(2)'Ipadequ'at'e'trafni'ng:.'p'rograms.for Nu'clear'Gperatop,'- Nuclea'r Turbine'
- -.'
Operator, and Auxiliary, Equ'ipment Operator.
Training has not included'l'assroom sessi'ons.
and periodic lectures along with training goals and objectives and an evaluation of how effective the training has been.
(3)
Establishment of Training programs for administrative and outage departments personnel as r'equired by Technical Specification 6.4. 1 and QI-2 PR/PSL- (Unresolved 335/81-02-05) Failure of departmental training coordinators to always submit monthly training reports as required by Technical Specification 6. 8 and QI-2 PR/PSL-2 paragraph 4.4.4.
Departments involved include Mechanical Maintenance, Health Physics, Instrument and Control, Quality Control, Reactor Engineering and Technical Staff.
(Unresolved 335/81-02-06)
Failure of Licensed Operators to Complete Requalification Training as Required by
CFR 55 and Administrative Procedure 005720 paragraph 8. 1. 1 and 8.3. 1.
Three licensed operators apparently did not participate in the six week thermodynamics course nor.take the examinations,,
g.
(Unresolved 335/81-02-07)
Failure to Perform QC Surveillance on the Training Department as Required by Technical Specification 6.8 and
.. QI-.2PR/P.S.L-,2. par agr aph 4;6.
h.
(Unresolved 335/81-02-08)
Failure to Insure QA Program Implementation by Objective Evidence.
The following QA Audit Checklists were reviewed for indications of objective evidence.
Each item listed revealed a
failure on the part of the auditor to ensure QA pr'ogram implementation.
QAO-PSL-80-08-200 Sheet 4/7, item 8; Sheet 2/7, item 5 QAO-PSL-80-05-193'heet 4/25, item.8.'J QAO-PSL-.80;
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Sheet 4/12,, item 7.a and 7.b QAO-PSL-80-.189 Sheet 4/12, item 10; Sheet 3/12, item 9.C
!'AO-PSL-80-05-193, Sheet 4/25, item 8.J required the auditor to ensure retraining had been accomplished.
The auditor reported he attended a
mul'imedia training session"for new security'personnel'.
There was no'"
j'n'dicati'on that security personnel. retraining had'been accomplished.
QAO'-PSL-80-04-189, Sheet 4/12, item 10, required the auditor to ensure
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'that 'the plant "had
'a 'raining'rog'ram 'that included. a'etraining
program for maintaining proficiency.
There was no objective evidence to ensure implementation.
Sheet 3/12, item 9.c of the same audit required the auditor to ensure that QC,had conducted inspections, monitoring, surveillance, and review
... of..plant activities'.
The. evidence.documented.:by:,the'audi.torconsisted.'.
of..reference:to.QI-1-1, defining QC.responsibilities..
. i...: (Unresolved 335/81.-02-.'09) 'Failure. to Conduct. Audits..of Power, Resources
'.':- Staff "and Qua'lity Assurance Committee:
'The Corporate.Office Power-Resources Staff and the Quality Assurance Committee are both identified in Topical Quality Requirement 1.0, Section 1.2 as having specific organizational responsibilities for implementation of the QA Program.
The Quality Assurance Committee apparently has not been audited as of December'1980; and the Power'Resources
'Staff has apparently not been" audited since October 6, 1975.
e V
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10 CFR 50,Appendix B, Criterion 18, requires periodic audits be carried out to verify compliance with all aspects of the Quality Assurance Program, as implemented by FPL Topical Quality Requirement 18.2.2, requiring that the applicable elements of the internal and onsite programs be audited once every two years.
(Unresolved 50-335/81-02-10)
Failure to have an Adequately Detailed Quality Control Surveillance Program.
QI-10 PR/PSL, QI-18 PR/PSL-2 and QI-18 PR/PSL-3 do not appear to contain adequate program details.
QI-5 PR/PSL-1 section 5.2.6 does not appear to provide adequate guidance.
(Unr'e'sol'ved" 035/81-0241)"" Fai.l'ur'e 'o".Include'quip'ment" Clear'i'nce'.'
" '"
Procedures in Maintenance and Surveillance Instructions and to Obtain Proper Approval of Equipment Clearance Procedures.
II (Unresol ved 335/81-02-12)
Fai 1 ure to Identi fy, 'n the maintenance program, when a procedure is needed to accomplish work activities.
(Unresolved 335/81-02-13)
Inadequate Plant Work Orders (PWO).
PWO 2928 for "A" Low Pressure Safety Injection (LPSI)
Pump and 2929 for "A" Containment Spray Pump (CSP) instructed mechanics to tighten bolts as necessary.
The results are reported to be:
A LPSI pump-flange bolts
,turned 4 flats, casing bolts turned 2 flats; A
CSP -slugging wrench used and bolts could.not be ti:ghtened.
Bolts were very, tight.
n.
o.
The scope of PWO 2997 for A LPSI pump was= exceeded.
(Unresol,ved 335/81-02-,14), Failure to Maintain Records of the Operating Cycles of, Technical Specifica'tion Table 5.9.-1.
(Unresol ved 335/81-02-15)
Failure to Obtain Faci 1 ity Review Group Approval of Changes to Letter of Instruction 0-9 Baseline Data as
'R'equired by Techn'ical S'pecifi'cat'ion'6.'8'.'2.
P
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(Unresolved 335/81-02-16)
Failure to Obtain Facility Review Group Approval Prior to Changes to Administrative Procedure AP 0010123.
(Control of valves, locks, and switches).
q. '(Unresolved 335/81-02-.17). Program for Evaluation of Operational',Events and Initiatiqg Report's t'o.the NRC:
An. adequate program.is not apparent
"'".";:;:::.to:.c'al'.l':e'ct; documeiit'.'eval.uat'e',.,.alid;wh'ere n'eces'sarp:,>.repor't'.to
'.the 'NRC ".'.'
-"., :
. significant deviatjons
..in.operation,.'dherence
.'to procedures, and,
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pr'ocedural'nadequacy.
'to ensure that-these
'items:are brought. to management attention, corrected, and reported as necessary.
e (Unresolved 335/81-02-18)
Establishment of Independent Verification of Operational Activities.
The Quality Assurance Program does not address independent verification of activities although 'NSI N18.7-1972 does..
This area is currently being addressed under the TMI Action Plan, NUREG"0737;I tern"I;C. 6..'.
s.
(Unresolved 335/81-02-19)
Certain Facility Instructors do not hold a Senior Reactor Operator's License Contrary to a NRC letter from Harold Denton to Licensees dated March 28, 1980.
This item is unresolved pending NRC Office of Nuclear Reactor Regulation review of FPL letter L-81-6 of January 6,
1981, which forwards the St.
Lucie Licensed Operator Requalification Program for review.
This letter addresses this unresolved item.
10.
Review of Plant Procedures to Determine Availability of Instruction for Operator s in Case Automatic Reactor Trip Fails to Occur (Anticipated
'. 'The.'ins'pector-was 're'questedby "IE Headqoart'ers to -i"evi'ew p'lant'>roc'e'dur'es for the existance of directions to operators in case automatic reactor trip (ATWS) failed to occur.
The results of that review are summarized below:
'I a.
The licensee does not have an ATWS procedure as such.
b.
Existing plant procedures listed below were reviewed in accordance with Inspection Requirements and Acceptance Criteria.
Comments are included.
Administrative Controls:
. 00/0/20,,'ev ll, Duties and Responsibilities of Operators on Shift.
Nuclear c'ontrol'enter operator given authority and responsibility to shut reactor, down when operating parameters exceed reactor protection circuit setpoints and automatic shutdown does not occur or if operator determines that safety of the reactor is in jeopardy.
Off-normal Operating'rocedures:
(1)
0030130 Rev 9, Shutdown Resulting From Reactor Trip or Turbine Trip.'tandard Post.-Tr'ip 'mmediate 'ctions include tripping turbine and reactor manually ensuring all full-length CEA's are fully inserted and reactor trip breakers are open, and manual initiation of any automatic function that failed to occur.
Subsequent operator actions include emergency boration if shutdown margin is below technical specification requirements.
(2)
0030140 Rev 18.,
Blackout Operation.
Standard Immediate Actions
.:....'.,- -:,:..'.,'..,.,". inc'1ude t'ripping'turbi're.'and",reactor manually,: 'checking al.l fu'll
length, CEA's.,are fully inserted and,-reactor 'trip breakers are open,'nd manual.initiation of any automatic function that failed to occur.
Subsequent actions include boration to cold shutdown conditions.
(3)
0110030 Rev
FLCEA Off-normal Operation and Realignment.
This procedure addresses.
various cases of rod position/dropped rod problems.
Each sub-procedure has a statement to "Insure automatic functions have initiated"
~.
(4)
(5)
0120035 Rev
Pressurizer Pressure and Level Off-Normal Operation.
This procedure lists pressurizer pressure as a Reactor Trip signal.
0120040 Rev 7 -
Loss of Reactor Coolant Pump Flow/Natural Circulation.
This procedure includes boration to maintain required shutdown margin and sampling the Reactor Coolant System at several places since boron concentration may not be uniform.
It also includes a
reference to carryout immediate operator actions for reactor trip.
..., (6);. 0120041 Rev.8
.-. Steam. Generat'or.
Tube. Leak/Failure."
This. procedure
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'all's 'for shutdown-o'ot'standby u'nder'c'e'r'tain conditi'ons'.'7)
0120042 Rev
Loss of Reactor Coolant.
'fhis procedure refers to procedure
=.(1).above.
(8)
(9)
0250030 Rev
Emergency Boration.
This procedure lists conditions requiring emergency boration under three categories:
(a)
Unanticipated or uncontrolled Reactor Coolant System cooldown following a trip (b)
Unexplained or uncontrolled reactivity increase (c)
Loss of shutdown margin 0250031 Rev
Boron Concentration Control Off-Normal.
This procedure provides instructions for operating the Boron Concen-tration Control System (BCgS)
and maintain Volume Control Tank level when the BCCS has various malfuncti'ons.
(10) 0700040 Rev 8 Loss of Feedwater or Steam Generator Levels This procedure refers to procedure('1)in case of reactor trip.
0810040 Rev
Main Steam Line Break.
This procedure refers to procedure (1).
(12)
1210030 Rev
Wide Range Nuclear Instrumentation Channel Mal-function. 'eactorTrip is li,sted. as an automatic action under certain.condi tions.
(13)
1220030 Rev. 3 - Linear'ower Range Channel Malfunction.. Reactor Trip is listed as an automatic action under certain conditions.
c.
FPL letter L-80-418 of December 23, 1980 (Uhrig Eisenhut; Post TMI Requirements)
indicates that ATWS accident guidelines are being pursued by the C-E owners group under NUREG 0737 Item I.c. P ll.
Review of Plant Operations The inspector was kept informed on a daily basis of the overall plant status and of 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, of plant housekeeping and vital area controls.
, -',Ouring:a...plant-tour:.on".January 6, )983.;.the 'inspector, observed. several...opep-
".'. '
'
floo'r cab1e penetrations
<<'i>i theabTe spreadsn'groom.""'The'se all'ad=
recently installed cables in them except one which had in it a length of temporary plastic tubing run from the drain of a nearby air conditioning coil unt.
,The.inspector:informed l.icensee management (nuclear plant. super-
. :
visor) of the situation at the time and again on January 16, 1981, at a
management interview.
The licensee stated that a roving patrol check of the room was initiated on January 16 in accordance with Technical Specification 3.7.12.a.
Failure to establish a fire watch patrol of the cable spreading room when the cable penetrations were first breached appears to be in violation of Technical Specification 3.7. 12.a which requires within one hour of electrical penetrations not, being intact, in a
room protected by fire detectors, that a roving fire watch patrol be established to inspect the penetrations at least once per hour.
(Violation 335/81-02-20).
P,y