ML20246G088

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Summary of 890606-07 Meetings W/Bnl & C-E Re Concerns Resulting from NRC & BNL Review of Sys 80+ Baseline Pra. List of Meeting Attendees,Agenda & Viewslides Encl
ML20246G088
Person / Time
Site: 05000470
Issue date: 07/06/1989
From: Kenyon T
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
PROJECT-675A NUDOCS 8907140157
Download: ML20246G088 (71)
v • d • e


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  1. July 6, 1989 Project No.-675 APPLICHT: Combustion Engineering Inc.

FACILITY: CESSAR-DC System 80+

SUBJECT:

SUMMARY

OF MEETING TO DISCUSS STAFF COMMENTS ON THE SYSTEM 80 BASELINE PRA IN SUPPORT OF THE SYSTEM 80+

On June 6-7, 1989, representatives of the NRC, Brookhaven National Lab-(BNL) and Combustion Engineering met in Windsor, Connecticut to discuss concerns resulting from the staff's and BNL's review of.the System 80 baseline PRA.

The System 80 baseline .PRA will be modified to reflect system design enhance-ments proposed for the System 80+ standard design such as improvements in the electrical distribution system and in the component cooling water system.

Enclosure 1 is a list of meeting attendees. Enclosure 2 is the agenda followed during the meeting and the slides presented.

.The first part of the meeting was a presentation by CE on the System 80+ standard design. A presentation was then given on the status of the System 80+ PRA.and responses to NRC comments on the baseline PRA. CE has made design enhancements in the System 80+ standard design in response to previous comments by the NRC staff. Enclosure 3 provides a summary of the staff's and BNL's comments.

CE indicated they would respond to the staff's concerns discussed during this meeting and forwarded to them by letters dated December 15, 1988 and March 14,.

1989. CE indicated that the final PRA for the System 80+ will be made in three_submittals starting with the Fall of 1989 and ending in 1990.

In summary, the baseline PRA was generated from a generic B0P because the ap >l1 cant-didn't have sufficient detailed information during its development. Since tie '

scope of the System 80+ has bcen expanded to include the 80P portions of the plant, CE will upgrade the System 80+ PRA to reflect the final design details of the plant using fault tree analysis methodology. CE indicated that the PRA now reflects changes made in the electrical distribution systemsand in the component cooling water systems. Other upgrades'will be made as the design progresses.

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$$N47o PNV Thorras J. Kenyon, Project Manager Standardization and Non-Power l

Reactor Project Directorate Division of Reactor Projects - III, IV, V and Special Projects Enclor. ores:

As sitted CONTACT: 1 T. Kenyon, NRR/PDSNP 492-1120 ,

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UNITED STATES y' g NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 5 L'[

July 6, 1989 v  % . . . . . .o Project No. 675  :

APPLICANT: Combustion Engineering Inc.

FACILITY: CESSAR-DC System 80+

SUBJECT:

SUMMARY

OF MEETING TO DISCUSS STAFF COMPENTS ON THE SYSTEM 80 BASELINE PRA IN SUPPORT OF THE SYSTEM 80+

On June 6-7, 1989, representatives of the NRC, Brookhaven National Lab (BNL) and Combustion Engineering met in Windsor, Connecticut to discuss concerns resulting from the staff's and BNL's review of the System 80 baseline PRA.

The System 80 baseline PRA will be modified to reflect system design enhance-ments proposed for the System 80+ standard design such as improvements in the electrical distribution system and in the component cooling water system.

Enclosure 1 is a list of meeting attendees. Enclosure 2 is the agenda followed during the meeting and the slides presented.

The first part of the meeting was a presentation by CE on the System 80+ standard design. A presentation was then given on the status of the System 80+ PRA and responses to NRC coments on the baseline FRA. CE has mode design enhancements in the System 60+ standard design in response to previous coments by the NRC staff. Enclosure 2 provides a summary of the staff's and BNL's comments.

CE indicated they would respond to the staff's concerns discussed during this meeting and forwarded to them by letters dated December 15, 1988 and March 14, 1989. CE indicated that the final PRA for the System 80+ will be made in three submittals starting with the Fall of 1989 and ending in 1990.

In summary, the baseline PRA was generated from a generic B0P because the applicant didn't have sufficient detailed information during its development. Since the scope of the System 80+ has oeen expt,ded to include the B0P portions of the plant, CE will upgrade the System 804 PRA t, reflect the final design details of the plant using fault tree analysis mthodology. CE indicated that the PRA now reflects changes made in the electrical distribution system and in the component cooling water systems. Other upgrades will be made as the design progresses.

7-]} / a. ~

Tho, mas J. Kenyon, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects - III, IV, V and Special Projects

Enclosures:

As stated ,

CONTACT:

T. Kenyon, NRR/PDSNP 492-1120

_ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ 1

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Enclosure 1 ATTENDEES PRA MEET'!hG

_CESSAE'DC SYSTEM 80i June 6-7, 1989 Name Organization l

T. Kenyon NRC/NRR/DRSP.

S. Ritterbusch CE Licensing J. Ponninger HRC/NRR/DRSP E. Kennedy CE Licensing G. Davis CE Project Manager.

C. Bagual CE ALWR Project Office D. Finnicum CE PRA B. Jaquita CE PRA R. Turk CE ALWR Engineering Manager R. Matzie CE ALWR Director T.L. Chu BNL

~

B. Fitzpatrick BNL E. Che111ah NRC/RES l

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/- - we ENCLOSURE 2.

AGENDA MEETING WITH NRC STAFF ON S-80+ PRA JUNE 6 - 7. 1989 TUESDAY 9:30 INTRODUCTIONS S. RITTERBUSCH 9:45 OVERVIEW OF THE R. MATZIE SYSTEM 80+ DESIGN 10:45 STATUS OF PRA AND. D. FINNICUM RESPONSES TO NRC R. JAQUITH COMMENTS 12:00 LUNCH 1:00 PRA . . .

3:00

SUMMARY

OF SIR R. TURK DESIGN EDESDAY 9:00 PRA . . . ,

12:00 LUNCH 1:00 MEETING

SUMMARY

S. RITTERBUSCH AND REVIEW OF ACTION ITEMS u_-__- _ _- _

sJw ENCt0 SORE 2 o

MEETING WITH NRC-STAFF ON SYSTEM 80+ PRA I

suiE 6-7, 1989 a

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OVERVIEW 0F THE SYSTEM 80+ DESIGN i

R. A. MATZIE ALWR PROJECT OFFICE DIRECTOR jyjff i

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0 EPRI ALWR REQUIREMENTS DOCUMENT 0 C-E/ DUKE DESIRED IMPROVEMENTS 0 NRC SEVERE ACCIDENT POLICY &

STANDARDIZATION RULE O MODIFIED DESIGN SUBMITTED TO NRC, IN STAGES, FOR CERTIFICATION REVIEW 0 REVISED DESIGN CALLED SYSTEM 80 PLUS 0 REVISED -LICENSING DOCUMENT CALLED CESSAR-DC 1

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.1UPLEX 30+ DESIGN BASIS

?CR CISPLAY AND ALARM

1. REDUCE THE QUANTITY OF DATA THAT MUST BE MENTALLY PROCESSED BY AN OPERATOR, TO MINIMIZE "INFORMATION OVERLOAD':

a SIGNAL VALIDATION PRIOR TO DISPLAY O REDUCE DATA THROUGH PARAMETER CORRELATION PRIOR - TO DISPLAY

2. DISPLAY INFORMATION USING HIERARCHICAL PRESENTATION:

o PLANT LEVEL OVERVIEW INFORMATION ON IPS0 0 KEY SYSTEM PARAMETERS ON DISCRETE INDICATORS o THREE-LEVEL CRT DISPLAY PAGE HIERARCHY NUPLEX80+ I I l l SLIDE 127. DOC 24

3. REDUCE THE NUMBER OF ALARMS GENERATED TO MINIMIZE CPERATOR '"!FO.CF.ATICN CVERLOAD":

o CROSS-CHANNEL SIGNAL VALIDATION PRIOR TO ALARM GENERATION o ALARM LOGIC AND SETPOINTS CONTINGENT ON APPLICABl.E PLANT MODE

4. DISPLAY ALARM WITH DISTINCT VISUAL CUEING IN ACCORDANCE WITH PRIORITY OF OPERATOR RESPONSE:

O PRIORITY 1 - IlEEDIATE ACTION O PRIORITY 2 - PROMPT ACTION O PRIORITY 3 - CAUTION ~ o OPERATOR AID - STATUS INFORMATION 9 n SLIDE 127. DOC 25 i 1 .. l l

5. ALLOW AN OPERATOR TO USE THE DISPLAYS DURING  !

liCCIEENTS THAT UE '2ES CURING NOMAL OPERATION. O SEISMICALLY CUALIFIED INDICATORS CORRELATE l NORMALLY USED SENSORS TO PAMI SENSORS o SPDS IS INTEGRATED IN NORMAL CRT DISPLAY SYSTEMS

6. PROVIDE REDUNDANCY AND DIVERSITY IN INFORMATION PROCESSING AND DISPLAY.

O INFORMATION REQUIRED FOR OPERATION FOR 24 iiOURS WITHOUT DPS IS ALSO PROCESSED AND DISPLAYED BY , DIAS o TWO SYSTEM REDUNDANCY IS INVISIBLE TO OPERATORS THROUGH CONTINUOUS CROSS-CHECKING AND INTEGRATED OPERATOR INTERFACES o PRIORITY I AND 2 ALARMS ARE PROCESSED AND DISPLAYED BY TWO INDEPENDENT SYSTEMS yuptgygg+ 4 , e '9 i + C - CD y 'h y 0 t . . "J -- d O *$ 4 1 - - N C i 3 3 = - - y ~

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  • NO RECOVERY
    • ESTIMATED LYb11

3 ~ l SYSTEM 80+ PRA OVERALL CORE DAMAGE FREQUENCY INTERNAL EVENTS 1.75E-6 SEISMIC 7.9E-6 (ARSAP) TORNADO STRIKE 3.1E-7 (ARSAP) TOTAL 9.96E-6 I A g e I Q _ tDGla" --- J 1 ,4 - 4 g- . S - 5 W . g 8 - M E - G = g 8 u - 5 g R " - g e 2 5 i m g _ 0 w g a m = _E 5 a a E l 8 "

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1) When using the IPPAS 11 code for PRA, concern was expressed over whether IFIAS II was cepable of handling large fault trees.
2) CE was asked to submit two selected fault trees for one sequence for j auditing purposes.
3) The baseline PRA was generated from a generic BOP and didn't have sufficient detailed information. CE indicated that the System 80+ PRA would include design details of the plant including the BOP.
4) What are the special features that allow CE to meet the proposed safety goal of 25 rem beyond a one-half mile radius following a large release of radiation due to core melt?
5) CE should ensure that all potential problems and event sequences caused by the addition of new features have been addressed to ensure that new

! problem have not been introduced by such features. ~

6) CE should justify the use of the IRRAS 11 code and address the potential for non-conservative results.
7) How did CE model the comon mode failures? Please provide additional documentation.

l 8) CE should include maintenance unavailability estimates. The PRA should provide some unavailability estimates for the most adverse train.

9) Since the Technical Specifications for the System 80+ are to be based on reliability assumptions, CE should ensure the assumptions used for developing the PRA and the Technical Specifications are the same.
10) Provide documentation on how each initiating event affects plant systems and response.
11) The frequency of the loss of offsite power seems low. CE should make use l of site parameters.

i 12) Discuss any dependency of the actuation signals in the reactor protection system.

13) Discuss the impacts of single steam generator tube rupture verse multiple steem generator tube ruptures.
14) In the steam generetor tube rupture event tree, CE should modify this event tree to account for ATWS sequence.
15) The NRC staff indicated that CE could request a copy of the risk codes currently used by the staff.
16) CE should provide an electrical power system distribution list including various electrical loads connected to the 125V and 4180V buses.

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