ML20151T723

From kanterella
Jump to navigation Jump to search
Summary of 980821 Meeting W/Nei in Rockville,Md Re NRC GL 98-04, Potential for Degradation of Eec Sys & CSS After LOCA Because of Construction & Protective Coating Deficiencies & Foreign Matl in Containment
ML20151T723
Person / Time
Issue date: 09/03/1998
From: John Hickman
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
GL-98-04, GL-98-4, NUDOCS 9809100130
Download: ML20151T723 (7)


Text

_

e September 3, 1998 ORGANIZATION:

NUCLEAR ENERGY INSTITUTE

SUBJECT:

SUMMARY

OF MEETING TO DISCUSS NRC GENERIC LETTER 98-04 On August 21,1998, the NRC stef/ met with representatives of the Nuclear Energy Institute (NEI) in Rockville, Maryland, to discuss NRC Generic Letter 98-04 (GL 98-04), " Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Materialin Containment."

NEl staff stated that the intent of the meeting was to have a general discussion of GL 98-04 and to prepare for a workshop on GL 98-04 to be conducted September 10,1998. The meeting began with a brief presentation by the, NRC staff of the intent of GL 98-04. NEl staff then presented a list of questions (attached) on GL 98-04 that they anticipate will need to be addressed at the workshop. The NRC staff then discussed how the Maintenance Rule applies to coatings, current research activities on coatings, and current research activities on debris generation, transport, and accumulation for pressurized water reactors. Finally, the proposed agenda for the workshop on September 10,1998, was reviewed.

ORIG. SIGNED BY John B. Hickman, Project Manager Project Directorate 111-2 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation Attachments:

DISTRIBUTION: (hard copy w/all attchs)

1. Meeting Agenda Central File PUBLIC
2. Questions on GL 98-04 PDlll-2 r/f JHickman
3. List of Attendees OGC ACRS
4. Draft Agenda for September 10,1998, Meeting (e-mail):

SCollins/FMiraglia BBoger EAdensam.

SRichards CMoore -

TMartin (SLM3)

THiltz (TGH)

LCampbell RCorreia JDavis RElliott RGramm RLobel.

MMarshall i

ASorkiz i

l 000081

>0)

DOCUMENT NAME: G:\\CM\\ BYRON \\GL9804MT. SUM To rtceive a copy of this document, indicate hthe box:

"C" = Copy without enclosures "E" = copy with e.Asures "N" = No copy OFFICE PM:PDill-2

(

4:491$2 f_/EMCB c

4-SCSB lT?

D:PDill-2 l f.,

NAME JHickman:spG/8# DIVhfo'rd JDavisM IV RElliott Gf;6 SRici ards SF t

DATE 08/ 2 9/98 '

06/fJ/98 08/1) U98 0)/ 3 /98 h) Og/ 3 /98 OFFICIAL RECORD COPY 4g_y Q y 0 4 y. q (4 Q 98o9

"" :"oo:3o,so,o3 g.fy9

""*"'"*"W SC RiF CMEB mpv

  • arrog g

UNITED STATES j

NUCLEAR REGULATORY COMMISSION 2

WASHINGTON, D.C. 30666-0001 49.....,o September 3, 1998 ORGANIZATION:

iUCLEAR ENEP.GY INSTITUTE

SUBJECT:

SUMMARY

OF MEETING TO DISCUSS NRC GENERIC LETTER 98-04 On August 21,1998, the NRC staff met with representatives of the Nuclear Energy Institute (NEI) in Rockville, Maryland, to discuss NRC Generic Letter 98-04 (GL 98-04), " Potential for Degradetion of the Emergency Core Cooling System and the Centainment Spray System After a LosNM AccM Because of Construction and Protect,ve Coating Deficiencies and Foreign Motorial b Containment."

NEl staff stated that the bient of the meeting was to have a genormi discussion of GL 96-04 and to prepare for a workshop on GL 98-04 to be conducted September 10,1998. The meeting began with a brief presentation by the NRC staff of the intent M GL 98 04. NEl staff then premonted a list et queehens (attached) on GL 9844 that they aruticipate will need to be addressed atthe workshop. The NRC staff then discusscd how the Maintenance Rule applies to coatings, current research activities on coatings, and current research activities on debris generation, transport, and accumulation for pressurized water reactors. Finally, the proposed agenda for the workshop on September 10,1998, was reviewed, s

/roject DwectorateilW!B. Hekmen, Project Manager P

Division of Reactor Projects - lil/IV Office of Nuclear Reactor P="*n Attachments:

1. Meeting Agenda
2. Quest.'ons on GL 98-04
3. List of Attendees
4. Draft Agenda for Septer:,ber 10,1998, Meeting t

j

MEETING To Discuss GL-98-04 August 21,1998 m NRC One White Flint North CR 3-B4 m Rockville Maryland AGENDA TIME TOPIC PRESENTFR 9:00

Introductions

9:05 NRCStaffPresentation Nno 9:45 Key Areas ofIndustry Concern / Comment on GL 98-04 NEllindustry 10:30 Discussion All 11:00 PlanningforIndustry Workshop cn GL BR-N All 11:30 Adjournment

^

DRAFT Topics for Discussion en Generic Lett:r 9844 Questions on GL 98-04 Required Responses 1.

Our andernesading is tbst the sosponse to the infannesian sequested in (1) pertains only to Service Level I coatings inside containment. Is this correct?

2.

In (2) (ii) the staff states...."If a licensee can demonstrate this compliance [to 10 CFR 50.46] without quantifying the amount of unqualified coatings, this is

-+--

" Please discuss the type ofinformation the staff would expect to

^

make this demonstration of compliance.

3.

With regard to item (1) of the " Required Response", what does the NRC expect relative to vendosupplied equipment?

4.

For item 2.(i).(b), what informatian should be submitted on how the limit for the amount ofunqualified protective costings allowed in containment is detennimed.

GameralQuestionsen CL9844

.5.

Please descrite the process and schedule the staffplans to follour to sumisuse licenseesuspeanus.

6.

Does the staff have, or is them in preparation, a Temporary Instruction (or similar) to provide guidance in the performance ofinspections of coatings in i

containment and licensee coating programs? If not currently available, what is the schedule for completion?

7.

Specifically, what criteria does the staffintend to provide to inspectors (e.g., in a Tennporary Instmetion) in sugards to the acceptable quantity of degraded or unqualified costing.

8.

The generic letter states tiet "the NRC inlands to use fmfanmation psovidsdin response to the GL] to assess whether current teguistory seguissessass ase being -.dy impleA and whether they should be sosised." Pisese idendfy 1bc seguissory requirements and guidenne dae=ments included within the scope of this planned as=e===ent 9.

If the staff concludes that a zevision to regulations is appropriate, does the staff anticipate the need to perform a backfit review for applicability to current licensees, or is it =P that the nevisions would only apply to future licensees.

i i

DRAPT Tepics f:r Discussi:n c2 Generic Letter 98-04

10. It is our understanding that the NRC has in progress or is planning to conduct research related to coatings. Please desenbe fue ongoing or pha~i activities inthisarea. Whnyaddress:

a) The goals and objective ofthe research b) The scope of testing c) Schedule for completion of testing and publication ofresults d) Discuss the NRC's need fortesting and research given currentindustry activities e) If NRC research and testing it, planned, what criteria will the NRC use to evaluate licensee's 120 day responses absent the testing program's conclusion and will GL 9g-04 rnmin open pending completion of the NRC testing program.

11. The generic letter states that the NRC may conduct inspections to ensure compliance with regulations that provide assurance that the ECCS and the safety selsted CSS remain A of;A=2a= their intended safety f*t a)

What is the currest status of!= ;=;_'m plans?

b)

Whatisthe midscope of theinspections?

Questions on Related Issues

12. The staff has previously communicated that it plans to re-assess PWR sumps in light of the information leamed from the issue on BWRs. Please provide an update on staffplans in this mea and the schedule for completion.
13. In a March 20,1998 lener to Gary Holahan, the Nuclear Ene gy Institute stated that coordination ofindustry and NRC activities is W to better understand potential problem areas and concems about blockage of PWR sump screens by LOCA-generated debris. WhatareNRC plans related to w n=h ofthese AddM
14. The PWR Owners Groups have, in letters to the NRC, requested the use of LBB provisions to allow the exclusion of the dynamic effects of pipe rupture loads in the consideration of debris generation and coatings removal following a design basis LOCA. What is the status of the NRC evaluation of these requests?

-.. -. -. - - ~. -.

LIST OF ATTENDEES FOR MEETING HELD ON AUGUST 21.1998 NAME AFFIL1ATION John Butler NEl Dave Menfuen NEl LarryL. Campbell NRC/NRR Rich Correia NRC/NRR Jim Davis NRC/NRR Rob Elliott NRC/NRR Bob Gramm NRC/NRR John B. Hickman NRC/NRR Richard Lobel NRC/NRR Mike Marshall NRC/RES Al Serkiz NRC/RES Barrylubin AB N Jeffery Brown APS/CEDG Kevin Anstee Baltimom Gas & SocIne Sam MaGgio Bertistihiundser Jon R. Cavallo W 28. inc.

John Lewand Commonwealth Edison Company Ron Janowiak Commonwealth Edison Company Larry Waggoner Duke-Energy Ray Rosten Duke Engineering & Services Les England Entergy Operations John M. Giscion EPRI l

Gartt.Doldour FPL Tom Green GE/BWROG C Gilbert Zigler ITS Corp.

Jim Fulford NUS-LIS KarlJacobs N.Y.P.A.

Bill Houston Sequois Cenaulting Group Altheis Wyche SERCH Licensing /Bechtel Jeff Brauum SNSiBWROG Dennis Evans Southem Califomia Edison Bob Howard TVA Timothy S. Andreychek Westinghouse i

Bob Temple Wmston & Straun 4

ATTACHMENT 3

Workshop on Generic Letter 98-04 September 10,1998 I Hilton at Washington Dulles Airport I Herndon, Virginia DRAFI AG4hlDA TIME TOPIC PRESENTEE 8:00 Introduction & Opening Remarks NEl 8:15 Background Discussion Regulatory Requirements BWROG Programs i

EPRI/NUCC Containmant Coatings Guideline NEISump Perb-Task Force

)

9:30 Break 9:45 GL 38 04 Panel 5=e""~n Overview of GL 9644 Coordinated Industry Response 11:00 Key Issues and Topics for Discussion with NRC

-l 12:00 LUNCH j

Berinnine of Onen Portion ofWorkehne 1:00 NRCltr.4ven on GL 98-04 Information on current issues and activities of NRC staff mlated to NRC C-c Intter 9644.

1:45 Question and Answer.1%riod on GL 98-04 3:00 NRC Action Plan to Address ECCS Recirculation Issues End of Onen Portion of Meeting 3:30 Break 4:00 Roundtable Discussion 5:00 Adjourn SPONSORED BY THE NUCLEAR ENERGY IN S TITU T E

-