ML20211J061

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Summary of CRGR Meeting 333rd on 981208 Re Closure of Bulletin 97-02, Puncture Testing of Shipping Packages Under 10CFR71 & Draft Final GL, Lab Testing of Nuclear-Grade Activated Charcoal. List of Attendees Encl
ML20211J061
Person / Time
Issue date: 03/08/1999
From: Jerome Murphy
Committee To Review Generic Requirements
To: Travers W
NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
Shared Package
ML20211J067 List:
References
IEB-97-002, NUDOCS 9909030029
Download: ML20211J061 (48)


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  • NUCLEAR REGULATORY COMMISSION S wasumotoN, D.C. asememH g

e.... March 8, 1999 MEMORANDUM TO: 'Niiiiam D. Travers Executive Director for Operations FROM: Joseph A. Murphy, Chairman Committee To Review Generic eq ements

SUBJECT:

MINUTES OF THE CRGR MEETING NUMBER 333 .

The Committee To Review Generic Requirements (CRGR) met on Tuesday, December 8,1998, from 9:00 a.m. to 3:30 p.rri, to Md the Committee's 333* meetirig. Attachment 1 contains the list of attendees.

W. Kane, W. Hodges and D. Tiktinsky, all of NMSS, briefed the CRGR on closure of Bulletin 97-02, " Puncture Testing of Shipping Packages Under 10 CFR Part 71." Attachment 2 contains the staff's presentation material. In 1997, the staff became aware that two holders of NRC Certificates of Compliance for transportation packages had performed the puncture test using a bar that was not property mounted as =p+C in 10 CFR 71.73(c)(3).Bulletin 97-02 was issued to notify the certificatees about quality-assurance-related concems in conducting the puncture test. However, the CRGR did not review this bulletin prior to issuance. The staff proposed to close out Bulletin 97-02 by requiring: (1) no further action on previously approved packages Although the staff was aware that for these packages puncture testing had not been performed ceii.cuy, this decision was based on the fact that there have been no incidences involving these packages; and (2) commencing April 1999, packages to be fabricated meet the puncture testing requirements. The Committee accepted the staff's proposal for closure to Bulletin 97-02.

S. Newberry, J. Segala and H. Walker, all of NRR, presented for CRGR review and endorsement the draft final generic letter (GL) titled " Laboratory Testing of Nuclear-Grade Activated Charcoal." In this draft, the staff had incorporated resolution of public comments. The CRGR had reviewed the proposed generic letter on September 9,1997, at the Committee's 310* meeting, and endorsed for issuance for public comments.

Attachment 3-A contains the staff's presentation material. The staff has determined that the ASTM D3803-1979 standard for charcoal testing is inadequate because the test results are not reproducible. Therefore, the staff proposes to-require the licensees to consider the ASTM D3803-1989 standard. The Committee was informed that some licensees are already using the ASTM D3803-1989 standard, but their technical specifications (TS) refer to the ASTM D3803-1979 standard. These hoensees, although they are using a more reliable test standard, are nevertheless in violation of their TS. There are others who are using the ASTM D3803-1989 standard as required by their TS.

The Committee made various comments and recommendations. Most importantly, the Committee commerted that the staff is proposing a new requirement; hence it is a backfit. It is in fact a comphance, backfit because the regulations (namely, GDC 19 and 10 CFR Part 100 9909030029 990308 PDR NEETINO333 REVOP lEOCROR PDR dg rg(M N Ifl [ D Nr ,

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William D. Travers 2 guidelines) cannot be met in most cases by using the 1979 standard. Additionally, the Committee recommended that if the staff was requesting information of licensees to determine if their license should be modified, suspended or revoked, it should cite 10 CFR 50.54(f).

Furthermore, since the information is required for a purpose other than to verify compliance with I the licencing basis of a facility, the staff must provide reason (s) for the requested information, and the burden to be imposed on the respondents should also be justified in view of the potential safety significance of the issue to be addressed. The Committee asked the staff to require that the licensees use at least two laboratories in determining the acceptability of the altemate test protocol. The Committee also advised the staff to consider not colltecting laboratory test results, and recom, mended that the licensees are afforded altamate options.

Following the CRGR meeting, the staff requested a meeting with the CRGR Chairman to discuss some exceptions it proposed to take with respect to the CRGR recommendations.

Specifically, (1) allow the licensees to do TS amendment first and charcoal testing later. The test schedule can be determined by the TS to avoid plant shutdown for conducting test; and (2) require plant-specific charcoal testing at the anticipated post-accident temperatures (about 130*C) rather than 30*C. The Chairman accepted both arguments. .

February 22,1999, the staff submitted the revised generic letter for CRGR endorsement, informing the Committee that it has addressed all of the Committee's comments and recommendations, except invoking 10 CFR 50.54(f). Attachment 3-8 contains the revised generic letter endorsed by the Committee, subject to minor comments.

S. Black and R. Gramm, both of NRR, presented for CRGR review and endorsement the draft inspection procedure for graded quality assurance. Attachment 4-A contains the staff's presentation material. The Committee found this inspection procedure unacceptable, as presented, and did not endorse it for issuance. On December 17,1998, in a memorandum to the EDO (Attachment 4-B), the Committee recommended that this inspection procedure not be issued because of the following concoms:

1. The inspection procedure is not performance-based and reads like a Standard Review Plan, better performed by probabilistic risk analysis (PRA)-trained license reviewers.

The majority of NRC inspectors do not possess sufficient PRA expertise to make the proposed judgement calls in a repeatable manner.

2. The inspechon procedure requires a broad scope assessment of the quality and acceptability of the licensee's graded quality assurance (QA) program, but provides no objechvo or deterministic standards against which an inspector can determine acceptability. Consequently, as proposed, the inspection procedure could be implemented by different inspectors in an inconsistent manner, with a large potential for unauthorized backfitting, as licensees attempt to accommodate individual inspector views of what constitutes acceptability.
3. In the context of structure, system, and component categoriMeri, the guidance on inclusion of high-safety-significant-non-safety-related components in the QA program would be considered unauthorized backfitting if pursued by the NRC inspector l

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William D. Travers 3 The Committee recommended that, given the current limited applicability of this proposed j inspection procedure, the staff should consider issuance of a plant-specific temporary '

instruction, tailored to assess the implementation of the individual licensee's graded QA commitments.

D. Matthews and T. Bergman, both of NRR, presented for CRGR review and endorsemerit the l

. l draft Regulatory Guide (DG-1083) titled " Content of the Updated Final Safety Analysis Report in Accordance with 10 CFR 50.71(e)," endorsing NEl 98-03. Attachment 5 contains the staff's presentaten material. The Committee made various comrrents and recommendations. One specific comment that the Committee made was that the statement in the Introduction section of

. DG-1083 implying that this guide will alleviate Millstone-related concems, is not accurate.

Therefore, it should be reworded. The staff appropriately changed the statement to the Committee's satisfaction. In addition, the staff addressed all the remaining comments and recommendations. The CRGR endorsed DG-1083 for issuance on December 22,1998.

In accordance with the EDO's IJiy 18,1983 directive concoming " Feedback and Closure of CRGR Review," a written response is required from the cognizant office to report agreement or disagreement with the CRGR recommendations in these minutes. The response is to be forwarded to the CRGR Chairman and if there is disagreement with the CRGR recommendations, to the EDO for decision making.

Questions coriceinlig these meeting minutes should be referred to Raji Tripathi (415-7584).

Attachments: As stated cc: Commission (5) SECY M. Knapp, DEDE F. Miraglia, DEDO ,

J. Lieberman, OE M. Springer, ADM H. Bell, OlG K. Cyr, OGC J. Larkins, ACRS H. Miller, R-l L. Reyes, R-Il J. Dyer, R-ill E. Merschoff, R-IV C. Paperiello, NMSS A. Thadani, RES S. Collins, NRR '

G. Holahan, NRR W. Kane, NRR J. Strosnider, NRR B. Boger, NRR D. Matthews, NRR e

e

~h Willicm D. TrCvers 3 The Committee recommended that, given the current limited applicability of this proposed inspection procedure, the staff should consider issuance of a plant-specific temporary

' instruction, tailored to assess the implementation of the individual licensee's graded QA commitments.

D. Matthews and T. Bergman, both of NRR, presented for CRGR review and endorsement the draft Regulatory Guide (DG-1083) titled " Content of the Updated Final Safety Analysis Report in Accordance with 10 CFR 50.71(e)," endorsing NEl 98-03. Attachment 5 contains the staff's presentation material. The Committee made various comments and recommendations. One specific comment that the Committee made was that the statement in the introduction section of DG-1083 implying that this guide will alleviate Millstone-related concerns, is not accurate.

Therefore, it should be reworded. The staff appropriately changed the statement to the Committee's satisfaction, in addition, the staff addressed all the remaining comments and recommendations. The CRGR endorsed DG-1083 for issuance on December 22,1998. .

In accordance with the EDO's July 18,1983 directf9e concoming " Feedback and Closure of .

CRGR Review," a written response is required from the cognizant office to report agreement or disagreement with the CRGR recommendations in these minutes. The response is to be forwarded to the CRGR Chairman and if there is disagreement with the CRGR recommendations, to the EDO for decision making.

Questions concoming these meeting minutes should be referred to Raji Tripathi (415-7584).

Attachments: As stated cc: Commission (5) SECY M. Knapp, DEDE F. Miraglia, DEDO J. Lieberman, OE M. Springer, ADM ,

H. Bell, OlG K. Cyr, OGC J. Larkins, ACRS H. Miller, R-l L. Reyes, R-il J. Dyer, R-ill E. Merschoff, R-IV C. Paperiello, NMSS A. Thadani, RES S. Collins, NRR G. Holahan, NRR W. Kane, NRR J. Strosnider, NRR B. Boger, NRR D. Matthews, NRR Distnbution:

File Center (w/atts.) PDR (NRC/CRGR)(w/o atts. 38 and 4B) CRGR SF CRGR CF DDambly BSheron JJohnson, Ril ETen Eyck JJohnson, OCM MVirgilio MFederline STreby JMitchell WHodges CChappell SBlack RGramm DTiktinsky NOsgood BWhite JMyers JRaval BThomas JShapaker HWalker SNewberry JSegala JLyons JHayes GMizuno WBurton REmch MRafky SDinsmore SMagruder - TBergr .an JPeralta LCampbell SWong FAkstulewicz DISK / DOCUMENT NAME: E:\ MINUTES \MITS-333.WPD V"c~.',;2lllll y . c.,,.-;,r . o - . ~o c-OPc cRGfr C CRGR' C h j/ C uma onem @ me w RTg @f

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Attendance List CRGR No. 333 Meeting (December 8,1999)

CRGR MEMBERS NRC STAFF T. Martin (Chairman) J. Lieberman, OE J. Murphy W. Kane, NMSS D. Dambly D. M'atthews, NRR B. Sheron W. Hodges, NMSS J. Johnson S. Black, NRR E. Ten Eyck for M. Knapp, NMSS S. Newberry, NRR J. Raval, NRR l B. Thomas, NRR ,

CRGR STAFF J. Shapaker, NRR l R. Gramm, NRR l R. Tripathi H. Walker, NRR l

G. West (on detail) J. Segala, NRR J. Lyons, NRR F. Akstulewicz, NRR G. Mizuno, OGC T. Bergman, NRR W. Burton, NRR D. Tiktinsky, NMSS M. Rafky, OGC S. Dinsmore, NRR S. Magruder, NRR J. Hayes, NRR J. Myers, OSP N. Osgood, NMSS J. Peralta, NRR L. Campbell, NRR S. Wong, NRR R. Emch, NRR 1 B. White, NMSS I

C. Chappell, NMSS  !

Minutes of CRGR Meeting No. 333, December 8,1998 1

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