ML20210E588
| ML20210E588 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 06/30/1999 |
| From: | Schuelke D NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| FRN-64FR3138, RTR-REGGD-XX.XXX, TASK-*****, TASK-RE 64FR3138-00014, NUDOCS 9907280266 | |
| Download: ML20210E588 (8) | |
Text
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. C 77wima-0% A, $'7p 7 Rad Northern States Power Company PFCEIVED Prairie Island Nuclear Generating Plant lp99 g / g g g 1717 Wakonade Dr. East j Welch, Minnesota 55089 l RULES & D7 T%NCH US .S.4
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June 30,1999 Rules and Directives Branch l Office of Administration U.S. Nuclear Regulatory Commission Washington, DC 20555 l
PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos.50-282 License Nos. DPR-42 l 50-306 DPR-60 l Transmittal of Northern States Power Comrnents on Draft Regulatory Guide DG-1074,
" Steam Generator Tube Integrity" In the Federal Register (January 20,1999), the NRC issued Draft Regulatory Guide DG-1074 for public comment. Comments were requested by June 30,1999. Northern States Power has participated in an industry effort to collect and transmit comments.
Based on our participation and review of this collective effort, Northern States Power endorses the comments transmitted by NEl letter, " Transmittal of Industry Comments on Draft Regulatory Guide DG-1074" and includes the attached additional comments.
In addition to the NEl submittal, it should be further emphasized that the issuance of DG-1074 for public comment does not reflect the current state of the industry /NRC discussion of NEl 97-06 and its supporting generic license change package. The NRC has recognized this joint effort as the best path to a successful resolution of steam generator program issues. Considering the extensive nature of the industry comments and the progress of the joint NRC/ industry effort, it is Northern States Power's position that no further effort be expended in modifying DG-1074; neither by industry nor by the NRC.
In performing a review of the industry comment package, Northern States Power recommends that the NRC focus on severalimportant areas considered principal concerns and contentions. These include:
I 9907280266 990630 PDR REGGD XX.XXX C PDR
.USNRC NORTHERN STATES POWER COMPANY June 30,1999 Page 2 e in late 1998, the NRC agreed that the best path to a successful resolution of the questions surrounding steam generator program requirements was through approval of a generic license change package implementing the requirements of NEl 97-06 and its referenced EPRI Guidelines. DG-1074 does not reflect the current positions of the NRC or the industry on key issues. As a result, accepting the positions expressed by DG-1074 would result in a loss of six months of productive work on resolution of steam generator program requirements. Similarly, the potential for conflict and confusion that arises with parallel industry and NRC guidance documents is obvious. The recent focus has been on the industry guidance and should remain there. As stated previously, no further effort should be expended in modifying DG-1074. It should be deleted from all NRC lists of publications.
. DG-1074 is not clear on the issue of severe accidents and risk-informed
- methods. The draft regulatory guide repeatedly makes reference to " risk-informed" approaches in the context of " core damage severe accident"
, analysis and calls for a " risk assessment" to be performed, while in other l l.
areas it states that the intent is to ensure that steam generator tubes "are capable of performing their intended safety functions consistent with the licensing basis." This seems to infer that severe accident risk assessment is part of the licensing / design basis of the plant. This is clearly not the case before now and represents a major backfit in regulation.
- DG-1074 requirements contain excessive conservatism, given the safety l
margins currently contained in each plant's licensing basis. The treatment of analysis inputs and analysis variability goes well beyond typical design analysis for RCS pressure boundary components as governed by ASME Code. This excessive conservatism is considered punitive, is not performance based, and is contrary to a goal established at the beginning of the review of steam generator regulation.
l
. The draft regulatory guide contains an inconsistent level of detail. DG-1074 provides very detailed guidance in some instances, while in other situations the guidance is at such a high level that the desired licensee action is unknown. For example, the NDE Data Acquisition and Analysis regulatory l position is so detailed concerning plant procedures that it includes requirements for procedures that regulations do not even dictate be :
implemented, e.g., independent two-party analyses. Detailed guidance such !
as this detracts from the real intent of the guidance-to ensure that steam generator tube integrity is maintained. On the other hand, where risk is discussed in the draft guide, a typical statement such as, "The staff encourages licenses to follow risk-informed approaches..." can be found.
dg 1074 conenents. DOC
USNRC NORTHERN STATES POWER COMPANY June 30,1999 Page 3 The industry continues to wrestle with understanding the conditions requiring consideration of severe accident risk, the method of assessment and criteria by which to judge success or failure.
. Many of the requirements in DG-1074 do not meet the intent of a performance-based regulation. For example, the draft guideline includes requirements that go well beyond what is required for plants applying NRC and ASME Code-approved repair criteria for repair on detection. Many of the requirements included in the draft guideline are taken from previous NRC staff documents and positions regarding submittals for alternative repair criteria. In these special cases, such prescription may be appropriate, but this type of prescriptive guidance in a regulatory guide is inconsistent with the attributes of performance-based regulation.
In addition to the industry comments enclosed with the NEl letter, Northern States Power has the additional comments submitted with this letter as Attachment 1.
Response to these comments and any other questions regarding this letter or the enclosure should be directed to Richard P Pearson at Northern States Power (651-388-1121 ext 4224, richard.pearson@nspco.com).
p Donald A. Schuelke Plant Manager Prairie Island Nuclear Generating Plant c: Document Control Desk, NRC Regional Administrator- Region Ill, NRC Senior Resident Inspector, NRC NRR Project Manager, NRC J E Silberg l
l Attachment I
dg 20*F4 comments. DOC
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