ML20141C497

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Summary of 970609 Meeting W/W in Rockville,Md to Discuss Open Item Tracking Sys Issues Involving Instrumentation & Control Section of AP600 TSs Section 3.3.Highlights from Meeting & Summary of Results Listed
ML20141C497
Person / Time
Site: 05200003
Issue date: 06/23/1997
From: Huffman W
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
NUDOCS 9706250259
Download: ML20141C497 (6)


Text

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e ltrM f C Q e f Ma o p 4 UNITED STATES

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s* j NUCLEAR REGULATORY COMMISSION  ;

WASHINGTON, D.C. ma aaai I

June 23, 1997 l

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APPLICANT
Westinghouse Electric Corporation PROJECT: AP600 s

SUBJECT:

SUMMARY

OF MEETING TO DISCUSS AP600 OPEN ITEMS ASSOCIATED WITH THE j

INSTRUMENTATION AND CONTROL (I&C) TECHNICAL SPECIFICATIONS (TS) l l The subject meeting was held on June 9, 1997, in the Rockville, Maryland, l offices of Westinghouse Electric Corporation between representatives of Westinghouse and, the Nuclear Regulatory Commission (NRC) staff. The purpose '

of the meeting was to discuss open item tracking system (0ITS) issues involv-l ing the Instrumentation and Control section of the AP600 TSs (Section 3.3). '

Highlights from the meeting include the following items:

The AP600 technical specifications for reactor trip and engineered safety feature actuation system (ESFAS) instrumentation only requires three channels to be operable even though the AP600 design consists of four channels. Although indefinite operation with only three channels <

is acceptable, not specifying any required action in TS when the first of four channels fails or is declared inoperable is a concern to the NRC staff. To ensure that the I&C system logic (such as the global trip or trip enable subsystem) is not inadvertently compromised by lack of knowledge of the status of the fourth channel, the staff requested that the AP600 I&C TS be rewritten to require bypass of the fourth channel when inoperable. This channel could remain in the bypassed condition indefinitely without any further operational restrictions on the plant operator. The staff envisioned that Westinghouse would structure the TS to be similar to the I&C TS for CE System 80+. Westinghouse agreed to restructure the TS to address bypassing the fourth channel when inopera-bl e. The staff noted that Westinghouse should propose a reasonable time to place the channel into the bypass state (e.g., 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />). .

Westinghouse still disagrees with the staff on the need for a common cause software failure root cause analysis program in TS. The staff notes that such a program has already been agreed to by the evolutionary design vendors and there is nothing different about the Westinghouse I&C design that would exempt it from a similar program. Westinghouse agreed to take an action to provide additional justification for not including it in TS or to provide an equivalent alternate proposal to the staff.

The operability surveillance for squib valves consists of performing a

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sample charge test firing every two years per the inservice testing program. The staff, however, believes that some additional surveillance l should be available to demonstrate that the I&C system can actually fire i the valve (such as proof of continuity to the squib valve firing mechanism). Westinghouse agreed to take action to look at available alternatives.

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t June 23, 1997 e

The staff and Westinghouse went through the status of each OITS item. A summary of the results is listed below.

i OITS # ACTION STATUS UPDATE

, 2024 2454 ACT W Resolution of this item is tied to an expected West-inghouse submittal on disturbance analysis system availability administrative controls.

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2434 ACT W Westinghouse to reconsider the need for a common cause l software failure analysis program.  !

2436 l 2442 \

2443 ACT W Westinghouse to revise TS to reflect a four channel l design with indefinite bypass of the first channel l permitted.

l 2437 Resolved This item is considered resolved with Westinghouse restoring completion times and surveillance freque.i-cies consistent with the standard technical specifica-tion (STS).

2438 ACT W Westinghouse to add justification to TS basis to state that it is acceptable to place the first inoperable channel in bypass (per limiting condition for opera-tion required action statement) even if it has failed to the trip condition. t 2439 Resolved An adequate definition of a reactor trip channel is provided in the TS bases page B 3.3-6.

2440 ACT N The staff needs to inform Westinghouse if it has any problems with the current TS I&C related definitions.

2441 Resolved The definition of Automatic Trip Logic is addressed on TS bases page B 3.3-7.

2444 Resolved Pending confirmation in final TS revision.

2445 Resolved The staff agrees that TS currently addresses this issue.

2446 Resolved The definition of an engineered safety feature channel is addressed on TS bases page B 3.3-54.

June 23, 1997 2447 Resolved The staff notes that functional diversity is built into the design. However, Westinghouse does not take.

any credit for the functional diversity in the safety analysis. Westinghouse complies with the STS for completion times.

2448 Dropped The staff agreed that this item could be dropped. I 2449 Resolved Pending confirmation in final TS revision.

2450 Resolved The current version of TS adequately addresses this '

item.

' 1 2451 ACT W Westinghouse to determine if some on-line surveillance of squib valve operability is available. l 2452 Resolved The current version of TS adequately address this item.

t l 2453 Resolved Westinghouse noted that the TS bases will be corrected i

' to that VES/ Control Room isolation function will be applicable during fuel movement, j 2455 l 2456 ACT N Staff to determine if 7 day completion time for cor-

! recting two postaccident monitoring channels out of l service is acceptable.

-2457 Resolved The current version of TS adequately addresses this item.

2458 Resolved This item is considered resolved with Westinghouse l restoring completion times and surveillance frequen-cies consistent with the STS.

l 2459 2461 Resolved Westinghouse does not take credit for self-diagnostic I&C.

4 l 2460 ACT N Staff to datermine the acceptability of 24 month COT surveillance frequency.

2462 Resolved The current version of TS adequately addresses this item.

2463 ACT W Westinghouse to determine the appropriate title for the trip setpoint column headers in Tables 3.3-1 and 3.3-2. The staff recommends using " Allowable Value."

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l i June 23, 1997 i i I i

l. During the meeting, the staff made some editorial suggestions, including: 1 The applicable modes column of Tables 3.3-1 and 3.3-2 should include "or j other specified conditions."  !

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The required channels column of Table 3.3-1 and 3.3-2 should state l

" Required Channel / Devices" [Not Divisions]

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The conditions for ESFAS Table 3.3-2 should be combined as possible to l l eliminate use of double characters (e.g. DD) l

. Table 3.3-2 " Notes" should be provide at the bottom of each applicable page and not at the end of the section.

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! Attachment is the list of meeting attendees.

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A draft of this meeting summary was provided to Westinghouse to allow them the )

i opportunity to ensure that the representation of comments and discussion was  !

j accurate.  !

j original signed by: l t William C. Huffman, Project Manager l Standardization Project Directorate i Division of. Reactor Program Management 1

Office Of Nuclear Reactor Regulation 4 Docket No.52-003 1

Attachment:

As stated i

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DISTRIBUTION w/ attachment: I 1 Docket File PDST R/F TKenyon 1 i PUBLIC BHuffman DTJackson
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MReinhart, 0-13 H15 j i DOCUMENT NAME
A:TS-I&C. SUM .l

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i Westinghouse Electric Corporation Docket No.52-003 q

i cc: Mr. Nicholas J. Liparulo, Manager Mr. Frank A. Ross Nuclear Safety and Regulatory Analysis U.S. Department of Energy, NE-42 Nuclear and Advanced Technology Division Office of LWR Safety and Technology Westinghouse Electric Corporation 19901 Germantown Road P.O. Box 355 Germantown, MD 20874 Pittsburgh, PA 15230 Mr. Ronald Simard, Director Mr. B. A. McIntyre Advanced Reactor Program Advanced Plant Safety & Licensing Nuclear Energy Institute Westinghouse Electric Corporation 1776 Eye Street, N.W.

4 Energy Systems Business Unit Suite 300 i Box 355 Washington, DC 20006-3706 i Pittsburgh, PA 15230 Ms. Lynn Connor

, Ms. Cindy L. Haag Doc-Search Associates Advanced Plant Safety & Licensing ~ Post Office Box 34 Westinghouse Electric Corporation Cabin John, MD 20818 1 Energy Systems Business Unit Box 355 Mr. James E. Quinn, Projects Manager Pittsburgh, PA 15230 LMR and SBWR Programs GE Nuclear Energy Mr. M. D. Beaumont 175 Curtner Avenue, M/C 165 Nuclear and Advanced Technology Division San Jose, CA 95125 i Westinghouse Electric Corporation One Montrose Metro Mr. Robert H. Buchholz 11921 Rockville Pike GE Nuclear Energy Suite 350 175 Curtner Avenue, MC-781 Rockville, MD 20852 San Jose, CA 95125 Mr. Sterling Franks Barton Z. Cowan, Esq.

U.S. Department of Energy Eckert Seamans Cherin & Mellott NE-50 600 Grant Street 42nd Floor 19901 Germantown Road Pittsburgh, PA 15219 Germantown, MD 20874 Mr. Ed Rodwell, Manager Mr. S. M. Modro PWR Design Certification Nuclear Systems Analysis Technologies Electric Power Research Institute Lockheed Idaho Technologies Company 3412 Hillview Avenue Post Office Box 1625 Palo Alto, CA 94303 Idaho Falls, 10 83415 Mr. Charles Thompson, Nuclear Engineer AP600 Certification NE-50 19901 Germantown Road Germantown, MD 20874 l

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WESTINGHOUSE - NRC NEETING ON AP600 INSTRUNENTATION AND CONTROL TECHNICAL SPECIFICATIONS JUNE 9, 1997 NEETING ATTENDEES H6ME ORGANIZATION KEN DEUTSCH WESTINGHOUSE CHIP SUGGS WESTINGHOUSE ROBIN NYDES WESTINGHOUSE

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HULBERT LI NRC MATT CHIRAMAL NRC MARIO GARERI NRC

CARL SCHULTEN NRC

! ANGELA CHU NRC BILL HUFFMAN NRC 1

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