IR 05000397/1986016
| ML20205P937 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/16/1986 |
| From: | Kirsch D, Qualls P, Thomas Young NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20205P930 | List: |
| References | |
| 50-397-86-16-EC, NUDOCS 8605280062 | |
| Download: ML20205P937 (5) | |
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U.'S. NUCLEAR REGULATORY COMMISSION-
REGION V
Report No. ' 50.- 397/86-16
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-' Docket No. 50-397
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Licensee No. NPF-21 Licensee: Washington Public Power Supply System P.O. Box 968 Richland, Washington 99352
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Facility Name:'WNP-2 Hanford, Washington
- Inspection conducted: April 15, 1986 b-al b 5 /f 3 / f6
_ Inspectors:
P.
Qua.ls, React 6r Inspector Date Signed
' Approved By:
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'T. Young Jr., Cp ef, Engi
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hL s-/u.'n D.71rsch,' Firector, Da'te Sigtied Division of Reactor Safety Projects Summary:
An Enforcement Conference was held on April 15, 1986. The following topics
were discussed.
1.
An apparent violation identified during the inspection of the WNP-2 Nuclear Plant's Fire Protection Program.
(Inspection Report
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No'. 50-397/86-05).
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Matters of concern to the NRC.
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8605280062 860521 PDR ADOCK 05000397 Q
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DETAILS 1.
' Enforcement Conference Participants JRC Participants J. B. Martin, Regional' Administrator
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B.-H. Faulkenberry, Deputy Regional Administrator D.l Kirsch, Director of Reactor Safety and Projects A. Johnson, RV Enforcement Officer R. Marsh,- RV, Director Office of Investigation-R. Pate, Reactor Safety Branch Chief T. Young Jr., Engineering Section Chief R. Dodds, Chief, Reactor Projects Section 1 G. Cook, Public Affairs Officer R. Meeks, RV, Office of Investigation P. Qualls, Reactor Inspector WPPSS Participants J. Martin, Assistant Managing Director of Operations R. Glasscock, Director, Licensing and Assurance C. Powers, WNP-2 Plant Manager L. Harrold, Assistant Director, General Engineering D. Eggen, Principal Fire Protection Engineer G. Brastad, Technical Specialist State of Washington B. Fitch, EFSEC, Executive Secretary 2.
Enforcement Conference-On April 15, 1986, an enforcement conference was held at the NRC Region V office in Walnut Creek, California, with the individuals listed as identified in paragraph 1, above. The conference was in regard-to the 10 CFR 50, Appendix R, fire protection inspection conducted March 3-24, 1986. The inspection is described in inspection report 50-397/86-05.
The conference was announced in a letter to the licensee dated April 4, 1986.
Mr. Jack Martin informed the licensee that the purpose of the conference was to discuss the apparent violations of regulatory requirements identified during the recent fire protection inspection at WNP-2.
Mr. Pate then listed the items to be discussed during the meeting and restricted the discussion to the thermolag installation at WNP-2.
He identified that the key issues involved faulty engineering design criteria, improper thermolag installation and inadequate quality assurance review of the design criteria and thermolag installation.
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Mr. Jerry Martin responded for the licensee and Mr. C. Powers and L. Harrold discussed these issues in detail. They outlines the cause, the compensatory measures and corrective measures which address the issues of concern to the NRC. An outline of their presentation is included as an enclosure to this report.
Mr. Jack Martin noted that the design criteria for the seismic steel for the cable trays had been improperly established. This resulted from a clarification to the specification which allowed inadequate thermolag on the seismic supports to provide a three hour fire barrier.
In light of this finding, Mr. Martin questioned whether similar design clarifications or design changes to other systems at WNP-2 should be reviewed.
Mr. Jerry Martin stated that selected design changes in other systems would.be examined to ensure that the original design criteria had not been compromised.
Mr. A. Johnson then discussed the NRC enforcement policy with the licensee.
Mr. Jack Martin summarized the NRC concerns that weaknesses in the licensee's controls were identified in the areas of establishing design criteria, materials installation and quality control. He urged the licensee to do a critical self-examination of these areas and to make improvements as appropriat :
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SUPPLY SYSTEM PRESENTATION ENFORCEENT CONFERENCE -
APRIL 15, 1986 APPENDIX R - FIRE PROTECTION AUDIT ~ FINDINGS
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DISCUSSION OF ISSUES INVOLVING POTENTIAL VIOLATIONS
- License Condition 14 compliance
- Adequacy of three (3) hour fire barrier for safe shutdown equipment (cables)
II.
IMMEDIATE CORRECTIVE ACTIONS FOR ITEMS NOTED IN INSPECTION REPORT 50-397/86-05
- Established Technical Specification required hourly fire watch for potentially degraded fire barrier
- Installed additional Thermo-Lag on items identified in Inspec-tion Report 50-397/86-05
- Performed Engineering analysis and determined nine (9) inches of Thermo-Lag on seismic support steel is adequate for one (1)
hour barrier, but inadequate for three (3) hour barrier
- Applied increased monitoring of fire loading in Reactor Build-ing by Fire Protection Engineer
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III.
LONGER TERM CORRECTIVE ACTIONS TO ESTABLISH COMPLIANCE WITH BTP CMEB 9.5.1
- Amend License Condition 14 using SECY-85-306 as a guide
- Sample survey conducted on safe shutdown equipment (cables) to assess implementation of design [nine (9) inches]
- Contract for Thermoscience, Inc. (TSI) support to develop field direction to establish three (3) hour barrier at each tray support location
- Conduct 100% inspection of safe shutdown equipment (cables)
with " intelligent" field team to identify specific deficiencies
- Apply necessary manpower and material to correct deficiencies
- Apply appropriate QA/QC verification with inspection plans
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- Schedule of longer term corrective actions:
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- Develop Field Direction: April 18, 1986
- Procure Thermo-Lag / Fabricate Material: April 18, 1985
- Complete application in high rad areas:
Prior to restart
- Complete Balance of Work: July 1986
- Submit License Amendment: July 1986
- Continue with one (1) hour fire watch until three (3) hour barrier established for safe shutdown equipment (cables)
IV.
GENERIC IMPLICATIONS OF THESE ISSUES
- Engineering Design process must now review modifications for impact on three (3) hour fire barrier
- Plant Maintenance Procedures must acknowledge 18 inch criteria for Thermo-Lagging of safe shutdown equipment (cables)
- Plant Surveillance Procedures must inspect for missing and degraded Thermo-Lagging on safe shutdown equipment (cables)
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