IR 05000413/1998013
| ML20210L906 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 08/02/1999 |
| From: | Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Gordon Peterson DUKE POWER CO. |
| References | |
| 50-413-98-13, 50-413-98-16, 50-413-99-11, 50-414-98-13, 50-414-98-16, 50-414-99-11, EA-98-477, NUDOCS 9908100058 | |
| Download: ML20210L906 (39) | |
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August 2,1999 EA 98-477.
Duke Energy Corporation
- ATTN: Mr. G. Site Vice President
- Catawba Nuclear Station 4800 Concord Road York, South Carolina 29745
. SUBJECT: NRC INTEGRATED INSPECTION REPORT NOS. 50-413,414/98-13 AND 50-413,414/98-16, AND NRC SPECIAL INSPECTION REPORT NOS.
. 50-413,414/99-11
Dear Mr. Peterson:
This refers to inspections conducted by the Nuclear Regulatory Commission (NRC) between
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August 1998 and May 1999 at the Catawba facility, to review various aspects of the Unit 1 and 2 ice condensers. The inspections were specifically conducted to review maintenance and surveillance testing of the Unit 1 and 2 ice condensers. The NRC reviewed these issues after your identification of problems with the Unit 1 ice condenser program, which resulted in your decision to shut down Unit 1 in August 1998. In addition, an Office of investigations (01)
investigation was initiated on October 13,1998, to determine if a licensee employee willfully failed to identify and take corrective actions regarding blocked steam flow passages in the Catawba Unit 1 ice condenser. The synopsis of Ol Report 2-1998-020 was provided to Duke Energy Corporation (DEC) by letter dated June 8,1999.
An open, predecisional enforcement conference was conducted in the Region 11 office on July 20,1999, with you and members of your staff to discuss the apparent violations, the root causes, and corrective actions to preclude recurrence. A list of conference sttendees and copies of the NRC's and your presentation materials are enclosed.
Based on the information developed during the inspections, the Ol investigation, and the information you provided during the conference, we have concluded that six violations of NRC requirements occurred. These violations are: (1) the failure to promptly identify and correct a condition adverse to quality in accordance with 10 CFR 50, Appendix B, Criterion XVI. The adverse condition was ice blockage of steam flow passages in Unit 1, Bay 5 of the ice condenser in excess of the Technical Surveillance (TS) Requirement 4.6.5.b.2 from June 1996 until August 1998; (2) the failure to adequately conduct TS Surveillance Requirement 4.5.2.c for
. Unit 1 and Unit 2 ice condensers as evidenced by the discovery of a substantial amount of debris in both condensers during an August 1998 outage in Unit 1 and a September 1998 outage in Unit 2; (3) the failure to maintain Unit 1 and Unit 2 ice condenser lower inlet doors
- operable while the Units were operating in Modes 1-4 as required by TS (TS 3.6.13 for Unit 1
- and TS 3.6.5.3 for Unit 2). The doors were found to be inoperable due to their being impaired from opening fully by ice buildup, but capable of performing their safety function; (4) the failure to promptly identify and correct a condition adverse to quality in accordance with 10 CFR 50, Appendix B, Criterion XVI. The adverse condition was damage, such as denting and buckling,
. of a number of Unit 1 and Unit 2 ice condenser baskets. . This damage exceeded vendor supplied acceptance criteria as found during August and September 1998 outages in Unit 1 and
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4-DEC 2 Unit 2, respectively; (5) the failure to adhers to the requirements of 10 CFR 50, Appendix B, Criterion V, involving the as-installed intermediate deck door botting and structural beam bolting not being in accordance with design requirements as defined by construction drawings, and as discovered in Unit 1 during the August 1998 outage; (6) three examples of failure to satisfy the requirements of 10 CFR 50, Appendix B, Criterion Ill, in that design changes and/or field changes were made to Unit 1 and Unit 2 ice condensers without being subjected to design control measures commensurate with those applied to the original design and which were not verified for adequacy of design until the August 1998 and September 1998 outages.
The NRC has determined that each of the six violations should be classified individually in accordance with the " General Statement of Policy and Procedures for NRC Enforcement
' Actions"(Enforcement Policy), NUREG-1600, at Severity Level IV. The basis for our determination stems from our review of the actual and potential safety consequences and the associated risk of nuclear fuel damage or release of radioactive material to the environment for j each violation. Had an actual or potential event requiring system operation occurred during the '
time frame of the violations, the ice condenser system was capable of performing its intended !
- safety function. In addition, the containment sump (part of an emergency core cooling system)
could have performed its safety function even with the accumulation of debris in the sump area of each ice condenser. In each instance, the safety system remained degraded but operable, and the increase in risk was determined to be negligible.
- As indicated in our June 8,1999 letter, the results of our inspections and investigation indicate inadequate control or oversight of the surveillance, maintenance and correction of problems associated with the ice condenser. At the conference, you stated that the root causes and contributing factors which led to the violations included a lack of procedural guidance to perform post maintenance inspection and testing to verify ice condenser flow passage operability, inadequate ice basket inspection techniques, inadequate questioning attitude and follow up of deficient conditions by individuals responsible for performing maintenance and engineering activities associated with your ice condenser program, an inadequate understanding of the Technical Specification surveillance requireme.its by maintenance personnel who performed the ice condenser surveillances, and inadequate interface or communication between the maintenance and engineering groups who oversaw ice condenser operations. As a result of these findings, you also concluded that the root causes and contributing factors stemmed from inadequate oversight of ice condenser maintenance and engineering activities.
As a result of the violations, most of which were identified by DEC staff, you implemented prompt and comprehensive corrective actions. These included an extensive review of the root causes, management controls and processes related to other passive safety systems at the
. Catawba site in order to identify similar problems or deficiencies. Based on this review, DEC concluded that the oversight deficiencies were limited to the ice condenser program. Other corrective actions included improved surveillance procedures and the development of criteria for taking action on surveillance results, changes in accountability in the ice condenser oversight j organization, shutting down Unit i until the Bay 5 condition was corrected, examining both Unit 1 !
and Unit 2 for extent of condition of problems found, required audits of the ice condenser l program by both maintenance and engineering representatives, the use of a job sponsor for contractor oversight, correction of examples where the ice condenser design was inappropriately modified, and establishment of a review session with appropriate workers prior to each outage to discuss the criteria for action based on post maintenance and surveillance test l results.
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DEC 3 Discussions were also held at the enforcement conference regarding whether DEC employees or management willfully violated regulatory requirements. . Based on these discussions and
-- review of 01 Report 2-1998-020, the NRC concluded that the violations as discussed above were not willful, but rather.were due to the root causes and contributing factors as described above.-
Based on our review of your corrective actions, the safety significance of each violation, and the lack of willfulness associated with each violation as discussed in this letter, we have determined that these six violations should be treated individually as Non-Cited Violations, consistent with Appendix C of the NRC Enforcement Policy. Therefore, you are not required to respond to this
' letter, unless the description therein does not adequately reflect your corrective actions or your position.
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this lett 1, its enclosures, and any response will be placed in the NRC Public Document Room (PDR). To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without redaction.
if you have any questions regarding this letter, please contact Bruce Mallett, Director, Division of Reactor Safety, at (404) 562-4601.
Sincerely, Original signed by LAR Luis A. Reyes Regional Administrator Docket Nos. 50-413, 50-414 License Nos. NPF-35, NPF-52
Enclosures:
1. List of Conference Attendees 2. NRC Presentation Material 3. DEC Presentation Material
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DEC 4
REGION 11 OFFICE, ATLANTA, GEORGIA 1. OPENING REMARKS AND INTRODUCTIONS L. Reyes, Regional Administrator 11. NRC ENFORCEMENT POLICY S. Sparks, Acting Enforcement Officer Enforcement and Investigations Coordination Staff Ill. SUMMARY OF THE ISSUES L. Reyes, Regional Administrator IV. STATEMENTS OF CONCERNS / APPARENT VIOLATIONS B. Mallett, Director, Division of Reactor Safety V. LICENSEE PRESENTATION VI. BREAK / NRC CAUCUS Vll. NRC FOLLOWUP QUESTIONS Vill. CLOSING REMARKS L. Reyes, Regional Administrator Enclosure 2
p,..
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O STATEMENT OF APPARENT VIOLATIONS The failure to promptly identify and correct a condition adverse to quality in accordance with 10 CFR 50, Appendix B, Criterion XVI, involving excessive ice condenser flow blockage in Unit 1, Bay 5 which did not meet Technical Specification Requirement 4.6.5.b.2. (eel 50-413/98-13-01).
The failure to adequately conduct Technical Specification Surveillance Requirement 4.5.2.c for Units 1 and 2 ice condensers as evidenced by the identification of a substantial amount of loose debris in both containment buildings (eel 50-413/98-13-03 and 50-414/98-16-03).
The failure to maintain the Unit 1 and Unit 2 ice condenser inlet doors operable in Modes 1-4 as required by Technical Specifications (TS 3.6.13 for Unit 1; TS 3.6.5.3 for Unit 2) due to the fact that the inlet doors were impaired by ice and frost buildup
]
(eel 50-413/99-11-01 and 50-414/98-16-04).
The failure to promptly identify and correct a condition adverse to quality in accordance with 10 CFR 50, Appendix B, Criterion XVI, involving damage, such as denting and buckling, to a number of Unit 1 and 2 ice condenser baskets which exceeded vendor supplied acceptance criteria (eel 50-413/98-13-05 and 50-414/98-16-01).
Note: The apparent violations discussed in this PREDECISIONAL enforcement conference are subject to further review and are subject to change prior to any resulting enforcement action.
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O STATEMENT OF APPARENT VIOLATIONS The failure to adhere to the requirements of 10 CFR 50, Appendix B, Criterion V, when the Unit 1 ice condenser intermediate deck door bolting and structural beam bolting requirements as defined by construction drawings were not implemented in accordance with these drawings (eel 50-413,414/98-13-07).
The failure to satisfy the requirements of 10 CFR 50, Appendix B, Criterion Ill, in that the design changes and/or field changes had been made to Unit 1 and Unit 2 ice condensers without being subject to design control measures commensurate with those applied to the original design and which were not verified for adequacy of design (eel 50-413,414/98-13-08).
A synopsis of Office of Investigations investigation Report No. 2-1998-020 states that based on the evidence obtained during this investigation, it was not possible to identify the person who allowed the blocked air flow passages to be returned to service. Consequently, it was not possible to determine whether the responsible party deliberately left air flow passages in a degraded condition.
Note: The apparent violations discussed in this PREDECISIONAL enforcement conference are subject to further review and are subject to change prior to any resulting enforcement action.
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e foth 9
sh rt ei s
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