IR 05000335/1982015

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IE Insp Repts 50-335/82-15 & 50-389/82-21 on 820411-0514. Noncompliance Noted:Failure to Implement Procedure for Locking Safety Valves in Required Position
ML20058H607
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 06/11/1982
From: Bibb H, Elrod S, Julian C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20058H555 List:
References
50-335-82-15, 50-389-82-21, NUDOCS 8208030641
Download: ML20058H607 (8)


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  1. o, UNITED STATES 8' 3, NUCLEAR REGULATORY COMMISSION y E REGION li 2 101 MARIETTA hT., N.W., SUITE 3100 of ATLANTA, GEORGIA 30303

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a Report Nos. 50-335/82-15 and 50-389/82-21 Licensee: Florida Power and Light Cmpany 9250 West Flagler Street Miami, FL 33152 FaciIity Name: St. Imcie Unit 1 and 2 Docket Nos. 50-335 and 50-389 License Nos. DPR-67 and CPFR-144 Inspection at St. Lucie site near Ft. Pierce, Florida inspectors: Ig// fA 4t.4 l jO l i M S. A. Elrod(/ (_/ Date Signed l 4&fh Al% l0.IiEA H. E. Bibb~ g/ () hte Signed Approved by:

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r) w( /// b C. A. Julian', Section Chief, Division of "Date Signed Project and Resident Programs SLM MRY Inspection on April 11 - May 14,1982 Areas Inspected This routine, inspection involved 199 resident inspector-hours on site in the areas of Plant Operations, Surveillance, t,bintenance, Procedures, Bulletins, Reactor Coolant System Leakage, Fire in radiation controlled area, and Licensee action on previous inspection findings and inspector followup itom Results Of the nine areas inspected, no violations or deviations were identified in 8 areas; one apparent violation was found in one area (inadequate Procedure -

Paragraph 5).

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8208030641 820726 PDR ADOCK 05000335 PDR G

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DETAILS Persons Contacted Licensee Enployees

  • C. M. Wetby, Plant Abnager J. H. Barrow, Operations Superintendent J. E. Bowers, Maintenance Superinterdent
  • D. A. Sager, Operations Supervisor
  • N. G. Roos, Quality Control Supervisor R. J. Frechette, Gemistry Supervisor C. F. Leppia, instrunent and Control Supervisor P. L. Fincher, Training Supervisor R. R. Jennings, Technical Departnent Supervisor C. A. Pell, Reactor Engineering Supervisor H. F. Buchanan, llealth R1ysics Supervisor J. G. West, Security Supervisor J. Barrow, Fire Prevention Coordinator O. D. Hayes, Nuclear Plant Supervisor L. W. Pearce, POclear Plant Supervisor N. D. West, ibclear Plant Supervisor C. L. Burton, Nuclear Plant Supervisor M. B. Vincent, Assistant Plant Superintendent - Electrical T. A. Dillard, Assistant Plant Superintendent - Mechanical
  • A. W. Bailey, Quality Assurance Supervisor
  • B. J. Escue, Si te Manager
  • N. T. Weems, Assistant Abnager (% -PSL E. W. Shenmn, GA Engineer
  • E. Crowell, Site Engineering Supervisor G. J. Boissy, Startup Superintendent Other licensee mployees contacted included construction craf tstren, technicians, operators, mechanics, securi ty force menbers and office personne Other Organizations Ebasco, Mr. Ocorge Wood
  • Attended exit interview Exit interview The inspection scope and findings were su1marized on May 14, 1982, with those persons indicated in paragraph 1 above. For Unit 2, the applicant confirmea that previously conducted hydrostatic tests were to be evaluated

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for possible damage caused to adjacent portions of systems not protected by l safety valves.

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. Licensee Action,on Previous inspection i
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, (Closed-Uni t 1) Unresolved I tcm 335/81-18-04 " Operation of Equirment with

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Quali ty Control ik>ld Tags Attached." s ~

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. Subsequent investigation showed that;a systcm to control " hold" imterial existed but ' that the trechanism for conth tlonal release wasn' t ctearly

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visible. Tne inspector reviewed QI 10-PR/PSL-1 Revision 6, Qi 14-iM/PSL-1 Pevision 5,'and Q1 16 m/PSL-1 Revision 9. The process for conditional re' lease' of " hold" rmterial is now cleare ,

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Unresolvvi itafis were not identifiedduringIhisinspectio \

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The inspector obserytd cor. trol roun operations, revieded applicable , logs and -i

] conducted discussions with control rocm operators during the report perio '

, The ,instw.dtor verified the operabiii ty of seledted umrgency systems, ,

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revieweds tagout records and veri fied proper return to service of affected ,

cmponents.TTours of the reactor, auxiliary and turbine buildings were '

conducted to observe plant equipmnt conditions, inc!uding potential fire hazards,(fli.$1d leaks, and excessive vibrations and to verify that rmin-tenance requests had been initiated for equipnent in need of rmintenanc The inspec(or by observation and direct interviewgerified that the physical , ',

securi ty pidn was being inplemented i,n aqcordance vj th the station securi ty -

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\ Theinspector,observedplanthousekeepibg/cleanlinessconditionsand*

verified ivpimentation of radiation protection controls. The inspedtor -

walked dom the accessible portions of contairnent spray systen to vel i fy operability. During the walldown, the inspector noted a valve with a lock ,

and chairi dra'ped around the 'vaiv slbonnet but not locked through the hand vAicci as' required by Adminisiratlye Procedure 0010123, Mninistrative .

Control of Valves, Locks and Swncnes. The position of the valves Iisted in this procedure is veri ficd once per q'uarter. However, when a plant equipmnt clearance is issued to reposition one of these valves to accurplish needed repair '(as was the case wi th this valve, V-7166; opened to e drain a header to repair an adjacentWalve bonnet leak), there is not wri ttdn,' posi tive means to assure that the valve is reposi t ioned a "lockect" closed. Operating Procedure 0010122, IrePf ant equipnent Clearance ,

Order;, addresses itseif to assuring that the valve,isjreturned to its

cor rect posi tion, but doe's not nention veri fylry that locks and chains are ,

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rehung where required. This_ constitutes a vloidt10:0 (50-335/82-15-01) nf /

failure to inplanent the procedure for locking safety-related valves in

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6. SurveiiIance Observation Duriry the inspection period, the inspector verified plant operations cmpilance with at least sixteen different technical specification requ:re-ments. Systerns observed included refueling water tank, contairrnent spray,

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diesel generators, reactor coolant systmlleakage, chemistry, pressure /

tmperature Iimi ts, ard other The inspector reviewed operating procedure 0120051, Rev. 6, Reactor Coolant

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System Flow Verification by Calorimetrics, for cmpleteness, technical L accuracy, approval, etc. Final flow calculation was found to agree with the

, previous detennination wi thin 0.5%. The inspector verified that testiry was performed in accordance with adequate procedures, test instrtmentation was calibrated, limi ting condi tions for operation were rnet, rmuval and restora-tion of the af fected cmponents were properly accmplished, test results met requirarents and were reviewed by personnel other than the individual directing the test, and that any deficiencies identified during the testiry were properly reviewed and resolved by appropriate nunagenent personnel .

No violations or deviations were identifled in this are . Maintenance Observation Station rmintenance activities of safety-related systmis and conponents

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listed below were observed / reviewed to ascertain that they were conducted in accordance wi th requirmients. The foilowing itans were considered during this review: the limiting conditions for operation were met; activi ties were accmplished using approved procedures; functional testing and/or calibrations were performed prior to returning conponents or systems to service; quality control records h were nuintained; activities were accmpiished by qua1ified personnei; j' parts and nuterials used were properly certified; and radiological controls were inplemented as required. Work requests were reviewed to detennine status of outstanding jobs and to assure that priority is '

j assigned to safety-related equipnent rmintenance which nuy af fect r systun perfonmnce. The foilowing nuintenance activities were

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observed / reviewed:

On Tuesday, April 20, 1982 the inspector reviewed Plant Work Order No. 7054, which performed work on Pressure hidicator 2208. A gage that senses pressure on the "B" boric acid punp discharge. The sensing iine was pitgged and the gage indicated no pressure. A heat

,, imp was placed on the sensing iine for one hour and then the 1A and l 1B boric acid pmps were run to verify unplugging of the sensing lin Discussions with plant ILC personnel indicate this to be a continuing

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probl an. The nuin piping is heat traced up to an isolation diaphragm,

! but the capillary tube from the diaphragn to the gage is exposed and j not heat traced.

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On Tuesday, /prii 20, 1982, the inspector conducted an in depth review of Plant Work Order No. 2733 which performed work on the "B" charging pmp. No inadequacies were observe No violations or deviations were identified in this area.

i IE Bulletins / Circulars /information Notices

. The following IE Bulletins were reviewed to determine whether they have been received and reviewed by appropriate tronagment, responses, where necessary, were accurate and cmplete, and that action taken, i f required, was cmpl et ' (Closed-Unit 2)lE Bulletin 77-01 - Pnumatic Tirrn Delay Relay Set Point Drift - closed based on review of applicant investigation which shows that the subject relays are not used at St. Lucie Unit Ajastat series 7000 relays are used.

! (Closed - Unit 2) lE Bulletin 77-02 - Potential Failure Usechanisms in

certain Westinghouse "AR" relays with latch attactments. Closed based

on applicant investigation which shows that the only AR type relay is used in the turbine scal-oil pmp rrotor starter. That relay is a non-latch mode (Reopened - Unit 2) IE But letin 77-04 - FH of contaiment smp water

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following LOCA. Previously closed in report 389/78-04 - rcopened j perding review by applicant and inspector.

I (Reopened - Unit 2) IE Bulletin 77-05/77-05A - Electrical Connector Assmbl ics. Previously closed in report 389/78-04-reopened pending

! review by the applicant and inspecto (Closed - Uni t 2) IE Bulletin 77-06, Potential Problems with Contain-rrent Electrical Penetration Assmblies. This bulletin was sent to

! operating plants. A similar bulletin, IEB 77-07, was sent to construction plant IED 77-06 is closed as "not applicabic." '

' (Reopened - Linit 2) IE Bulletin 77-08 - Assurance of Safety and Safeguards During an &nergency - previously closed in 389/78-0 Reopened pending security inspectio (Reopened - Unit 2) IE Bulletin 78-05 - Mal function of Circuit Breaker Auxiliary Contact Mechanism. Previously closed in 389/79-09. Reopened pending futher applicant reviewe (Reopened - Unit 2) IE Bulletin 78-07 - Protection Provided by Air i.ine Respirators and Supplied Air floods. Previously inspected in 389/78-1 Reopened pending health physics inspection.

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5 (Reopened - Uiit 2) IE Bulletin 78-08 - Radiation from Fuel Elanent Transfer Tubes. Previously inspected in 389/78-10. Reopened pending health physics inspection, (Closed - Unit 2) IE Bulletin 78-10 Bergen - Patterson Shock Suppresor Accurulator Sprirg Coils. Closed based on FPL investigation and docunentation in a memo to file that the subject shock suppressors are not used at St. Imcie Unit (Closed - Unit 2) IE Dulletin 79-04 incorrect Weights for Swing Check Valves Manufactured by Velan Engineerirg Corp. Closed based on review of the applicants reveri fication that Velan valves are not used at the St. Imcie 2 si te. This vendor was removed fran the bidders list in 1980. This is an update of inspection report 389/79-0 (Closed - Unit 2) IE Bulletin 79-25 Failures of Westinghouse BFD relays i n Sa fe ty-Re l a t ed Systems. Closed based on the applicant confirming that subject relays were not used and that none are ordered for stores as unit 2 spares. This is an update of inspection report 389/80-0 (Closed - Unit 2) IE Bulletin 79-27 Loss of Non-Class 1E instrunenta-tion and Control Power System Bus During Power Operation. Ahlini-stratively closed because it is specificallsf adressed in the FSH at question 420.1. This also incorporates IE Circular 79-02 and Infonmtion Notice 79-2 (Cl e, sed) - Un i t s 1 and 2 ) IE Bulletin (IEB) 81-02 and Supplement Failure of Cate Type Valves to Close Ajainst Differential Pressur (Unit 1) The IEB and Supplement are closed based on review of Iicensee responses and consultation with the Region iI cognizant inspecto Licensee responses L-81-204 of May 14,1981, L-81-432 of October 5, 1981 and L-81-515 of Decenter 7,1981 show that St.1.ucie 1 has one subject valve, however analysis showed that no corrective action was neede (01it 2) The IEB and Supplement are closed based on review of correspondence, procedures and documntation in conjunction with interviews with the responsible engineer who supervised repair Li terature reviewed included FPL response L-81-289 of July 14, 1981; 10 CFR 50.55(e) 389/81-002 final report L-81-480 dated Novenber 16, 1981; Nonconfonmnce report 3109 AE dated February 15, 1982; Inspection report AE 820644 with attached valve repair procedure; Westinghouse trip report no. Engineerirg 81-14 The licensee and contractors have rrodified the operators for sum twenty eight valves. Control wiring diagrams were changed for those va Ives requ i r i rg pos i t i on I imi t ra ther than to rque I imi t . The i

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technical trunual for the valves has yet to be charged to show the new settings, however the NSSS vender was aware of this need and was pursuirg the change. Construction Deficiency Report 50.55(c)

389/81-002 is also closed, (Closed - Units 1 and 2) lE Bulletin 82-01 and 82-01 Revision Alteration of Radiographs of Welds in Piping Sub-assmblics. Bis IEB was sent to St. Lucie for information. h is inspector discussed the IEB with other Region iI inspectors who had been personnally involved with interpretation of radiographs at St. Lucie. Such alterations did not appear to be a problon at St. Luci (Closed - Unit 2) IE Circular 79-02 Failure of 120V Vital Power Supplies. This is an update of inspection report 79-12. Bis _ lEC was re-reviewed by the applicant as part of the response to FSAR question 42 (IE Bulletin 79-27). This circular is achtinistratively closed based on inclusion in the FS (Closed - Unit 2) IE Circular 81-06 - Potential Deficiency Af fcctiry Certain Foxboro 10-50 f,W Transrai tters. - Closed based on applicants findings that they do not use 10-50 f.M transmitter systan (Closed - Unit 2) IE Infonmtion Notice 79-29 Loss of Non-Safety-Related RCS Instrmentation During Operation. Mninistratively closed because it is included in IEB 79-2 . Reactor Coolant Systan Unidenti fied Leakage above 1 GRd h e operators observed the reactor cavity in-leakage to increase rapidly about 2:15 p.rn. on April 24. Confirming indications included stnp level and contalrnent particulate alanns at the alert and high Icvels. The operators conducted a contairment entry and found a leak blowiry steam at the location of the pressurizer cubicle. The clouds of steam stopped when spray control valve 1100F was isolated locally. A leak rate calculation confirmed the stopping of the leak. W e licensee stated-the intention to investigate the problem during an upcoming scheduled outage.

The inspector reviewed this event for both technical and procedural aspects

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including reportirg criteria, procedure adherene, and plant aligruent af ter the event.

I No violations or deviation were identified duriry this event.

10. Fire in Radiation Controlled Area l

l On April 21, 1982 a snull fire was found and extinguished in the radioactive l waste drmming room. The inspector attended the critique that sane af ter-

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Worieren disnuntIing a concrete block walI had been cutting rebar with an oxy-acetylene torch. Apparently a piece of hot rebar fell on a piece of polyethylene bagging nuterial, igniting it after a couple of minute Worfmen had lef t the area for a brea The fire was noticed by a HP supervisor who innediatley reported it. The fire brigade responded and the fire was extinguished within 5 minutes of notification. There were no injuries, no penmnent danuge, no release of radiactive nuterials, and no exposure of personnel. All involved were given whole body count No violations or deviations were identified during this even . Hydrostatic Test Procedures - Unit 2 During this inspection period the inspector reviaved SQP-14 Revision Integri ty Testing; Quality Instruction QI 10.78, Revision 1 - Integrity Testing Inspection and interviewed supervising personnel in this are It was ascertained that SQP-14 did not specify that connected piping and equiptent adjacent to but outside hydrostatic test boundaries nust be protected frcm overpressurization. SQP-14 did not require any doctmentation of this protection. QI 10.78 did not require any inspection of such protectio At the request of the inspector, Construction Test nom CT-027-82 was issued to clari fy SQP 14. The applicant has cmmitted to establish a program to evaluate the sone 1200 previous Hydrostatic Tests to demonstrate there was no danuge to adjacent portions of systens. At the conclusion of this inspection, the detailed process had not been defined. This will be followed up by the inspector (389/82-21-01).

12. Licensee Action on Previously identi fied I tcms (Closed - Unit 1) Inspector Foilowup Item 335/82-05-01. The inspector reviewed Rev.18 of Operating Procedure 0410021, Safety injection Tank Nonml Operation and noted that four valves, previously identified as

" locked closed" had been changed to " closed." These valves have been l determined to not require strict achinistrative control.

! (Closed) IFl 335/77-19-01 - Conflicting nuxintm valve closure tines

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included in Technical Specifications (TS). This itcm originated from l Licensee Event Report 77-38 and resulting TS change request L-79-4 License amendnent No. 49 resolves this issue. D e inspector had no further questions at this tin (Closed) IFl 335/80-35-06 - Procedures for review of logs and check lists. His i tcm was reviewed during inspection 82-03 but not specifically addressed in the inspection report. The resident

. inspectors as well as these involved in 82-03 have not identified ( review of logs and checklists as an area with perfomunce probians.

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The inspector had no further questions at this tine.

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