IR 05000498/1988047: Difference between revisions

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{{Adams
{{Adams
| number = ML20153E628
| number = ML20206B798
| issue date = 08/29/1988
| issue date = 11/07/1988
| title = Insp Repts 50-498/88-47 & 50-499/88-47 on 880701-31. Violations Noted.Major Areas Inspected:Esf Sys Walkdown, Monthly Surveillance Observation & Operational Safety Verification
| title = Ack Receipt of 880929 Ltr Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-498/88-47 & 50-499/88-47
| author name = Bess J, Garrison D, Holler E
| author name = Callan L
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
| addressee name =  
| addressee name = Goldberg J
| addressee affiliation =  
| addressee affiliation = HOUSTON LIGHTING & POWER CO.
| docket = 05000498, 05000499
| docket = 05000498, 05000499
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = 50-498-88-47, 50-499-88-47, NUDOCS 8809060370
| document report number = NUDOCS 8811160022
| package number = ML20153E606
| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS
| page count = 2
| page count = 10
}}
}}


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Docket . 4''9 68-47 o 19/88-47 Houston Lighting & Power Company ATTN: J. H. Goldberg, Group Vice President, fiuclear P.O. Box 1700 Houston, Texas 77001 Gentlemen:
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Thank you for your letter of September 29, 1988, in response to our letter and Notice of Violation dated August 31, 198 We have reviewed your reply and find it responsive to the concerns raised in our fiotice of Violation. We will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintaine Sincerel Origiral t tri. ! r,y A. P R 4eh L. J. Callan Director Division of Reactor Projects CC:
i      APPENDIX B I U. S. NUCLEAR REGULATORY C0hMISSION      l REGION IV  ,
Houston Lighting & Power Company ATTN: M. A. McBurnett,tianager Operations Support Licensing P.O. Box 289 Wadsworth Texas 77483 Houston Lighting & Power Company ATTN: Gerald E. Vaughn, Vice F.esident F : lear Operations P.O. Box 289 Wadsworth, Texas 77483 Houston Lighting & Power Company ATTN: J. T. Westerneier, General Manager South Texas Project P.O. Box 289 Wadsworth, Texas 77483 ,
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l  NRC Inspection Report:  50-498/88-47  Operating License: NPF-76'
11/4/88 G811160022 831107    / il PDR ADOCN 05000 pt'
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50-499/88-47 ConstructionPermit(CP):.CPPR-129  l Dockets: 50-498          -
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]  Licensee: Houston Lighting & Power Company (HL&P)      i
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j  Facility Name: South Texas Project, Units 1 and 2 (STP)
1  Inspection At: STP, Matagorda County, Texas        l l            {
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Inspection Conducted:         ;
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(   f.E. Bess,SeniorResidentInspector, Section D Division of Reactor Projects  Project    l
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D. L. Garrison Resident Inspector, Project SfM/t V Date  I
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Houston Lighting & Power Company  -2-Central Power & Light Company ATTN:  R. L. Range /R. P. Verret P.O. Box 2121 Corpus Christi Texas 78403 City of Austin Electric Utility ATTN:  R. J. Miner, Chief Operating Officer 721 Barton Springs Road Austin, Texas 78704 Newman & Holtzinger, ATTN:  J. R. Neunan, Esquire 1615 L Street, Washington, D.C. 20036
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Houston Lighting & Power Company ATTN:  S. L. Rosen P.O. Box 289 Wadsworth, Texas 77483 Houston Lighting & Power Company ATTN:  R. W. Chewning, Chairman Nuclear Safety Review Board P.O. Box 289 Wadsworth, Texas 77483
'- City Public Service Board
; ATTN:  R. J. Costello/M. T. Hardt P.O. Box 1771 San Antonio, Texas 78296
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Houston Lighting & Power Company ATTN: Licensing Representative Suite 610 Three Metro Center Bethesda, Maryland 20814 Texas Radiation Control Program Director bectoDMB(IE01)
bec distrib, by RIV:
DRP    RRI-0PS SectionChief(DRP/D)    DRS MIS System    RPS-DRSS Lisa Shea, RM/ALF    RIV File R. Bachmann, OGC    RSTS Operator G. Dick, NRR Project Manager (MS:  13-D-18)
Project Engineer, DRP/D   RRI-CONST R. D. Martin
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Division of Reactor Projects      !
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j  Inspection Conducted July 1-31, 1988 (Report 50-498/88-47)       I l
t The Light company  PO. Box 1769 Ilouston. Texas 77001 (713) 228 9211 llouston Lighting k Power    .- -. ... --
I Areas Inspected: Routine, unannounced inspection included onsite followup of      !
September 29. 1988 ST-HL-AE-2805 Tile No.: G02. 04- -
j events, engineered safety feature system walkdown, monthly surveillance      !
10CTR2.201 gd,(b)[lil r[m -
  ; observation, operational safety verificatio ;
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i M ocr s ms U. S. Nuclear Regulatory Corresission Attention: Document Control Desk i
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Vashington, DC 20555
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South Texas Proj ect Electric Generating Station Unit 1 Docket No. STN 50-498 Response to Notice of Violation 498/8547-01 Houston Lighting & Power Company (HL&P) has reviewed Notice of Violation 498/8847-01 dated August 31, 1988. HL&P concurs that the cited violations occurred. These Licensee violations were fully addressed as the subject of the attached Licensee Event Reports. The status of actions addressed in the attached is up.iated as follows:
Licensee Event Report 88-040, "Ta11ure to Stagger Reactor Trip Breaker Surveillance Test Intervals" Corrective actions described in the attached LER have been complete Licensee Event Report 88-043, "Tailure to Perform Surveillance Test of Diesel Generator Fuel 011 for Centamination" Corrective actions described in the attached LER have been complete Appropriate actions have been taken to ensure co pitance in the futur If yod should have any questions on this matter, please contact Mr. H. A. McBurnett at (512) 972-$53 f G. E. Vaughn Vice President Nuclear Plant OpSrations GEV/PLV/n1 Attachments: 1) Licensee Event Peport 88-040  *
2) Licensee Event Report 88-043 A Subs dia:Y of 11ouston Industries Incorporated
, (h NL 88.263.02
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flouston Lighting & Power Company ST-HL-AE-2805 Tile No.: G02.04 Page 2 CCI Regional Administrator, Region IV Rufus S. Scott Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Associated General Counsel Arlington, TX 76011  Houston Lighting & Power Company P. O. Box 1700 Houston, TX 72001 George Dick U. S. Nuclear Regulatory Commission INFO  -
Washington, DC 20555 Records Center 1100 Circle 75 Ptrkway Jack E. Icss Atlanta, Ga. 303D9-3064 Resident Inspector / Operations c/o U. S. Nuclear Regulatory Commission Dr. Joseph M. Hent le P. O. Box 910  50 Be11 port Lane Bay City, TX 77414 Be11 port, NY 11743 J. I. Tapia Senior Rerident Inspector /Const.uction c/o U. S. Nuclear Regulatory Commission P. O. Box 910 Bay City, TX 77414 J. R. Newman, Esquire Newman & Holtzinger, L Street, Washington, DC 20036 R. L. Range /R P. Verret l Central Power & Light Company P. O. Box 2121 Corpus Christi. TX 78403 R. John Miner (2 copies)
Chief Operating Officer City of Auktin Electric Utility 721 Barton Springs Road Austin, TX 78704 R. J. Costello/M. T. Hardt City Public Service Board P. O. Box 1771 San Antonio, TX 78296
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Revised 05/24/88 NL.DIST


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P.O. Box 1700 Houston. Texas 77001 (713) 228 9211
. Houston Lighting As Power  ,
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July 25, 1988 ST-HL-AZ-2732 Tile No.: G26
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10CTR50.73
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U. S. Nuclear Regulatory :'or:rsission Attention: Docurtant Control Desk Washington, DC 20555 South Texas Project Electric Generating Station Unit 1 Docket No. STN 50-498 License Event Report 88-040 Regarding Tailure to Staeter Reactor Trip 3reaker Surveillance Test Intervals Fursuant to 10CTR50.73. Houston Lighting & Power (ML&P) Submits the attached Licensee Event Report (LER 88-040) reg'hrding f.ailure to stagger reactor trip breaker surveillance test intervals. This event did not have any
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adverse impact on the health and safety of the publi If you should have any questions on th.s matter, please contact Mr. C.A. Ayala at (512) 972-862 G. E. Vaughn Vice Tresident Nuclear Flant Operations GEY/3EN/pv Attachment: LER 88-040 l
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A Subsidiary of Houston Industrie, Incorporated  '
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Regional Administrator, Region IV
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Nuclear Regulatory Commission  Rufus S. Scott '
611 Ryan Plaza Driva, Suite 1000 Associated General Counsel Arlington, TX 76011  Houston Lighting & Powe- Company
      , P. O. Box 1700 George Dick
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Houston, 72 77001 U. S. Nuclear Regulatory Commission INPO Washington, DC 20555    ,
Records Center J1ck E. Bess  1100 circle 75 Parkway Resident Inspector / Operations  Atlanta, Ga. 30339-3064 c/a U. S. Nuclear Regulatory Commission Dr. Joseph H. Hendrie P, O. Box 910 Bay City. TX 77414  50 Bellport Lane Be11 port, NY 11713 Don L. Garrison Resident Inspector / Construction
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Newman & Holtzinger, Street, Washington, DC 20036 R. L. Range /R. P. Verret Central Power & Light Company    i P. O. Box 21:1 Corpus Christi. TX 78403 R. John Miner (2 copies)
;  Chief Operating Officer City of Austin Electric Utility    l 721 Barton Springs Road Austin, TX 78704
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R. J. Costello/M. T. Hardt    *
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San Antonio, TX 78296    ,
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  .82.act,b  ,= .... -. -  - -  ,nu On June 23, 1988, during the annual review of the plant surveillance database as required by procedure, the HL&P Plant Surveillance Coordinator identified that the surveillances associated with Technical Specification 4.3.1.1 and 4.3.2.1 vere scheduled with a method that could result in improper staggering of test inte rval Subsequent review by the responsible Divisional Surveillance Coerdinator identified that the surveillance tests for the Reactor Trip Breakers undervoltage and shunt trip devices did not meet the staggered test basis requirement between June 20, 1988 and June 23, 198 However, the tests were performed within their required interva * Surveillance testing for n. other divisions was also reviewed for proper application of the staggtred test basis. The root cause was determined to be f ailure of the surveilia. s e test program to properly schedule and review staggered tests. Cort  '
cive actions include revision to the method for scheduling staggered surveillances and creation of a Surveillance Program Task Force Subcommittee to study staggered test basis surveillance .
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UCENSEE EVENT REPORT (LER) TEXT CONTINUATION
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DESCRIPTION OF OCCURRENCE:
On June 23, 1988, during the annual review of the plant surveillance database as required by procedure, the HL&P Plant Surveillance Coordinator identified that the surveillances associated with Technical Specification  .
4.3.1.'1 staggerlagandof4.3. were scheduled with a method that could result test interval in improper scheduling,  This method, known as frequency based determines the next due date for a given surveillance by' adding the surveillance interval to the last date the surveillance was performed and  '
adjusting the due date as required by Technical Specification 4.c.2. The result of this calculation issures that tha surveillance interval for each train (equalmeets to thethetest Technical Specification requirement, however, the stagger redundant trains mayinterval divided by the number of trains) between tests of not remain constan Upon the discovery of the error in the scheduling method used, the Plant Surveillance Coordinator requested the responsible Divisional Surveillance Coordinator to review his surveillances for compliance with the staggered test basi The review identified that the surveillance tests for the Reactor Trip Breakers undervoltage and shunt trip devices did not meet the staggered
/  test basis June of Technical Specification 4.3.1.1.20 between Junn 20, 1988 and 23, 198 ,
Subsequently, "Staggered Test Basis" surveillances for r.11 for the current mode.reviewed to assure that Staggering intervals were correct other divisions were back to the issuance of the Operating License.The history of these surveillances wa
      *lvo surveillances were found to have bean improperly staggered on Pressurizer Water Level Prctection and Extended Range Nuclear Instrumentatio *
On June 24, 1988, with Unit 1 in Mode 3, the Divisional S : .veillance Coordinator notified the Shif t Supervisor of the f ailure to meet the staggered test basis which was a violation of Technical Specification 4.3.1.1.20. The condition was subsequently determined to be reportable on June 25, 1988 and the NRC was notified pursuant to 10CTK50.12*at 1602 hour The test had already been performed on June 23, 1988, as scheduled, within its required surveillance interva .


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Results: Within the areas inspected, one violation was identified (failure to perform surveillances in accordance with TS, paragraph 3.a).


Inspection Conducted July 1-31, 1988 (Report 50-499/88-47)
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Areas Inspected: Routine, unannounced inspection included observation of electrical component work and mechanical equipment and process work observatio Results: Within the areas inspected, one violation was identified (failure to implement naintenance requirements in accordance with NRC requirements, paragraph 7).
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CAUSE OF OCCURRDICE:  ,
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The root causes of this event were: .
1) Staggered test basis surveil?ances utilized frequency based scheduling which did not control the interval between tests of redundant traia ) Inadequate surveillance program in.that no requirement exists for assuring ttaggered intervals are restored and maintained af ter mode ch ang e s .
ANALYSIS OF EVDIT:
the This condition resulted in the violation of the staggered test basis for Reactor Trip Breaker undervoltage and shunt trip devices. Pressurizer Vater Level Protectian and Extended Range Nuclear Instrumentation as required by Technical Specifications which is reportable under 10CFR50.73(a)(2)(1)(B).


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The surveillance interval requirements were met. There vere no adverse safety or radiological consequences as a result of this eve,nt. The event did not
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produce any additional risk to the ,publi CORRECTIVE ACTION:    *
 
The followirg corrective accions are being taken to prevent recurrence of the event:
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1. -The surveillance data base was revised to establish calendar based scheduling for all staggered test basis surveillances'asscciated with Technical Specification paragraphs 4.3.1.1 and 4.3. ,
          ' A' Surveillance Program Task Force has been establishe This Task Force vill review the entire surveillance program in detail and provide managemont with suggestions for improvement. As a result of this incident, a subcocznittee to the Surveillasco Program Task Force has been created whose objectives are to more fully evaluate Staggered Test Basis surveillances, identify any additional corrective actions, and to implement changes to the staggering methods employed at ST This activity will be completed by September 30, 198 .
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      --3-DETAILS
        ! Persons Contacted
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HL&P
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  *W. P. Evans, Licensing Engineer    :
  *T. J. Jordan, Project Quality Assurance Manager    i
  *M. L. Duke, Engineer      i
  *D. C. King, Construction Manager, Unit 2    ;
  *A. R. Mikus, General Supervisor, Construction    j
  *S. M. Dew, Manager, Operations Support    '
  *J. T.. Westermeier, Project Manager    )
  *J. N. Bakey, Engineer and Licensing Manager
  *A. C. McIntyre, Manager, Support and Engineering    ;
  *W. A. Randlea, Security Manager    ;
  *W. G. We11 born, Supervising Project Engineer    ,
  *S. D. Phillips, Licensing Engineer    !
  * F. Polishak, Licensing Engineer    i
  *J. E. Geiger, General Manager, Nuclear Assurance    ;
  *G. L. Parkey, Plant Superintendent, Unit 2    ;
  *M. A. Garcia, ECI Construction    l
  *S. M. Head, Supervisor, Licensing Engineer    ;
  *W. H. Kinsey, Plant Manager Bechtel      i
  *R. W. Miller, Project Quality Assurance Manager    !
  *K. P. McNeal, Project Quality Assurance Engineer    !
  *R. D. Bryan, Construction Manager    ;
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  *D. D. White Construction Manager    !
  *C P. Rosen Site Manager    j In addition to the above, the NRC inspectors also held discussions with  '
various licensee, architect engineer (AE), constructor and other contractor personnel during this inspectio ;
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  * Denotes those individuals attending the exit interview conducted on  l August 1, 1988      l Plant Status South "sexas Project (STP), Unit 1, reached 75 percent power on July 6,  1 1988. Following the successful completion of the large load reduction  l (75 percent power to 25 percent power) test on July 17, 1988, reactor  ,
power was reduced to approximately 6 percent to allow maintenance on the  i High Pressure Turbine Generator Governor Valve No.1. The valve indicated  l erratic seating position during power escalation. After maintenance and  l i


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ADDITIONAL INFORMATION:
The following LER's have been previously submitted regarding surveillance test program deficiencies at STPEGS:
LER'87-009 Surveillance Deficiency Due to a Procedural Inadequacy Resulting in a Technical Specification violation
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LER 87-017 Pressurizer Low Pressure Safety Injection Setpoint Too Low Due to Procedural Error LER 87-019 Slave Relay Surveillance Deficiency Due to a Personnel Error LER d7 026 Degraded Undervoltage Coincident with a Safety Injection Circuitry Surveillance Deficiency Due to a Deficient Procedure LER 88-005 Inadequate Surveillance Performed on a Control Room
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Intake Radioactivity Monitor
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i  *LER 88-006 Inadequate Surveillance Testing of Haster Relays LER 88-007 Incorrect Formula in a HVAC Surveillance Procedure LER 88-010 Inoperability of Reactor Coolaat Pump Seal Injection Containment Isolation Valves l    .
LER 88-011 Nonperformance of Scheduled Surveillance Test for Essential Chilled Water Pump as a Result of a Lost Test Package l
l LER 88-012 Failure to Tully Implement Technical Specification
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LER 88-013 Failure to Test RCS Low ylow Times Due to Procedure Defleiencies
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LER 88-023 Nonperformance of a Scheduled Surveillance Test for Essential Cooling Water Screen Wash Booster Pump Due
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retesting of the valve, the licensee resumed power escalation to 75 percent. On July 19, 1988, at 9:24 a.m., the reactor tripped from 54 percent power, and the plant was brought to Hot Standby. The trip was caused by an !&C Technician resetting the wrong Quality Display Parameter ,
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System (QDPS) trai detail pursuant to 10 CFR 50.73. Following the completion of an investigation as to the cause of the trip, the licensee resumed power operation and reached a power level of 100 percent of rated reactor thennal power on July 27, 1988. On July 28, 1988, the reactor was the ability of the slant ,
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manually to sustain tripped from100 a trip from 100 percent percent powerpower reactor to verify (a requirement for tie initial startu) testing at 100 percent power plateau). lne acceptance criteria for t1e test appeared to have been met, and the primary systen functioned as designed. The licensee planned to stay in Hot Standby (Mode 3) for approximately 48 hours to repair steam leaks and other required maintenance before resuming power operation. At the close of this inspection period Unit 1 was in Hot Standb ,
STP, Unit 2, is 97 percent complete. Hot functional Testing started on July 15, 1988. On July 22, 1988, the plant was brought to cold shutdown to replace the number 1 seal in Reactor Coolant Pump (RCP) 1C. Seal replacement was completed on July 28, 1988. At the c19se of this inspection period, Unit 2 RCS temperature was 250 degrees F and RCS pressure was 350 psi . Onsite Followup of Events - Unit 1 (93702) Failure to Meet Technical Specifications Surveillance Requirements I During this inspection period, there were two instances where TS surveillances were not perfonned at the time required. The Mcensee has previously implemented corrective actions to preclude such i incidents. The two cases are discussed below'
On June 23, 1988, during a review of plant surveillance data-base, the licensee discovered that surveillances pertaining to TS Surveillance Requirements 4.3.1.1 and 4.3.2.1 were scheduled with a method that could result in inappropriate staggering of test intervals. Further reviews by the licensee determined that the surveillance tests for the reactor trip breakers under voltage and shunt trip devices did not meet the staggered test basis requirement !
from June 20-23, 1988. The licensee identified the causes and l corrective actions in Licensee Event Report (LER) 68-04 On July 12, 1988, the licensee discovered that the surveillance test i to verify that fuel oil particulate contamination was within  ,
acceptable limits on No. 11 Engineered Safety Feature (ESF) Diesel !
Generator Fuel Oil Storage Tank had been missed. TS Surveillance Requinnent 4.8.1.1.2.d requires this test to be perfonned every *
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31 days. The test was due on July 10, 1988. The Shift Supervisor was notified at approximately 9:45 a.m. on July 12, 1988, that the l test had not been performed and the No. 11 ESF Diesel was declared l
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    -5-inoperabl Imediate actions were taken to perform the required surveillance. The results of the test were satisfactory and the No.11 Emergency Safety Feature Diesel Generator was declared operable at 11:14 c.m. on July 12, 1988. The licensee intends to identify the causes and corrective actions in LER 88-043, which is due on or about August 11, 198 TS 4.0.1 states, in part, that surveillance requirements shall be met during the operational modes or other conditions specified in individualLimitingConditionsforOperations(LCOs). Contrary to this requirement, the licensee has demonstrated failure to comply with surveillance requiren.ents as illustrated by the examples abov Between March 11 and June 13, 1988, three other examples of the licensee's failure to adequately implement TS surveillance requirements occurred (LER 88-023,88-035,and88-038). Corrective actions implemented to date do not appear to be effective in preventing failure to meet surveillance requirenents. This is an apparent violation (498/8847-01).
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UCENSEE EVENT REPORT (LER) TEXT. CONTINUATION  m.ovio o= =o. si t2Pemt1;Scies
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South Texas Unit 1 0 5 lo lo le 14 l 918 818 -
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ADDITIONAL INFORMATION (Cont'd.)
 
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LER.88-034 Failure to Test Containment Spray Sequencer Actuation LER 88-035 Nonperfortnance of a Required Surveillance Test for a Component Cooling Water Valve Due to an Inadequate Procedure LER 88-038 Failure to Perform Surveillance Testing of Intemediate Range Nuclear Instrumentation Prior to Entering Mode 2
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l Engineered Safety Feature (ESF) System Walkdown - Unit 1 (71710)
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! The NRC inspector conducted a walkdown of the accessible portions of Train
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  "B" of the Component Cooling Water (CCW) System to independently verify the operability of the system. A review was perfonned to confirm that the licensee's system operating procedure matched plant drawings and the s
as-built configuration. Equipment condition, valve position, housekeeping, labeling, an0 support subsystems essential to actuation of the system were inspecte The NRC inspector identified the following items to licensee management:
. The label on Breaker ElB2B2 indicated as follows, "CCW to Charging )
]  Pump Return." The CCW electrical lineup indicated this breaker ,
:  supplied power to the CCW Return Header Isolation from Charging Pumps i Cooler,    j
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The label on Breaker E181F1 indicated as follows, "CCW to Charging l J
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Pump Supply Valve." The CCW electrical lineup indicated this breaker !
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supplied power to the Moter Operated Isolation from CCW Train "B" to i Charging Pumps Cooler.
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. Houston LJghting k Power  P.O. Box 1700 Houston, Texas 77001 (713) 228 9211
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p August 9i 1988 ST-HL-AE-2754 File No.'s G26 10CFR50.73 11. S. Nuclear Regulatory Cocznission Attention: Document Control Desk Washington, DC 20555
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South Texas Project Electric Generating Feation Unit 1 Docket No. STN 50-498
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Licensee Event Report 88-043 Regarding Failure to Perform Surveillance Testing of Diesel Genarator Fuel 011 zor Contamination Pursuant to 10CFR50.73, Houston Lighting & Power (HL&P) submits the attached Licensee Event Report (LER 88-043) regarding failure to perform surveillance testing of diesel generator fuel oil for contamination due to a personnel error. This event did not have any adverse impact on the health and safety of the publi (  If you should have any quertions on this matter, please contact Mr. C.A. Ayala at (512) 972-862 C y G. E. Vaughn Vice President Nuclear Plant Operations  ,
GEV/3EM/n1 Attachment: LER 88-043
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The label on Breaker E18281 indicated as follows, "CCW Pump 10 Cubicle Cooler Fan llB." The CCW electrical lineup indicated this breaker supplied power to the CCW Pump 1B Cubicle Cooling Fan 11 .
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The label on Breaker ElB4B2 indicated as follows, "CCW Pump Essential Chiller Area Supply Fan Room." The CCW electrical lineup indicated this breaker supplied power to the CCW Pump Essential Chiller Area Supply Fan Coil Unit.
! k-  A Subsidiary of Houston Industries Incorporate,d NL.LER88043 meMobl
 
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ST-HL-AE-2754 -
File No.: G26 7-y    Page 2 ((!!.'l cc:
Regional Administrator, Region IV Rufus S. Scott Nuclear Regulatory Commission 6'' Ryan Plaza Drive, Suite 1000 Associated General Counsel
  .4ngton, TX 76011  Houston Lighting & Power Company
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P. O. Bou 1700 Houston, TX 77001 George Dick U. S. Nuclear Regulatory Commission INPO Vashington, DC 20555 Records Center Jack E. Bass 1100 circle 75 Parkway ,
Atlanta, Ga. 30339-3064 Resident Inspector / Operations c/o U. S. Nuclear Regulatory Commission Dr. Joseph H. Hendrie P. O. Box 910  50 Be11 port Lane Bay City, TX 77414  Be11 port, NY 11713 Don L. Garrison Resident Inspector / Construction c/o U. S. Nuclear Regulatory Commission P. O. Box 910 Bay City, TX 77414 J. R. Newman, Esquire (,.."'
Newman & Holtzinger, L Street, Washington, DC 20036 R. L. Range /R. P. Verret Central Power & Light Company    *
P. O. Box 2121 Corpus Christi, TX 78403 R. John Miner (2 copies)    .
Chief Operating Officer City of Austin Electric Utility 721 Barton Springs Road Austin, TX 78704
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   -6-The above listed discrepancies did not render the CCW System inoperable; however, they were examples of lack of attention to detail.
R. J. Costello/M. T. Hardt City Public Service Board .
P. O. Box 1771 San Antonio, TX 78196
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g Revised 06/16/88
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; No violations or deviations were identified.
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5. Monthly Surveillance Observation - Unit 1 (61726)
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The NRC inspector observed selected portions of the surveillances listed below to verify that the activities were being perfonned in accordance with the TS and surveillance procedures. The applicable procedures were reviewed for adequacy, test instrumentation was verified to be in calibra-tion, and test data was reviewed for accuracy and completeness. The inspector ascertained that identified deficiencies were properly reviewed and resolve Procedure 1 PSP 06-DJ-0001. Revision 6. "125 Volt Class 1E Battery ,
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7-Day Surveillance Test." The NRC inspector witnessed data ,
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acquisition and verified specific gravity checks on Unit 1 Class 1E i i
UCENSEE EVENT REPORT (LER)    ***8 5 ''n' '
batteries. The NRC inspector noted that the results were within TS j limits.
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ol5ga;o;o;4;9;8  i jopl 0 ;4 f  Failure to Perform Surveillance Testing of Diesel Generator Fuel Oil for Contaminatior gygw? DATI 864  68. Artassa. asa  .t. oaf oats (7) otud. ,acatif sts earvotyt. tai uos.1 m .AT TEAR Tl I M'''.0,$In'" NM Wo. stas o47 vl&A  '' O L8T ' * * *.44  Doca si 8.veso t assi 0 151010101 I l
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aae a CoC4 Charles A. Ayala - Supervising Licensing Engineer      5 ,1 i 2 97p;ippy B i
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usi.et.~  = -...-.- : = , n e, On July 12, 1988, with Unit 1 in Mode 1 at 76 percent power, the Houston Lighting & Power (HL&P) Chemical Operations and Analysis Department Divisional      t Surveillance Coordinator discovered that the monthly surveillance on Standby Diesel Generator (SDG) #11 Fuel Oil Storage Tank for particulate contaminat,lon had not been performed within its required interval. The Shift Supervisor was notified at 0945 hours and the test was performed at 1007 hours, two days past the end of the grace period. The cause of the occurrence was failure of the Divisional Surveillance Coordinator to take proper action in response to the surveillance schedule and overdue reports for this surveillance tes Corrective actions include the addition of requirements for the performance of surveillances on their due dates with limited use of the grace period and review of ov'erdue surveillance reports by responsible department managemen *
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J Procedure 1 PSP 03-DG-0001 Revision 5 "Standby Diesel 11 Operability Test." The NRC inspector observed pcrtions of Test Procedure 1 PSP 03-DG-0001 on Standby Diesel Generator 11 and verified that the Diesel Generator performed in accordance with the TS. The NRC inspector verified that data acquired was accurate and complet No discrepancies were identifie Procedure 1 PSP 02-FW-0574. Revision 1. "Steam Generator Narrow Range Level Alarms." The NRC inspector witnessed performance of '
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this procedure and verified that the procedure was followed >
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sequentially, Data was properly documented. No problems were identifie ,
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No violations or deviations were identifie ;
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  . t LICENSEE EVENT REPORT (LER) TEXT CONTINUATISN  areaovo o.. no. sine _ t apin t s 3/3 4$
6. Operational Safety Verification - Unit 1 (71707) ]
The objectives of this portion of the inspection were to verify that the facility is being operated safely and in confonnance with regulatory requirements, management controls are effective, selected activities of the licensee's radiological protection programs are implemented in compliance with regulatory requirements, and to verify licensee compliance with the approved physical security pla I The hRC inspector observed control room activity on a daily basis to verify that control room staffing, operator behavior, shift turnover, !
adherence to TS LCOs and overall control room decorum were being conducted I in accordance with NRC requirement )
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pacskery asamt 11 Docati asumet,a 121
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     -7-      1 Inspections were conducted throughout the plant to observe work in progress. Radiological work practices, posting of barriers, and the correct use of dosimetry were observe Four Radiation Work Permits (RWPs) were reviewe A review of the four RWPs was made to detemine whether the work process was cone in a safe manner and under controlled conditions. The NRC inspector also verified that the RWPs contained information which referenced job description, radiation levels, contamination levels, respiratory protect ve equipment, dosimetry, and expiration date i
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No violations or detiations were identifie f Electrical Component: Unit 2 (51053)
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An inspection of various electrical components was performed to assess the   i adequacy of the installation and workmanship. The inspection focused on basic installation practices, storage requirements, and an assessment of any damage or deterioratio The following equipment was inspected for installation; cleanliness; damge; termination of cables; condition of terminal boards, fans, motors,    7 closure panels and doors; maintenance; and general overall conditio . Cable and cable tray C2XE6-CT-EAB at elevation 79 feet in the Electrical Auxiliary Building (EAB) - This tray carries "C" train power cables through the plan . High range radiation alam controls in the EAB at elevation 65 feet in lhe electrical penetration room - This panel is designated CMA-R1-8051A and was turned over for startup testin . heutron Flux Amplifier 4Z3522-IP-686 at elevation 65 feet in the CAB - This equipment had components removed for use in Unit 1; however, the status of the unit was in accordance with site placedures. The electronics were subjected to the construction    :
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environtrent because an excess of large, nonterminated cable coming
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DESCRIPTION OF OCCURRENCE:
On July 12, 1988, with th.it 1 in Mode 1 at 76 percent power, the Houston Lighting & Power (HL&P) Chemical Operations and Analysis (C0&A) Department Divisional Surveillance Coord1Lator discovered that the monthly surveillance on Standby Diesel Generator (SDG) fil yuel Oil Storage Tank for particulate contamination had not been performed within its required interval. The Shift Supervisor was notified at 0945 hours and preparations were made to perform the tes The surveillance test was completed satisf actorily at 1007 hour ,
The NRC was notified at 1613 hour A subsequent investigation revealed that on June 17, 1988 the C0&A backup Divisional Surveillance Coordinator received the surveillance test package and misfiled it in a hold file instead of forwarding it to the Lead Chemical Technician's Offic When the surveillance became due on the Chemistry Sampling Schedule on June 30, 1988, the HL&P Lead Chemical Technician could not locate the surveillance test package or the test completion notic On July 1,1988, the surveillance test appeared on the daily overdue surveillance repor The Divisional Surveillance Coordinator was advised by i-another Lead Chemical Technician that he thought the surve111asce test had b'  been co=pleted as scheduled and took no further action. The surveillance test
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again appeared on the' overdue report on July 5, 1988. At that time, the Divisional Surveillance Coordinator believed that the test completion notice had been misplaced, and did not take the time to investigate until July 12, 1988 when the missing surveillance test package was found in the hold fil By then the grace period for this surveillance had been exceeded by two day .
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into the equipment prevented closing the door. The licensee took    ,
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immediate corrective action to protect this piece of equipmen '
CAUSE OF OCCURRDICE:
. Electrical penetration Nos. 46, 47, 48, 49, 55, 56, 57, and 64 in the EAB penetration room at elevation 60 plus - These units were   '
The cause of this event was f ailure of the Divisional Surveillance Coordinator to take proper action in response to the surveillance schedule and overdue reports for this surveillance tes .
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inspected for general condition and gas purge. The NRC inspector noted that some penetration cabinets had covers removed for several days which allowed the internals to become covered with construction dust. This condition was immediately corrected by the licensee. The NRC inspector also noted that the nitrogen gas pressure in the penetrations was as follows:
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UCENSEE EVENT REPORT (LER) TEXT CONTINUATCN  anaovio ove o si .
.      s ciais em . e.ciurv m  a c==5i= = a m  to a n ... ne vs.a .t slow ab ; :,*I v e = g South Texas, Unit 1  g,p[ojogog4 l9;S m 8; 8  0l4l3 Oo g Oj3 or 0; 4
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ANALYSIS OT EVENT:
Failure to perform surveillr :- te, sting of Standby Diesel Generator Tuel Oil Storage Tank for particulate con'. amination is a violation of Technical Specification 4.8.1.1.2.D and is reportable under 10CTR50.73(a)(2)(1)(B). The test was performed on July 12, 1988 and the particulate contamination level was determined to be acceptabl .
There were no adverse safety or radiolcgical consequences as a result of this even The event did not produce any additional risk to the publi CORRECTIVE ACTION:
The following corrective actions are being taken to prevent recurrence of the event: The Plant Manager has issued a directive to emphasize the requirement that
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surveillances be performed on their due dates and that the use of the b 7  grace period be limited. Additionally, direct 8ca has been included    .
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Instructing personnel to review objective evi'.ca9 to verify surveillance completio . The Plant Surveillance Program procedure has been revised to require the responsible department manager to review the overdue report and allocate sufficient resources to insure timely completion of surveillance tests.
8-N pressure (psig) N Pressure (psig)
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11  30 47  15 56  0 48  55 57 15 49  5 64  5
:  The NRC inspector detennined that the' constructor had maintained nitrogen gas pressures in the penetration assemblies between 30 and 65 psig prior to March 1983. These pressures were checked monthly by
, the construction maintenance department. In March 1988 these itcms
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were turned over to the licensee operations maintenance departmen The operations maintenance department has not picked up these items for continued maintenance and had not written a maintenance procedure to cover the items. (Procedure FM EM-1-PH87016768 "Inspect Electrical Penetrations" has been implemented for the same activity
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inUnit1.) Thisisanapparentviolation(50/499-8849-02).


. Auxiliary Relay Panel 3E252 ERR 114 and the hydrogen recombiner power
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supply at elevation 65 feet in the EAB
ADDITIONAL INFORMATION:
 
The following LER's have been previously subenitted regarding surveillance test program deficiencies at STPEGS:
. Tennination Cabinets 3E122ETC80 2. -3, -4, and -5 at elevation 65 feet in the cable vault - These units are lacking shields, which preclude the entry of contaminants; however, they are acceptable at ;
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{  this tin . 4160 volt switchgear for High Head Safety Injections (HHSI) Pump '
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Motor "B" No. 3E152ESGOElB at elevation 32 feet in the EAB - This '
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unit was inspected visually on the outside for damage to panels and cable entr . Battery chargers at elevation 32 feet in room 213 - These units were under control of the Nuclear Power Operations Department (NP00). i I  This room had been recently painted. All related equipment in the !
LER 87-009 ourveillance Deficiency" Due to a Procedural Inadequacy Resulting in a Technical Specification Violation LER 87-017 Fressurizar Low Pressure Safety Injection Setpoint
] room was in a satisfactory conditio : During the inspection, the NRC inspector noted that the status of the high I radiation alann, 4160V switchgear, and the battery charging equipment were not in accordance with licensee procedures. This is an additional example ofapreviousviolation(50/499-8824-01) for which the licensee is
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Too Low Due to Procedural Error
implementing corrective action, Safety-Related Components and Process Work Observations - Unit 2 (50073)
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! The NRC inspector examined the following rechanical equipment and work processes as a part of general plant inspections concerning standard work practices or conditions of equipment and structure l
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Essential Cooling Water Auxiliary (ECW) Chillers Building(3V112VCH))at elevation
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70 feet in the Nechanical  (MAB - These three units are York 300 ton capacity units driven by Roliance electric motors. One unit was in operation during the inspection and two were
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    -9-on standby. The NRC inspector observed that the motor bearing temperature sensors were not wired, nor could an ininediate status of this item be determined. The NRC inspector brought this matter to the attention of the license . CCW pumps, motors, and coolers - The "B" train of the three units was operating. Maintenance was being perfonned on the "A" and "C" unit The NRC inspector visually inspected the units for oil levels, external damage, leakage, and general conditio .
E s ete t t. 3/3145
  . Small bore ECW bronze pipe fabrication - This system has been subject to deterioration and leaking because of the dealuminization of cast materials. The licensee has removed the deficient cast components and is replacing these parts with forged fittings. The NRC inspector reviewed the work in the MAB and materials in the fabrication sho l
  'a e itsTv maast it)  Doca i mu.e8m 12J  gga mgn I6i
  . Diesel Generator No. 23 - This unit, which is one of three, is a Cooper KSV Turbocharged V20, 7650 H.P. Diesel Generator. The unit has been the subject of several inspections during this reporting period. After a recent test run, maintenance was perfomed which required removal of two fuel injector lines and turning over of the engine. On turning the engine, water was observed coming out of the injector bosses in two heads. These two heads were removed and found to be cracked. On further investigation, all 20 heads were removed, and a total of 18 were found to be cracke Further review found that the timing chain was two notches off, which ;
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represented a timing error of approximately 20 degrees advance. The f licensee has issued a purchase order to the manufacturer, Cooper-Bessirner, to examine the rods, bearings, crankshaft, and other i
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moving corrponents. The resident inspector will follow the licensee's actions including any licensee reports regarding the matte ,
r s South Texas, Unit 1  o [s j o l o lo 14 l 918 (,f,-        f( 8 -
. Coatings - At this time, the paint / coating activity is at a maxirnum in all areas of Unit 2. The NRC inspector observed the work on the ,
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bridge crane, EAB fire doors, and electrical cabinets in the battery charger room (213) at elevation 32 feet. Additionally, the floor preparation in the reactor containment building at elevation -11 feet was inspecte .
010 Ol4 0F 01 4 ex, ,, . e w e mm w irn ADDITIONAL INFORMATION (Cont'd.)
Insulation - Insulation installation is progressing in all piping areas. The NRC inspector examined the in-process work at elevation 29 feet in the MAB. The work was checked for condition of pipe, cutting, fit, wiring, and sheathin ,


   . Security facilities - Construction of the west gate security i;uilding has been inspected on several occasions. The structure appears to
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LER 87-019 Slave Relay Surveillance Deficiency Due to a Personnel Error LER 87-026 Degraded Undervoltage Coincident with a Safety Injection Circuitry Surveillance Deficiency Due to a Deficient Procedure
meet standard construction practices for the structural steel portion
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LER 88-005 Inadequate Su m 111ance Performed on a Control Room Intake Radiose.tivity Monitor LER 88-006 Inadequate Surveillance Testing of Haster Relays IJR 88-007 Incorrect Formula in a HVAC Surveillance Procedure LER 88-010 Inoperability of Reactor Coolant Pump Seti Injection Containment Isolation Valves LER 88-011 Nonperformance of Scheduled Surveillance Test for
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Essential Chilled Vater Pump as a Result of a Lost
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LER 88-012 Failure to Fully Implement Technical Specification Surveillance Requirements Due to Procedural Deficiency LER 88-013 Failure to Test RCS Low Flow Tices Due to Procedure Deficiencies LER 88-023 Nonperformance of a Scheduled Surve'111ance Test fo,r Essential Cooling Vater Screen Wash Booster Pump Due to an Inadequate Procedure LER 88-03A Failure to Test Containment Spray Sequencer Actuation
    * LER 88-035 Honperformance of a Required Surveillance Test for a Co=ponent Cooling Vater' Valve Due to an Inadequate
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Procedure *
LER 88-038 Failure to Perform Surveillance Testing of
    . Intermediate Range Nuclear Instrumentation Prior to
  . Entering Mode 2 LER 88-040 Failure to Stagger Reactor Trip Breaker Surve111snee Intervale (
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of the building and specific design engineering drawings for the secured portion. Also, the installation of the ultrasonic detection system within the double fence appears to be satisfactor No violations or deviations were identifie . Exit Interview The NRC inspectors met with licensee representatives (denoted in paragraph 1) on August 1,1988, and summarized the scope and findings of the inspection. Other meetings between NRC inspectors and licensee management were held periodically during the inspection to discuss identified concerns. The licensee did not identify as proprietary any of t.)e infornation provided to, or reviewed by, the inspectors during this inspectio .
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Revision as of 16:48, 11 December 2020

Ack Receipt of 880929 Ltr Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-498/88-47 & 50-499/88-47
ML20206B798
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 11/07/1988
From: Callan L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Goldberg J
HOUSTON LIGHTING & POWER CO.
References
NUDOCS 8811160022
Download: ML20206B798 (2)


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Docket . 49 68-47 o 19/88-47 Houston Lighting & Power Company ATTN: J. H. Goldberg, Group Vice President, fiuclear P.O. Box 1700 Houston, Texas 77001 Gentlemen:

Thank you for your letter of September 29, 1988, in response to our letter and Notice of Violation dated August 31, 198 We have reviewed your reply and find it responsive to the concerns raised in our fiotice of Violation. We will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintaine Sincerel Origiral t tri. ! r,y A. P R 4eh L. J. Callan Director Division of Reactor Projects CC:

Houston Lighting & Power Company ATTN: M. A. McBurnett,tianager Operations Support Licensing P.O. Box 289 Wadsworth Texas 77483 Houston Lighting & Power Company ATTN: Gerald E. Vaughn, Vice F.esident F : lear Operations P.O. Box 289 Wadsworth, Texas 77483 Houston Lighting & Power Company ATTN: J. T. Westerneier, General Manager South Texas Project P.O. Box 289 Wadsworth, Texas 77483 ,

RIVd:PSD EJhtM er;df D:hNb LJfMlan 11/4/88 N[

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Houston Lighting & Power Company -2-Central Power & Light Company ATTN: R. L. Range /R. P. Verret P.O. Box 2121 Corpus Christi Texas 78403 City of Austin Electric Utility ATTN: R. J. Miner, Chief Operating Officer 721 Barton Springs Road Austin, Texas 78704 Newman & Holtzinger, ATTN: J. R. Neunan, Esquire 1615 L Street, Washington, D.C. 20036

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Houston Lighting & Power Company ATTN: S. L. Rosen P.O. Box 289 Wadsworth, Texas 77483 Houston Lighting & Power Company ATTN: R. W. Chewning, Chairman Nuclear Safety Review Board P.O. Box 289 Wadsworth, Texas 77483

'- City Public Service Board

ATTN
R. J. Costello/M. T. Hardt P.O. Box 1771 San Antonio, Texas 78296

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Houston Lighting & Power Company ATTN: Licensing Representative Suite 610 Three Metro Center Bethesda, Maryland 20814 Texas Radiation Control Program Director bectoDMB(IE01)

bec distrib, by RIV:

DRP RRI-0PS SectionChief(DRP/D) DRS MIS System RPS-DRSS Lisa Shea, RM/ALF RIV File R. Bachmann, OGC RSTS Operator G. Dick, NRR Project Manager (MS: 13-D-18)

Project Engineer, DRP/D RRI-CONST R. D. Martin

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September 29. 1988 ST-HL-AE-2805 Tile No.: G02. 04- -

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i M ocr s ms U. S. Nuclear Regulatory Corresission Attention: Document Control Desk i

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South Texas Proj ect Electric Generating Station Unit 1 Docket No. STN 50-498 Response to Notice of Violation 498/8547-01 Houston Lighting & Power Company (HL&P) has reviewed Notice of Violation 498/8847-01 dated August 31, 1988. HL&P concurs that the cited violations occurred. These Licensee violations were fully addressed as the subject of the attached Licensee Event Reports. The status of actions addressed in the attached is up.iated as follows:

Licensee Event Report 88-040, "Ta11ure to Stagger Reactor Trip Breaker Surveillance Test Intervals" Corrective actions described in the attached LER have been complete Licensee Event Report 88-043, "Tailure to Perform Surveillance Test of Diesel Generator Fuel 011 for Centamination" Corrective actions described in the attached LER have been complete Appropriate actions have been taken to ensure co pitance in the futur If yod should have any questions on this matter, please contact Mr. H. A. McBurnett at (512) 972-$53 f G. E. Vaughn Vice President Nuclear Plant OpSrations GEV/PLV/n1 Attachments: 1) Licensee Event Peport 88-040 *

2) Licensee Event Report 88-043 A Subs dia:Y of 11ouston Industries Incorporated

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flouston Lighting & Power Company ST-HL-AE-2805 Tile No.: G02.04 Page 2 CCI Regional Administrator, Region IV Rufus S. Scott Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Associated General Counsel Arlington, TX 76011 Houston Lighting & Power Company P. O. Box 1700 Houston, TX 72001 George Dick U. S. Nuclear Regulatory Commission INFO -

Washington, DC 20555 Records Center 1100 Circle 75 Ptrkway Jack E. Icss Atlanta, Ga. 303D9-3064 Resident Inspector / Operations c/o U. S. Nuclear Regulatory Commission Dr. Joseph M. Hent le P. O. Box 910 50 Be11 port Lane Bay City, TX 77414 Be11 port, NY 11743 J. I. Tapia Senior Rerident Inspector /Const.uction c/o U. S. Nuclear Regulatory Commission P. O. Box 910 Bay City, TX 77414 J. R. Newman, Esquire Newman & Holtzinger, L Street, Washington, DC 20036 R. L. Range /R P. Verret l Central Power & Light Company P. O. Box 2121 Corpus Christi. TX 78403 R. John Miner (2 copies)

Chief Operating Officer City of Auktin Electric Utility 721 Barton Springs Road Austin, TX 78704 R. J. Costello/M. T. Hardt City Public Service Board P. O. Box 1771 San Antonio, TX 78296

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July 25, 1988 ST-HL-AZ-2732 Tile No.: G26

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U. S. Nuclear Regulatory :'or:rsission Attention: Docurtant Control Desk Washington, DC 20555 South Texas Project Electric Generating Station Unit 1 Docket No. STN 50-498 License Event Report 88-040 Regarding Tailure to Staeter Reactor Trip 3reaker Surveillance Test Intervals Fursuant to 10CTR50.73. Houston Lighting & Power (ML&P) Submits the attached Licensee Event Report (LER 88-040) reg'hrding f.ailure to stagger reactor trip breaker surveillance test intervals. This event did not have any

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adverse impact on the health and safety of the publi If you should have any questions on th.s matter, please contact Mr. C.A. Ayala at (512) 972-862 G. E. Vaughn Vice Tresident Nuclear Flant Operations GEY/3EN/pv Attachment: LER 88-040 l

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Regional Administrator, Region IV

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Houston, 72 77001 U. S. Nuclear Regulatory Commission INPO Washington, DC 20555 ,

Records Center J1ck E. Bess 1100 circle 75 Parkway Resident Inspector / Operations Atlanta, Ga. 30339-3064 c/a U. S. Nuclear Regulatory Commission Dr. Joseph H. Hendrie P, O. Box 910 Bay City. TX 77414 50 Bellport Lane Be11 port, NY 11713 Don L. Garrison Resident Inspector / Construction

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cive actions include revision to the method for scheduling staggered surveillances and creation of a Surveillance Program Task Force Subcommittee to study staggered test basis surveillance .

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DESCRIPTION OF OCCURRENCE:

On June 23, 1988, during the annual review of the plant surveillance database as required by procedure, the HL&P Plant Surveillance Coordinator identified that the surveillances associated with Technical Specification .

4.3.1.'1 staggerlagandof4.3. were scheduled with a method that could result test interval in improper scheduling, This method, known as frequency based determines the next due date for a given surveillance by' adding the surveillance interval to the last date the surveillance was performed and '

adjusting the due date as required by Technical Specification 4.c.2. The result of this calculation issures that tha surveillance interval for each train (equalmeets to thethetest Technical Specification requirement, however, the stagger redundant trains mayinterval divided by the number of trains) between tests of not remain constan Upon the discovery of the error in the scheduling method used, the Plant Surveillance Coordinator requested the responsible Divisional Surveillance Coordinator to review his surveillances for compliance with the staggered test basi The review identified that the surveillance tests for the Reactor Trip Breakers undervoltage and shunt trip devices did not meet the staggered

/ test basis June of Technical Specification 4.3.1.1.20 between Junn 20, 1988 and 23, 198 ,

Subsequently, "Staggered Test Basis" surveillances for r.11 for the current mode.reviewed to assure that Staggering intervals were correct other divisions were back to the issuance of the Operating License.The history of these surveillances wa

  • lvo surveillances were found to have bean improperly staggered on Pressurizer Water Level Prctection and Extended Range Nuclear Instrumentatio *

On June 24, 1988, with Unit 1 in Mode 3, the Divisional S : .veillance Coordinator notified the Shif t Supervisor of the f ailure to meet the staggered test basis which was a violation of Technical Specification 4.3.1.1.20. The condition was subsequently determined to be reportable on June 25, 1988 and the NRC was notified pursuant to 10CTK50.12*at 1602 hour0.0185 days <br />0.445 hours <br />0.00265 weeks <br />6.09561e-4 months <br /> The test had already been performed on June 23, 1988, as scheduled, within its required surveillance interva .

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The root causes of this event were: .

1) Staggered test basis surveil?ances utilized frequency based scheduling which did not control the interval between tests of redundant traia ) Inadequate surveillance program in.that no requirement exists for assuring ttaggered intervals are restored and maintained af ter mode ch ang e s .

ANALYSIS OF EVDIT:

the This condition resulted in the violation of the staggered test basis for Reactor Trip Breaker undervoltage and shunt trip devices. Pressurizer Vater Level Protectian and Extended Range Nuclear Instrumentation as required by Technical Specifications which is reportable under 10CFR50.73(a)(2)(1)(B).

The surveillance interval requirements were met. There vere no adverse safety or radiological consequences as a result of this eve,nt. The event did not

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produce any additional risk to the ,publi CORRECTIVE ACTION: *

The followirg corrective accions are being taken to prevent recurrence of the event:

1. -The surveillance data base was revised to establish calendar based scheduling for all staggered test basis surveillances'asscciated with Technical Specification paragraphs 4.3.1.1 and 4.3. ,

' A' Surveillance Program Task Force has been establishe This Task Force vill review the entire surveillance program in detail and provide managemont with suggestions for improvement. As a result of this incident, a subcocznittee to the Surveillasco Program Task Force has been created whose objectives are to more fully evaluate Staggered Test Basis surveillances, identify any additional corrective actions, and to implement changes to the staggering methods employed at ST This activity will be completed by September 30, 198 .

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The following LER's have been previously submitted regarding surveillance test program deficiencies at STPEGS:

LER'87-009 Surveillance Deficiency Due to a Procedural Inadequacy Resulting in a Technical Specification violation

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LER 87-017 Pressurizer Low Pressure Safety Injection Setpoint Too Low Due to Procedural Error LER 87-019 Slave Relay Surveillance Deficiency Due to a Personnel Error LER d7 026 Degraded Undervoltage Coincident with a Safety Injection Circuitry Surveillance Deficiency Due to a Deficient Procedure LER 88-005 Inadequate Surveillance Performed on a Control Room

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Intake Radioactivity Monitor

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i *LER 88-006 Inadequate Surveillance Testing of Haster Relays LER 88-007 Incorrect Formula in a HVAC Surveillance Procedure LER 88-010 Inoperability of Reactor Coolaat Pump Seal Injection Containment Isolation Valves l .

LER 88-011 Nonperformance of Scheduled Surveillance Test for Essential Chilled Water Pump as a Result of a Lost Test Package l

l LER 88-012 Failure to Tully Implement Technical Specification

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LER 88-013 Failure to Test RCS Low ylow Times Due to Procedure Defleiencies

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LER 88-023 Nonperformance of a Scheduled Surveillance Test for Essential Cooling Water Screen Wash Booster Pump Due

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ADDITIONAL INFORMATION (Cont'd.)

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LER.88-034 Failure to Test Containment Spray Sequencer Actuation LER 88-035 Nonperfortnance of a Required Surveillance Test for a Component Cooling Water Valve Due to an Inadequate Procedure LER 88-038 Failure to Perform Surveillance Testing of Intemediate Range Nuclear Instrumentation Prior to Entering Mode 2

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p August 9i 1988 ST-HL-AE-2754 File No.'s G26 10CFR50.73 11. S. Nuclear Regulatory Cocznission Attention: Document Control Desk Washington, DC 20555

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South Texas Project Electric Generating Feation Unit 1 Docket No. STN 50-498

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Licensee Event Report 88-043 Regarding Failure to Perform Surveillance Testing of Diesel Genarator Fuel 011 zor Contamination Pursuant to 10CFR50.73, Houston Lighting & Power (HL&P) submits the attached Licensee Event Report (LER 88-043) regarding failure to perform surveillance testing of diesel generator fuel oil for contamination due to a personnel error. This event did not have any adverse impact on the health and safety of the publi ( If you should have any quertions on this matter, please contact Mr. C.A. Ayala at (512) 972-862 C y G. E. Vaughn Vice President Nuclear Plant Operations ,

GEV/3EM/n1 Attachment: LER 88-043

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Regional Administrator, Region IV Rufus S. Scott Nuclear Regulatory Commission 6 Ryan Plaza Drive, Suite 1000 Associated General Counsel

.4ngton, TX 76011 Houston Lighting & Power Company

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P. O. Bou 1700 Houston, TX 77001 George Dick U. S. Nuclear Regulatory Commission INPO Vashington, DC 20555 Records Center Jack E. Bass 1100 circle 75 Parkway ,

Atlanta, Ga. 30339-3064 Resident Inspector / Operations c/o U. S. Nuclear Regulatory Commission Dr. Joseph H. Hendrie P. O. Box 910 50 Be11 port Lane Bay City, TX 77414 Be11 port, NY 11713 Don L. Garrison Resident Inspector / Construction c/o U. S. Nuclear Regulatory Commission P. O. Box 910 Bay City, TX 77414 J. R. Newman, Esquire (,.."'

Newman & Holtzinger, L Street, Washington, DC 20036 R. L. Range /R. P. Verret Central Power & Light Company *

P. O. Box 2121 Corpus Christi, TX 78403 R. John Miner (2 copies) .

Chief Operating Officer City of Austin Electric Utility 721 Barton Springs Road Austin, TX 78704

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usi.et.~ = -...-.- : = , n e, On July 12, 1988, with Unit 1 in Mode 1 at 76 percent power, the Houston Lighting & Power (HL&P) Chemical Operations and Analysis Department Divisional t Surveillance Coordinator discovered that the monthly surveillance on Standby Diesel Generator (SDG) #11 Fuel Oil Storage Tank for particulate contaminat,lon had not been performed within its required interval. The Shift Supervisor was notified at 0945 hours0.0109 days <br />0.263 hours <br />0.00156 weeks <br />3.595725e-4 months <br /> and the test was performed at 1007 hours0.0117 days <br />0.28 hours <br />0.00167 weeks <br />3.831635e-4 months <br />, two days past the end of the grace period. The cause of the occurrence was failure of the Divisional Surveillance Coordinator to take proper action in response to the surveillance schedule and overdue reports for this surveillance tes Corrective actions include the addition of requirements for the performance of surveillances on their due dates with limited use of the grace period and review of ov'erdue surveillance reports by responsible department managemen *

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DESCRIPTION OF OCCURRENCE:

On July 12, 1988, with th.it 1 in Mode 1 at 76 percent power, the Houston Lighting & Power (HL&P) Chemical Operations and Analysis (C0&A) Department Divisional Surveillance Coord1Lator discovered that the monthly surveillance on Standby Diesel Generator (SDG) fil yuel Oil Storage Tank for particulate contamination had not been performed within its required interval. The Shift Supervisor was notified at 0945 hours0.0109 days <br />0.263 hours <br />0.00156 weeks <br />3.595725e-4 months <br /> and preparations were made to perform the tes The surveillance test was completed satisf actorily at 1007 hour0.0117 days <br />0.28 hours <br />0.00167 weeks <br />3.831635e-4 months <br /> ,

The NRC was notified at 1613 hour0.0187 days <br />0.448 hours <br />0.00267 weeks <br />6.137465e-4 months <br /> A subsequent investigation revealed that on June 17, 1988 the C0&A backup Divisional Surveillance Coordinator received the surveillance test package and misfiled it in a hold file instead of forwarding it to the Lead Chemical Technician's Offic When the surveillance became due on the Chemistry Sampling Schedule on June 30, 1988, the HL&P Lead Chemical Technician could not locate the surveillance test package or the test completion notic On July 1,1988, the surveillance test appeared on the daily overdue surveillance repor The Divisional Surveillance Coordinator was advised by i-another Lead Chemical Technician that he thought the surve111asce test had b' been co=pleted as scheduled and took no further action. The surveillance test

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again appeared on the' overdue report on July 5, 1988. At that time, the Divisional Surveillance Coordinator believed that the test completion notice had been misplaced, and did not take the time to investigate until July 12, 1988 when the missing surveillance test package was found in the hold fil By then the grace period for this surveillance had been exceeded by two day .

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CAUSE OF OCCURRDICE:

The cause of this event was f ailure of the Divisional Surveillance Coordinator to take proper action in response to the surveillance schedule and overdue reports for this surveillance tes .

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ANALYSIS OT EVENT:

Failure to perform surveillr :- te, sting of Standby Diesel Generator Tuel Oil Storage Tank for particulate con'. amination is a violation of Technical Specification 4.8.1.1.2.D and is reportable under 10CTR50.73(a)(2)(1)(B). The test was performed on July 12, 1988 and the particulate contamination level was determined to be acceptabl .

There were no adverse safety or radiolcgical consequences as a result of this even The event did not produce any additional risk to the publi CORRECTIVE ACTION:

The following corrective actions are being taken to prevent recurrence of the event: The Plant Manager has issued a directive to emphasize the requirement that

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surveillances be performed on their due dates and that the use of the b 7 grace period be limited. Additionally, direct 8ca has been included .

Instructing personnel to review objective evi'.ca9 to verify surveillance completio . The Plant Surveillance Program procedure has been revised to require the responsible department manager to review the overdue report and allocate sufficient resources to insure timely completion of surveillance tests.

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ADDITIONAL INFORMATION:

The following LER's have been previously subenitted regarding surveillance test program deficiencies at STPEGS:

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LER 87-009 ourveillance Deficiency" Due to a Procedural Inadequacy Resulting in a Technical Specification Violation LER 87-017 Fressurizar Low Pressure Safety Injection Setpoint

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Too Low Due to Procedural Error

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LER 87-019 Slave Relay Surveillance Deficiency Due to a Personnel Error LER 87-026 Degraded Undervoltage Coincident with a Safety Injection Circuitry Surveillance Deficiency Due to a Deficient Procedure

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LER 88-005 Inadequate Su m 111ance Performed on a Control Room Intake Radiose.tivity Monitor LER 88-006 Inadequate Surveillance Testing of Haster Relays IJR 88-007 Incorrect Formula in a HVAC Surveillance Procedure LER 88-010 Inoperability of Reactor Coolant Pump Seti Injection Containment Isolation Valves LER 88-011 Nonperformance of Scheduled Surveillance Test for

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Essential Chilled Vater Pump as a Result of a Lost

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Test Package

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LER 88-012 Failure to Fully Implement Technical Specification Surveillance Requirements Due to Procedural Deficiency LER 88-013 Failure to Test RCS Low Flow Tices Due to Procedure Deficiencies LER 88-023 Nonperformance of a Scheduled Surve'111ance Test fo,r Essential Cooling Vater Screen Wash Booster Pump Due to an Inadequate Procedure LER 88-03A Failure to Test Containment Spray Sequencer Actuation

  • LER 88-035 Honperformance of a Required Surveillance Test for a Co=ponent Cooling Vater' Valve Due to an Inadequate

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LER 88-038 Failure to Perform Surveillance Testing of

. Intermediate Range Nuclear Instrumentation Prior to

. Entering Mode 2 LER 88-040 Failure to Stagger Reactor Trip Breaker Surve111snee Intervale (

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