ML20153B043
ML20153B043 | |
Person / Time | |
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Issue date: | 09/15/1998 |
From: | Dante Johnson NRC (Affiliation Not Assigned) |
To: | Beckner W NRC (Affiliation Not Assigned) |
References | |
PROJECT-689 NUDOCS 9809220290 | |
Download: ML20153B043 (5) | |
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' MEMORANDUM TO: William D. Becknir, Chief September 15,.1998 Technical Spicifications Branch Associita Director for Proj: cts, NRR '
FROM: Deborah L. Johnson, Information Management Assistant l Technical Specifications Branch ,
Associate Director for Projects, NRR
SUBJECT:
FORTHCOMING MEETING WITH NEl TECHNICAL SPECIFICATIONS TASK ;
. FORCE l DATES & TIME: September 24,1998 ,
9:00 a.m. to 4:00 p.m.
LOCATION: U.' S. Nuclear Regulatory Commission 11555 Rockville Pike One White Flint North Building Room O-6B11 Rockville, MD 20852 PURPOSE: To discuss proposed Standard Technical Specification changes.
PARTICIPANTS *: NRC INDUSTRY TSB Staff NEl TS Task Force 1 HICB Staff SCSB Staff EELB Staff ?
S. Magruder, Project 689 ;
Attachments: 1. Meeting Agenda g 2. Project 689 Addressee Ust ;
cc: (via e-mail)
'J. Davis, NEl
' D. Hoffman, EXCEL l D. Williamson, WOG '!
~ T. Weber, CEOG l B. Ford, BWROG l N. Clarkson, BWOG D. Wuokko, BWOG CONTACT: Debbie Johnson, NRR u
301-415 3060 /f nE " Meetings between NRC technical staff and applicants or licensees are open for interested i@a.-48340, m to embers
" Commissionof the 9/20/94.
Policypublic, Statementpetitioners,intervenors,
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on Staff Meetings Open to theor y
other Public" partiesRegister 59 Federal to attend as ob 1
DISTRIBUTION: See Next Page
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_ DOCUMENT NAME: GADU\MTGNTE09.9s 'see previous concurrences
' ' OFFICE IMA:TSB:ADPR:NRR TSB:ADPR:NRR , C:TSBhADPR:NRR !
NAME- DLJohnson'- FMRein' hart WDBeckner bd0 DATE 09/14/98 09/ M /98 09// I/98 9$ $ 'b . 1
M etoq p *, UNITED STATES p j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-0001 4
9***** September 15, 1998 MEMORANDUM TO: William D. Beckner, Chief Technical Specifications Branch Associate Director for Projects, NRR ,
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FROM: Deborah L. Johnson, Informati Management ssista t i Technical Specifications Branch l Associate Director for Projects, NRR ;
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SUBJECT:
FORTHCOMING MEETING WITH NEl TECHNICAL SPECIFICATIONS TASK FORCE l DATES & TIME: September 24,1995 9:00 a.m. to 4:00 p.m.
LOCATION: U. S. Nuclear Regulatory Commission l 11555 Rockville Pike One White Flint North Building l Room 0-6B11 l Rockville, MD 20852 l i
PURPOSE: To discuss proposed Standard Technical Specification changes.
PARTICIPANTS *: NRC INDUSTRY TSB Staff NEl TS Task Force HlCB Staff SCSB Staff EELB Staff S. Magruder, Project 689
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Attachments: 1. Meeting Agenda
- 2. Project 689 Addressee List I cc: (via e-mail) i J. Davis, NEl l D. Hoffman, EXCEL D. Williamson, WOG T. Weber, CEOG B. Ford, BWROG N. Clarkson, BWOG D. Wuokko, BWOG CONTACT: Debbie Johnson, NRR 301-415-3060
- Meetings between NRC technical staff and applicants or licensees are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to " Commission Policy Statement on Staff Meetings Open to the Public" 59 Federal Register 48340, 9/20/94.
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DISTRIBUTION FOR MEMORANDUM DATED: Sentember 15.1998 !
l Hard Cony E-Mailed Conies l ;
j flLE CENTER B. Boger, ADRP ,
l OPA TSB Staff PUBLIC J. Wermiel, HICB l ACRS (4) C. Berlinger, SCSB l
OGC J. Calvo, EELB PMNS T. Collins, SRXB >
Receptionist (OWFN)
TSB R/F ,
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AGENDA
! TSB/NEl TSTF Meeting i
September 24,1998 o Comments on Meeting Summary of April 22, .398 Meeting i
o Process improvement General Discussion (i.e., generic change process, ITS Bases usage & control, and electronic file transfer) ,
i o Discussion of Selected Travelers Response Time Testing, Channel Functional Testing, and RPS and ESFAS Instrumentation Ice Condensers (Issue Summary Attached) and BWR Secondary ;
Containment Doors ]
DC Electrical Systems and SRs that require a licensee to enter LCO 3.0.3 j L to perform Administrative Controls o Traveler Status of High, Medium and Low Priority Travelers l
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o Agenda for Future Meeting l
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Summary of l Ice Condenser Technical Specification issues .
Over the past several weeks, a numbers of issues have been raised relative to licensee compliance with technical specifications (TS). These TS involve ice condenser plants with TS '
similar to the Westinghouse improved Standard Technical Specifications (STS) 3.6.15 " Ice Bed".
These issues involved several different surveillarr s in this section and have highlighted problems literally complying with the TS, ambigu Fce a the requirements, and in at least one case a TS with no apparent relationship to the design basis.
SR 3.6.15.2 requires weighing a sample of ice baskets to ensure that "... each basket contain >
[1400] Ib ..." and calculating the total weight of ice at a 95% confidence limit. While it is obvious that calculating sufficient total weight of ice is required to pass the surveillance, use of the word "each" would also imply that any basket found less than the required weight of ice would also result in failure of the surveillance. However, the Bases would appear to contradict this interpretation of the TS by providing specific guidance on expanding the sample if baskets ,
without sufficient ice are found. Clearly the total weight of ice is the intent of the surveillance so !
why have an 6pparent requirement on the individual baskets which is then contradicted by the TS '
Bases. I l
SR 3.6.15.5 is a similar surveillance requirement to check that the boron concentration in the ice
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and pH are adequate. Unlike SR 3.6.15.2, the requirement does not seem to necessarily imply l that each basket must meet the appropriate limits, but then neither is there a requirement to l calculate the total or average concentration. Licensees have focused on ensuring that the average of all samples meet the limits by melting and mixing samples in the past. More recently, l individual samples have been analyzed separately and have resulted in some samples falling !
below the limit. It is not clear if an individual sample falling below the limit would result in fai'ure I of the surveillance or if the total or average values may be calculated in a manner used in the weight surveillance.
SR 3.6.15.5 also has a potential problem relative to the action statements if the surveillance is not met. If based on limited sampling it is determined that either the pH or boron concentrations ;
are not met, the plant is placed in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> action statement to either restore operability or shut down. However, a mom prudent path would be to perform additional testing, such as using an i expanded sample similar to the guidance contained in the Bases of SR 3.6.15.2 for the weight of i the ice, to better understand the overall characteristics of the ice bed.
SR 3.6.15.4 requires inspection of the flow channels to ensure that ice buildup is not restricting the channels. Either the TS or, in the case of the improved STS, the Bases, further define specific locations to be inspected which include the lower inlet plenum and tuming vanes.
Inspection of the lower plenum and tuming vanes is not possible during power operation and thus presents a problem since the frequency is 9 months in the improved STS. Inspection of ,
these same locations is also probably not necessary since these areas do not represent the minimum flow areas wh;ch would be most susceptible to blockage by ice buildup. Licensees ,
have avoided problems in the past by either modifying the frequency from the improved STS value to every 18 months or simply (incorrectly?) interpreting the TS to not require inspection of these inaccessible areas.
SR 3.6.15.4 requires verification of ice on structural members of < [0.38) inch. This value has nothing to do with the design basis of the plant. A uniform coating of this thickness would provide significantly more flow blockage than assumed in design hasis calculations while at the same time, isolated areas with grester than this thickness of ice mgy not provide excess flow blockage.
Attachmer,t
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NEl Project No. 689 September 15,1998 cc: Mr. Ralph E. Beedle, Senior Vice President and Chief Nuclear Officer Nuclear Generation Nuclear Energy institute Suite 400 ,
1776 i Street, NW '
Washington, DC 20006-3708 Ms. Lynnette Hendricks, Director Plant Support Nuclear Energy Institute Suite 400 1776 i Street, NW Washington, DC 20006 3708 r
Mr. James W. Davis, Director Operations Nuclear Energy l'nstitute Suite 400 1776 i Street, NW ,
Washington, DC 20006-3708 Mr. Nicholas J. Liparuto, Manager Nuclear Safety and Regulatory Activities Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, Pennsylvania 15230 )
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