IR 05000259/1998002
| ML18039A427 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/02/1998 |
| From: | Plisco L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Scalice J TENNESSEE VALLEY AUTHORITY |
| References | |
| 50-259-98-02, 50-259-98-2, 50-260-98-02, 50-260-98-2, 50-296-98-02, 50-296-98-2, EA-98-358, NUDOCS 9807170310 | |
| Download: ML18039A427 (12) | |
Text
CA,TEQORY
S REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9807170310 DOC.DATE: 98/07/02 NOTARIZED: NO FACIL:50-259 Browns Ferry Nuclear Power Station, Unit 1, Tennessee 50-260 Browns Ferry Nuclear Power Station, Unit 2', Tennessee 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee AUTH.NAME AUTHOR AFFILIATION PLISCO,L.R.
Region
(Post 820201)
RECI P. NAME RECIPIENT AFFILIATION SCALICE,J.A.
Tennessee Valley Authority SUBJECT: Ack receipt of 980604 ltr informing NRC of steps taken to correct. violations noted.in insp,rept 50-259/98-02, 50-260/98-02
&. 50-296/98-02.
D1STRTBOTION CODE:
TE01D CORTES RECETVED:LTR i ENCL f STZE:
TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response I
NOTES:
DOCKET 05000259 05000260 05000296 RECIPIENT ID CODE/NAME PD2-3-PD INTERNAL: ACRS AEOD/TTC L
CB NUDOCS -ABSTRACT OGC/HDS3 COPIES LTTR ENCL
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1 RECIPIENT ID CODE/NAME DEAGAZIO,A AEOD/SPD/RAB DEDRO NRR/DRCH/HOHB NRR/DRPM/PERB OE DIR RGN2 FILE
COPIES LTTR ENCL
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1 ERNAL: LITCO BRYCE, J H NRC PDR
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1 NUDOCS FULLTEZT
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D NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THF NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL
SUBJECT:
NRC INSPECTION REPORT NO. 50-259/98-02.
50-260/98-02.
AND 50-296/98-02
Dear Mr. Scalice:
-
Thank you for your response of June 4, 1998, to our Notice of Violation, issued on May 5, 1998, concerning activities conducted at your Browns Ferry facility.
Me have evaluated your response and found that it meets the requirements of 10 CFR 2.201.
Atter reviewing your letter; we performed an additional evaluation of Violation D in the Notice of Violation and concluded that a violation of 10 CFR 50 Appendix B, Criterion XVI did not occur in this instance.
Accordingly, we will adjust our records to reflect withdrawal of Violation D.
NRC's evaluation of this matter is enclosed.
Your corrective actions associated with Violations A through C in the Notice of Violation will be reviewed during a future inspecti.on.
Your cooperation in this matter is appreci.ated
Sincerely, (Original signed by Loren R. Plisco)
Lor en R. Plisco, Director Division of Reactor Projects Docket Nos.:
50-259.
50-260, and 50-296 License Nos.:
DPR-33, DPR-52, and DPR-68 Enclosure'.
NRC Evaluation cc w/encl:
See page
'P807i 703i0 980702 PDR ADGCK 0500025'P
TVA cc w/encl:
Senior Vice President Nuclear Operations Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Jack A. Bailey, Vice President Engineering and Technical Services Tennessee Valley Authority 3B Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 C.
M. Crane Site Vice President Browns Ferry Nuclear Plant Tennessee Valley Authority P. 0.
Box 2000 Decatur, AL 35602 General Counsel Tennessee Valley Authority ET 10H 400 West Summit Hill Drive Knoxville, TN 37902 Raul R. Baron, General Manager
~ Nuclear Assurance Tennessee Valley Authority 4J Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Karl W. Singer, Plant Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P. 0.
Box 2000 Decatur, AL 35609 Mark J. Burzynski, Manager.
Nuclear Licensing Tennessee Valley Authority 4J Blue Ridge 1101 Market Street
.
Chattanooga.
TN 37402-2801 cc w/encl continued:
See page.3
cc w/encl:
Continued Timothy E. Abney, Manager Licensing and Industry Affairs Browns Ferry Nuclear Plant Tennessee Valley Authority P. 0.
Box 2000 Decatur, AL 35609 Chairman Limestone County Commission 310 West Washington Street Athens, AL 35611 State Health Officer Alabama Department of Public Health 434 Monroe Street Montgomery, Al 36130-1701 Distribution w/encl L.
R. Plisco. RII L. Raghaven, NRR A. DeAgazio, NRR F; J.
Hebdon.
NRR T.
K. Morrissey, RII W.
C. Bearden, RII C.
F. Smith, RII E.
D. Testa.
RII D.
H. Thompson, RII L. S. Mellen, RII PUBLIC NRC Senior Resident Inspector U. S.
Nuclear Regulatory Commission 10833 Shaw Road Athens, AL 35611 OFFICE S IGNATURE NAKE RI:DRP PTDylOZ Dlt 6/ AP
/98 RII DRP LMOrt 6/ @g
/98 RI:EICS QLD
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/98 DR<41M 6/
/98 6/
/98 YES NO 6/
/98 YES NO 6/
/98 YES NO OFFICIAL RECORD COPY DOCINENT NANE:
G:iBFi TERSVLCK9802.LTR
EVALUATION AND CONCLUSION VIOLATION 0 - NOTICE OF VIOLATION MAY 5 1998 On Hay 5, 1998, a Notice of Violation (Notice) was issued for a violation identified during a routine NRC inspection.
Tennessee Valley Authority responded to the Notice on June 4, 1998.
The NRC's evaluations and conclusion regarding the licensee's positions are as follows:
Restatement of Violation
CFR 50, Appendix B, Criterion XVI, Corrective Action, states that measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations.
defective material and equipment.
and non-conformance are promptly identified and corrected.
In the case of-significant conditions adverse to quality, the measures shall assure that the cause. of the condition is determined and corrective action taken to preclude repetition.
Contrary to.the above, a condition adverse to quality was not identified during inspection of the inboard Unit 2 High Pressure Coolant Injection system exhaust line rupture disc.
The process used to determine the "as found" condition of the disc material was not adequate in that the disc material itself was not inspected.
Subsequent inspection identified that the disc material was degraded.
Summar of Licensee's Res onse to Violation 0 The licensee's response presented the position that the incident did not constitute a violation.
The response contained specific sections presenting statements that all applicable code requirements were met for disc assembly inspection and replacement.
The licensee noted that ANSI/ASHE OH-1-1981 specifically states that the visual inspection of the pressure relief devices-is to be in accordance with the Owner's receiving inspection procedures which do not require disassembly of the device.
The Unit 2 disc assembly was being inspected and replaced in accordance with ANSI/ASHE OH-1 requirements.
The response. stated that the licensee voluntarily went beyond the ON-1 requi rements for inspection, identified the conditions adverse to quality, and initiated actions required by 10 CFR 50 Appendix B.
NRC Evaluation of Licensee's Res onse The NRC staff has carefully evaluated the licensee's response and has concluded that a violation of Criterion XVI did not occur in this instance.
Although an NRC inspector questioned if the surfaces of the actual rupture disc material should be inspected, the licensee identified the condition adverse to quality and implemented comprehensive corrective actions within'
reasonable time period.
The corrective actions are discussed in more detail in the following paragraphs.
Enclosure
As stated in Section H1.2 of Inspection Report 98-02, the NRC agrees that the specific requirements of ANSI/ASHE ON-1-1981 were met regarding inspection and replacement of the disc assembly.
The central issue in this incident is that the licensee's process for the "as found" inspection of the disc assembly was not adequate to ensure that the disc material itself was inspected.
As discussed in Inspection Report 98-02, the licensee's implementati,on of OM-1 required performance of an "as found" visual inspection of the disc in accordance'with Surveillance Instruction 2-SI-3.2. 19, Inspection of ASHE Section XI Rupture Discs.
The SI did not provide sufficient guidance to indicate that the disc assembly should be taken apart in order for the pressure retaining components to be properly inspected.
The engineer involved in the inspection was not knowledgeable of the details of the disc assembly and thus it was not understood that disassembly was required to view the surfaces of the pressure retaining components.
Although NRC questioning prompted disassembly of the disc, the actual presence of degraded conditions and the deficiencies in the inspection processes were identified by the licensee.
Problem Evaluation Report 98-0479 states that cracks were found on the rupture disc.
The first listed corrective action was that the inspection requirements of the surveillance procedure should be clarified.
Additional corrective actions were planned to ensure that only single layer disc assemblies would be provided by the vendor for future replacements.
NRC Conclusion As discussed above, the NRC concluded that a violation of Criteria XVI of 10 CFR 50 Appendix B did not occur.