IR 05000285/1988010: Difference between revisions

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{{Adams
{{Adams
| number = ML20154J514
| number = ML20196G287
| issue date = 05/19/1988
| issue date = 06/29/1988
| title = Forwards Notice of Violation & Notice of Deviation Re Insp Rept 50-285/88-10 on 880314-18.Documents Inadvertently Transmitted to Third Party One Day Before Rept Signed Out
| title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-285/88-10.Followon Insp Will Be Conducted to Determine If Unresolved Item Acceptable,Deviation or One or More Violations
| author name = Milhoan J
| 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 = Andrews R
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
| addressee affiliation = OMAHA PUBLIC POWER DISTRICT
| docket = 05000285
| docket = 05000285
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = NUDOCS 8805270025
| document report number = NUDOCS 8807050485
| document type = INTERNAL OR EXTERNAL MEMORANDUM, MEMORANDUMS-CORRESPONDENCE
| title reference date = 06-03-1988
| page count = 6
| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| page count = 2
}}
}}


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=Text=
{{#Wiki_filter:2*# Wg,  UNITED STATES
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i , NUCLEAR REGULATORY COMMISSION . ,b  REGION IV
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JUR 2 91988 T In Reply Refer To:
ARLINGTfN, MA I91988 TEXAS 79011
Docket: 50-285/88-10 l- -Omaha Public Power District
      .
. ATTN: R. L. Andrews, Division Manager-Nuclear Production 1623 Harney Street    ,
      '
Omaha, Nebraska 68102 Gentlemen:
MEMORANDUM FOR: File FROM: James L. Milhoan, Director, Division of Reactor Safety SUBJECT: INADVERTENT RELEASE OF DRAFT MATERIAL The purpose of this memorandum is to place in the PDR copies of documents related to NRC Inspection Report 50-285/88-1 These documents were inadvertently transmitted via fascimile to a third party on April 18, 1988, the day before the report in question was signed ou M h James . lho n, Director T Division of Reactor Safety Enclosure: Ai stated cc w/ enclosure:
Th'ank you for your letter of June 3,1988, in response to our letter and Notice of Violation dated April 19, 1988. We have reviewed your reply and find it responsive to the concerns raised in Violation A of our Notice of Violation. . We will review the implementation of your corrective actions for this violation during a future inspection to determine that full compliance has been achieved and will be maintaine With regard to Violation B, we are downgrading this to an unresolved item based on your response. We believe that your respcnse appeared to indicate that there may have been other violations. Specifically, your response-indicated that you were in possible violatinn of Criteria V and XVII of Arpendix B to 10 CFR 5 Your response does not indicate corrective actions of sufficient scope to address these apparent violations. Therefore, we shall-coriduct a followon inspection to determine if the unresolved item is acceptable, a deviation, or one or more violation t
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Sincerely, Original SJgned By, 8807050485 880629  L. J. Callan PDR ADOCK 05000285 G  L. J. Callan, Director l    Division of Reactor Projects l
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Fort Calhoun Station ATTN: W. G. Gates, Manager P.O. Box 399 Fort Calhoun, Nebraska 68023 l
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Harry H. Voigt, Es LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, NW Washington, D. Kansas Radiation Control Program Director Nebraska Radiation Control Program Director
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APPENDIX A
_ NOTICE OF VIOLATION Omaha Public Power District Fort Calhoun Station  Docket: 50-285 Operating License: DPR-40 During an NRC inspection conducted from March NRC requirements were identifie , 1988, two violations of resolve deficiencies identified during a surveillance test and failure licensee reactor coolant to verify systemthe leakcorrect tes qualifications for an examiner completing a Policy (1987), the and Procedure violations forbelow:
are listed NRC Enforcement Actions " 10 CFR Part 2 Failure To Promptly Resolve Test Deficiencies  ,
O quality assurance program requires that a test program sI established satisfactoril to assure that . . . systems and components will perfonn  )
documented satisfie and evaluated to assure that test requirements ha i
j Contrary to the above, Surveillance Test ST-NZ-1 was completed on May 8,  i 1987, with anamolies or deficiencies involving 11 nozzle i There was not i an evaluation started of these anomalies or deficiencies 198 until March 15, This is a Severity Level IV violatio (SupplementI)(285/8810-01) j Failure Test Evaluationto Use Correct Qualification level of Examiner for Surveillance i
Section 5.8.1 of the Technical Specifications (TS) requires that written procedures and administrative policies shall be established, implemented and 5.2 of ANSI N18.7-1972.and maintained that meet or exceed the minimum Table 1 of G-26 of the licensee's Standing Order G-26, R17. "Maintenance Quality Control Program," requires a minimum level II capability for personnel who evaluate and report test result Contrary to the above, Surveillance Test ST-RLT-1, F.1 (leak test) results were evaluated and reported on May a lower capability level (Level 1). 29, 1987, by an individual qualified to This is a Severity Level IV violatio (SupplementI)(285/8810-02)
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Pursuant to the provisions of 10 CFR 2.201, Omaha Public Power District is hereby required to submit to this office, within 30 days of the date of the letter transmitting this Notice, a written statement or explanation in reply, including for each violation: (1) the reason for the violations if admitted, (2) the corrective steps which have been taken and the results achieved, (3) the corrective steps which will be taken to avoid further violations, and (4) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending the response tim Dated at Arlington, Texas, this day of 198 l l
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APPENDIX B  '
NOTICE OF DEVIATION
~0maha Public Power District  Docket: 50-285 Fort Calhoun Station Operating License: DPR-40 Based on the results of an NRC inspection conducted from March 14-18, 1988, a deviation from your comitment was identifie The deviation consisted of failure to continue implementation of corrective actions comitted to in the response to an NRC violatio In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2 Appendix C (1987), the deviation is listed below:
Failure to Continue Implementation of Corrective Actions Violation 285/8511-01, dated June 26, 1985, involved failure to account for six surveillance ending in July 1984,tests (STs),
in the files.performed during the refueling outage The licensee's response to this violation stated, in part, "Each month the surveillance test clerk will issue a list of STs that are due but not filed and those due but not complete Each indicating the supervisor status of each will test.be required to respond to this list by This status list will then be compiled and presented to the Plant Review Committee (PRC) by the Supervisor-Technical indicating those tests not completed /not filed and the action taken to assure completion / filing by the end of the next monthly review period."
 
Contrary to the above, in deviation to that written comitment, a status list indicating the action taken to assure completion / filing by the end of the next monthly review period did not exist for a delinquent ST list dated March 2, 1988, which showed 11 STs dating from August 22, 1986, t through the end of the 1987 spring refueling outage, as being delinquent for filin (285/8810-03)
Omaha Public Power District is hereby requested to submit a written statement or explanation to this Office within 30 days of the date of the letter transmitting this Notice. This reply, should include for each deviation:
(1) the reason for the deviation if admitted, (2) the corrective steps that have been taken and the results achieved. (3) the corrective steps that will be
,
taken to avoid further deviations, and (4) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending the response time.
 
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Dated at Arlington, Texas, this day of  198 ,
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of test results records for each procedur The TS surveillance requirements or IST component together with the associated test procedures reviewed by the NRC inspector are tabulated in the Attachmen The NRC inspector determined that the required tests were being scheduled and performed as required in accordance with approved procedure Acceptance criteria were specified in the procedures and, with the exceptions discussed below, the records stated satisfaction of acceptance criteria. Appropriate instructions for returning equipment to service following testing were given. Some problems involving failure to complete timely reviews of completed test records are discussed in Section above and an example is given belo The NRC inspector discovered that completed Procedure ST-NZ-1, Section F.1, for flow testing containment spray nozzles noted anomalies and deficiencies which had not been formally reviewed and dispositione Specifically, it was noted that ten nozzles were not tested because of inaccessibility and that one nozzle was not working properly. The test had been completed on May 8, 1987, and was listed as delinquent for filing in the list updated on March 2, 1988. The failure to evaluate the anomolies or deficiencies with these nozzles is an apparent violation of 10 CFR i Part 50, Appendix B, Criterion XI, and the approved quality assurance I progra (285/8810-01)
The NRC inspector discussed the deficiencies noted in the test record for ST-NZ-1 with plant management on March 15, 198 The NRC inspector !
 
expressed concern that the plant was restarted with the operability of the containment spray system undetermined. A second conc. n expressed was that the licensee's administrative procedures for followup on test deficiencies were apparently not followed. The Supervisor-Maintenance initiated an Incident Report on March 16, 1988, to address the test problems note It contained the results of a preliminary safety analysis i
which indicated that over 100 spray nozzles must be plugged before the i design flow rate of 5100 gpm would be decreased. The NRC inspector had no further safety concerns on this tes During the inspection, the NRC inspector requested records verifying the appropriate qualification level of examiners who completed reactor coolant system leak testing on May 29, 1987, and on June 1, 1987, in accordance with Procedure ST-RLT-1, Section Because these records were not made available prior to the exit, it was discussed as an unresolved ite Copies of qualification records were subsequently forwarded by the licensee to the NRC Region IV office on March 22, 1988. The qualification record for the examiner completing the test on May 29, 1987, indicated he had only an ANSI N45.2.6, level I qualification for hydrostatic testin Paragr6ph F.1.b.(2)(a) of ST-RLT-1 states that examiners must be qualified in accordance with ASME Section XI, Article IWA-2000. Paragraph IWA-2212 of Article IWA-2000 requires the use of VT-2 visual examination for leak testing. Subarticle IWA-2300 requires qualification of personnel l
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Latest revision as of 04:02, 9 December 2021

Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-285/88-10.Followon Insp Will Be Conducted to Determine If Unresolved Item Acceptable,Deviation or One or More Violations
ML20196G287
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 06/29/1988
From: Callan L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Andrews R
OMAHA PUBLIC POWER DISTRICT
References
NUDOCS 8807050485
Download: ML20196G287 (2)
v • d • e


Text

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JUR 2 91988 T In Reply Refer To:

Docket: 50-285/88-10 l- -Omaha Public Power District

. ATTN: R. L. Andrews, Division Manager-Nuclear Production 1623 Harney Street ,

Omaha, Nebraska 68102 Gentlemen:

Th'ank you for your letter of June 3,1988, in response to our letter and Notice of Violation dated April 19, 1988. We have reviewed your reply and find it responsive to the concerns raised in Violation A of our Notice of Violation. . We will review the implementation of your corrective actions for this violation during a future inspection to determine that full compliance has been achieved and will be maintaine With regard to Violation B, we are downgrading this to an unresolved item based on your response. We believe that your respcnse appeared to indicate that there may have been other violations. Specifically, your response-indicated that you were in possible violatinn of Criteria V and XVII of Arpendix B to 10 CFR 5 Your response does not indicate corrective actions of sufficient scope to address these apparent violations. Therefore, we shall-coriduct a followon inspection to determine if the unresolved item is acceptable, a deviation, or one or more violation t

Sincerely, Original SJgned By, 8807050485 880629 L. J. Callan PDR ADOCK 05000285 G L. J. Callan, Director l Division of Reactor Projects l

l cc:

Fort Calhoun Station ATTN: W. G. Gates, Manager P.O. Box 399 Fort Calhoun, Nebraska 68023 l

Harry H. Voigt, Es LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, NW Washington, D. Kansas Radiation Control Program Director Nebraska Radiation Control Program Director

  • previously concurred
  • RIV:RI *C:TPS *D:DRS *C:PSB D:DRb HBundy/cjg WSeidle JLMilhoan TWesterman LJCa lan i\

l

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_____

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' Omaha Public Power District -2-

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bec distrib._by RIV:

'

R.D.-Martin, RA- :RPSB-DRSS Section Chief'(DRP/B) MIS System RIV File DRP RSTS Operator- Project Engineer, DRP/B Lisa Shea, RM/ALF- T. Bournia, NRR Project Manager DRS G. F.- Sanborn, E0 H. Bundy

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RRI W. Seidle

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