ML20197B588
| ML20197B588 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 12/19/1997 |
| From: | Collins S NRC (Affiliation Not Assigned) |
| To: | Desiree Davis, Norris J DUKE ENGINEERING & SERVICES, YANKEE ATOMIC ELECTRIC CO. |
| Shared Package | |
| ML20197B592 | List: |
| References | |
| EA-97-387, NUDOCS 9712240007 | |
| Download: ML20197B588 (3) | |
Text
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f UNITED STATES
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NUCLEAR REGULATORY COMMISSION l
waswiwatow, o.c. senswen December 19, 1997 EA 97 387 Mr. Don K. Davis, President
& Chief Executive Officer Yankee A'9mic Electric Company 580 Ms.. Street Bolton, Massachissetts 017401398 Mr. John F. Nor :s, President
& Chief Executive Officer Duke Engineering & Services Co.
P.O. Box 1004 Charlotte, North Carolina 2C201 1004
SUBJECT:
DEMAND FOR INFORMATION TO YANKEE ATOMIC ELECTRIC COMPANY AND TO DUKE ENGINEERING & SERVICES RE: PROVIDING INADEQUATE ENGINEERING ANALYSES AND MATERIALLY INCOMPLETE AND INACCURATE INFORMATION TO AN NRC LICENSEE (NRC 01 Report No.
1 95-050)
Deat Messrs. Davis and Norris:
The enclosed Demand for Information (Demand) is being issued to obtain information the NRC considers necessary to determine whether Yat,xee Atomic Electric Company (YAEC) and Duke Engineering & Services Co. (DE&S) should continue to provide engineering analyses, and in particular Less of Coolant Accident (LOCA) analyses, to NRC power reactor licensees. It is the NRC's understanding that subsequent to the events described in the enc losed Demand (Enclosure 1), Duke Engineering & Services purchased the YAEC Loss-of-Coolant Accident (LOCA) Group, which performed the above described engineering ana!yses. Concurrent with the issuance of this Demand, Maine Yankee Atomic Power Co.(MYAPCo)is being notified of apparent violations associated with inadequate LOCA analyses and providing inaccurate information to the NRC (Enclosure 2).
YAEC has routinely provided a jineering services to MYAPCo. In particular YAEC provided analyses of emergency core cooling system (ECCS) performance used by MYAPCo to c'emonstrate compliance with 10 C. F. R. i 50.46 and Appendix K to 10 C.F.R. Part 50.
Specifically, YAEC prepared the small break LOCA analysis which was utilized by MYAPCO during its operating Cycle: 14 and to support its reload analyses for operating Cycles 14 and 15.
See YAEC 1868, " Maine Yankee Small Break LOCA Analysis" (RELAPS'i4 SBLOCA analysis).
YAEC also prepared the large break LOCA analys!4 utilized by MYAPCO for Cycles 14 and 15.
See YAEC 1160, " Application of Yankee WREM BASED Generic PWR ECCS Evaluation Model to Maine Yanken"(WREM LBLOCA analysis).
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3 As a resut of an NRC technical review conducted at YAEC headquarters in Bol Massachusetts on December 11 14,1995, and an investigation conducted b investigations, the NRC concludes that by YAEC's preparation and approval SSLOCA analysis and the WREM LSLOCA analysis, and by YAEC's prep of the Core Performance Analysis Reports (CPARs) used to support Cycle 1 i
operation of Maine Yankee, YAEC caused MYAPCo to be in apparent violation of 1l singly or combined, were not capable of acceptab performance for the portion of the break spectrum between 0.35 ft' and at leas was not possible to confirm that the limiting break had been identifled and tha the NRC concludes that YAECcore cooling system was capable of muigatin Wed MYAPCo with information that was not complete and accurate in all material respects togarding this noncompliance with 10 C.F.R. $
thus caused MYAPCo to apparently violate 10 C.F.R. l 60.9(a) by maintaining CPA contained information which was not complete and accurate in all material respects connection with MYAPCo's Cycle 14 and Cycle 15 reload analyses.
Additionally, the NRC concludes that as a result of hs incorrect calculation o misapplication of the Alb-Chambre cortolation, and inadequate QA review of YA caused MYAPCo to rely on an unacceptable SBLOCA evaluation model which ove core cooling and overstated the conservatism of the evaluation model for Cycle in apparent violation of 10 C.F.R. $ 50.46(e)(1). Finally, the NRC concludes tha unacceptable "Best Estimate" SSLOCA analysis to determine the effects of a reductio generator pressure on LOCA analyses YAEC caused MYAPCo to apparently violate
$ $0,46(a)(1). Specifically, MYAPCo relied upon this unacceptable *Sest Estimat evaluation model to calculate ECCS cooling performance in connection with a analysis concoming the effects of a reduction in steam generator pressure.
A copy of the Synopsis of NRC 01 Report No.195-050, " Maine Yankee Atomic Alleged Deliberate Failure to Comply with NRC Re with Enclosure 2.
YAEC and DE&S have 30 days from the date of this Demand for informat oath or affirmation. After reviewing your response the NRC will determine whether f action is warranted. in the absence of a response,to this Demand for informatio will proceed to determine what, if any, enforcement action is warranted by the f the enclosed Demand for information.
A copy of this letter and Ms enclosures are being sent to the YAEC LOCA the YAEC LOCA Principal Engineer. These individuals are not voquired to m the Demand for information, but may do so, under oath or affirmation, if they s the same time frames as specified for your response.
Questions concoming this Demand for information should be addressed to Mr. J Lieberman, Director, Office of Enforcement, who can be reached at (301) 415
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3 in accordance whh 10 C.F.R.
enclosures, and your response $ 2.790 of the NRC's " Rules of Practice," a copy will be placed in the NRC Public Document Room (PDR). To the extent g ossible, your response should not include any personal pdvocy, proprietary, or asfogustds information 60 that it can be placed in the PDR without redaction.
or proprietary information is necessary to provide an acceptable response, then pleas bracketed copy of your response that identifies the informction that should be protected redseted copy of your response that deletes such information if you request withholdi such material, youms) specifically identify the portions of your response that you seek to h withheld and provide in detail the bases for your claim of withholding (e.g., explain why disclosure of information will create an unwarranted invasion of personal privacy or prov information required by 10 C.F.R. I 2.790(b) to support a request for withholding confide commercial or financialinformation). If safeguards information is necessary to provide en occeptable response, olesse provide the level of protection, described in 10 C F.R. I 73.21.'
$1ncerely, ctor Office of Nuclear Reactor Regulation
Enclosures:
- 1. Demand for information
- 2. Letter to Michael Sellman, MYAPCo, dated 12/1g/g7 from H. Miller, Regional Administrator w/ enclosures en w/ enc:
n iichael B. Sellman, President, MYAPCo LOCA Group Manager, YAEC I,>CA Principal Engineer, YAEC G. Leitch, Vice President, Operations, M'/APCo M. Meisner, Vice President, Licensing and Regulatory Compliance, MYAPCo R. Fraser, Director of Engineering, MYAPCO P. Anderson, Project Manager, YAEC W. Odell, Director of Operations, MYAPCo M. Ferri, Director of Decommissioning, MYAPCo L Diehl, Manager of Public and Govemmental Affairs, MYAPCo J. Ritsher, Ropes and Gray P. Dostie, State of Maine Nuclear Safety inspector U. Vanags, State of Maine Nuclear Safety Advisor C. Brinkman, Combustion Engineering, Inc.
First Selectmen of Wiscasset State of Maine Planning Officer Nuclear Safety Advisor State of Maine, SLO Designee State of Maine Planning Officer Executive Department R. Shadis, Friends of the Coast i
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