ML19281A078

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Summary of 781201 Meeting in Bethesda,Md W/Westinghouse Re RESAR-414 Integrated Protection Sys Design Verification Program Status & Future Plans.W/Encl Proposed Documentation & Summary of R&D Info
ML19281A078
Person / Time
Site: 05000572
Issue date: 12/19/1978
From: Oreilly P
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 7903060083
Download: ML19281A078 (9)


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UNITED STATES

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CEO 1 i:. d Docket No STN 50-572 APPLICANT: WESTINGHOUSE ELECTRIC CORPORATION FACILITY:

RESAR-414

SUBJECT:

SUMMARY

OF MEETING HELD DECEMBER 1,1978 TO DISCUSS THE RESAR-414 INTEGRATED PROTECTION SYSTEM DESIGN VERIFICATION PROGRAM On December 1,1978, we met with representatives of the Westinghouse Electric Corporation (W) at NRC Headquarters in Bethesda, Maryland.

W requested the meeting in order to discuss with us the current status and future plans for the RESAR-414 Integrated Protection System (IPS)

Design Verification Program. A list of attendees is contained in Enclosure No. 1.

During its introductory remarks, W informed us that, instead of continuing work on the RESAR-414 design effort, it was pursuing prep-aration of an FDA application for the RESAR-412 design which would be tendered in July 1979. This RESAR-412 design would incorporate the same IPS contained in the RESAR-414 design.

It was agreed that further discussion of 'd licensing plans be postponed until the meeting scheduled in the afternoon with hRC regarding standardized designs.

W then described the method which it proposes to use to document the IPS design in the generic sense that will facilitate referencing by applicants in individual case reviews. Enclosure No. 2 contains this proposal. Briefly, this method would use the topical report approach.

The documentation would consist of three parts:

(1) the so-called "I&C" (instrumentation and controls) material normally contained in Chapter 7 of an SAR, (2) and (3) aapendices documenting the Design 2i Verification Program. These would be of two types - (i) tests and i

(ii) analyses.

W reported that the testing aspect of the design verification program Ts currently in progress. Some results should be available in early 1979. 'd then described plans under consideration for the preparation of a Systems Verification Manual. Since proprietary information will be involved, the mechanics of how the staff's review of the test results will be conducted must be worked out with this consideration.

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'le expressed concern about how the staff's canpower and resources situation might affect our review of the design verification program.

The ideal situation would be to have our review and evaluation com-pleted before any OL application incorporating the IPS design is submitted for review. Depending upon the staff's manpower require-ments, this may or may not be possible.

We then discussed the staff's requirements for validation and verifi-cation of IPS design which are being developed.

In view of the critical manpower problem, we proposed that further discussions in the form of meetings and telephone conmunications be held so that our review of the W verification program can begin. A meeting was tenta-tively scheduliiid for the period between December 15 and 21,1978. We requested that W examine our guidelines for validation and verification so that at the iiext meeting they can explain how the RESAR-414 IPS design verification program meets our objectives. This explanation should also indicate where, on the record, the documentation describing this conformance is located. We emphasized the importance of getting early resolution of any differences of opinion regarding conformance.

W provided us with a summary of the R&D matters mentioned in the RESAR-4'l4 Safety Evaluation Report along with their current status and future plans if pertinent to the RESAR-414 IPS verification program review.

This information is contained in Enclosure No. 3.

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(' \\ - A Patrick D. O'Reilly, Project Manager Standardization Branch Division of Project Management Office of Nuclear Reactor Regulation

Enclosures:

As stated r'r'

ENCLOSURE 1 December 1, 1978 10:00 A.M. Meeting RESAR-414 IPS DESIGN VERIFICATION PROGRAM ATTENDANCE LIST Name Affiliation Patrick D. O'Reilly NRC/DPM M. Srinivasan NRC/ICSB W. L. Luce

'g/ Licensing J. M. Gallagher W/ Engineering D. W. Call

'j/ Nuclear Safety D. H. Rawlins W/ Nuclear Safety B. G. Croley y/NuclearSafety R. M. Satterfield NRC-ICSB J. P. Joyce NRC-ICSB.

L. Beltracchi NRC-ICSB 2.- _7 -

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ErlCLOSURE 2 1112 FDA DOCUMENT (7/12/79)

INTEGRATED PROTECTION SYSTEM DOCUMENTATION CH.

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3YN IRC 10PICAL REPORI (FILE JULY /9)

SECTI0ft 1 SECTI0li 2 SECTIOri 3 CilAPTER 7 "I&C" DESIGil VERIFICATI0!!

DESIGil VERIFICATI0fi fMTERIAL PROGRAF 1 PROGRAM (TESTS)

(AtlALYSES) 4 %

EXISTIflG R.bk P

TOPICAL p.

REPORTS SUMMARIES OF DETAILED DATA DETAILE DATA MODULES TRAtlSMITTED TO MEflDMEtlTS I

flRC VIA SPECIAL C0ilTROLLED DISTRIBUTI0tl SYSILMS VERIFICAlloN ANALYSES

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MODULES TRAN5MITTED SOFTWARE

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QUARTER 1979 DESIGN VERIFICATION PROGRAM 3

-- TESTS --

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SYSTEMS PERFORMAtlCE SPECIFICATIONS SER + NUREG-0493 REQUIREMEllTS DETAILED TEST PROCEDURES (E.G., DIVERSITY REPORT, RELIABILITY TEST RESULTS STUDIES, UNCERTAltlTY STUDIES)

CONCLUSI0ilS I

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Ef1 CLOSURE 3

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TABLE NRC ITDfS RELATED TO I & C TOPICAL SECTION 2 AND 3 AND RECOMMENDATIONS FOR SAME PORT PACE

_ SUBJECT OR ITEM RECOMMENDATION 17 &

General statement on need for 414 IPS Design ble 1-3 Verification Program - To Be Completed 4Q/79.

Agree - item II in Table and statements on pg. 17 are consistent with Sec. 2 of I&C Topical.

Agree with date provided li & NRC have a coordinated schedule for key milestones.

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Items Requiring AdJ1tional Technical Information Item 22, Analysis and tests to demonstrate defense These two items are covered by I&C b

in depth principle of IPS, and 23, Demonstration of Topical Sections 2 and 3.

adequacy and reliability of the signal selector.

f Items 24, Automatic nower control system stability These two items related to the FDA and interactions, and 25, System verification test and. therefore, are included in I&C plan of plant computer and operator display Topical, Section 1.

information.

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Item 28, Justification of final instrument error, Agree that instrument errors and

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setpoints and delay times and control rod insertion delay times associated with IPS are

time, included in the DVP and are covered by Sec. 2 and 3 of I6C Topical.

Item 30, Consideration of Operator Action Tines Those operator action times necessary to claim credit for manual action on the diversity analysis for the IPS are part of DVP and will be included in Sec. 3 of I6C Topical.

Item 33. Anticipated transients without scram -

Do not agree that this is part of IPS this item makes reference to 15.4.7 pg. 15-19, DVP.

This analysis should be part of system reliability analysis to demonstrate effects the resolution given to the ATWT issue of IPS unreliability are consistent with which is outside scope of DVP. (Sec. 2 assumptions used in analysis for ATWS.

and 3 of I&C Topical).

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e TABLE (CON'T)

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REPORT PACE SUBJECT OR ITEM RECOMMENDATION

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Review of Topical Report identified by NRC as part l 19 &

Table 1-5 of Design Program WCAP 8587 Note 1 WCAP 8897 Integrated Bypass Logic Note 2 WCAP 8899 Signal Selector Device Note 2 WCAP 9153 IPS Verification Note 3 WCAP 9172 N-16 Flow Meas.

e tiote 4 WCAP 9190 N-16 Power Meas.

Note 2

..,fE 1: This is part of FDA, not part of DVP and will be Sec.1 of I&C Topical.

NOTE 2: Agree that this is part of DVP and will be covered in Sec. 2 & 3 of I&C Topical, however, approval of functional requirements in these topicals is needed prior to start of system testing. This approval should be included in detailed NRC Verification Program Schedule. Testing performed in Sec. 2 will be 1imited to prototype channel set.

Test results of N-16 detector vill be included in analysis given in Sec. 3.

NOTE 3:

Agree, this is essential to DVP.

We must reach agreement with NRC on modification of WCAP 9153 based on NRC V6V Program prior to 12/30/78.

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NOTE 4:

Do not agree that this is associated with IPS DVP.

Absolute flow is not an input constant for IPS.

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!t 1-24 Interface Criteria for IPS Agree based on note XXXX given in Table 7-1 of 414 SER.

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N TABLE (CON'T)

REPORT PAGE SUBJECT OR ITEM RECOMFIENDATION 4-19 WCAP 9105 - Measurement uncertainty only Agree that this is part of DVP and will be dovered in Sec. 3 of I&C Topical.

4-20 WCAP 9190 - N-16 Power Meas.

See comment on table 1-5 above.

4-28 "TilINC Equivalent" Method Do not agree that this is associated with IPS DVP 4~

4-33 WCAP 9172 - N-16 Flow Maas.

See comment on table 1-5 above.

7-10 Acknowledgement of W IPS DVP Agree - will be covered in Sec. 2 & 3 of I&C Topical.

7-13 Review and evaluation of design and performance Agree - will be covered by review of IPS and evaluation of Sec. 2 & 3 of I&C Topical.

7-13 Review and evaluation of design and performance Agree, provided that DVP coverage in of the protective action system, the interfaces Sec. 2 of I&C Topical will be established between the protective action system and the by secpe of prototype equipment as integrated protection system and the balance given in RESAR 414.

Equipment outside of plant interf aces will be part of DVP.

that scope will be covered by analysis under Sec. 3 of Topical.

7-?

Interface requirements for 414 Safety System See comment on pg. 1-24 above, will be identified as part of DVP.

7-16 Implementation details for error detection features Agree - this will be covered in will be further defined during DVP.

Sees. 2 & 3 of I&C Topical.

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TABLE (CON'T)

REPORT PACE SUBJECT OR ITEM RECOMMENDATION 7-16 Design Verification Program (Sec. 7.1.2.5)

Note 5 7-19, 21 & 21 7-21 Defense-in-Depth Evaluation (7.1.2.6)

Agree that DVP shall include analysis and testing identified in NUREG-0493 7-22 unless specific exception is stated by W.

Results will be presented in Sec. 2 and Sec. 3 of I&C Topical.

Exceptions will be dealt with on a case by case basis. However, in order to maintain W schedule agreement on modifications to WCAP 9153 to s

meet NRC V&V Program must be reached before 12/30/78.

h-25 Design and performance of reactor trip system Agree within scope established for design verification program as stated above.

7-27 Design and performance of Engineered Safety Agree within scope established for j;

Features System Actuation Functions DVP as stated above.

d NOTE 5: Agree based upon the following clarifications and positions:

(a) Results of failure modes and effects analysis and reliability analysis of system are limited to FMEA as needed to support test cases, to reliability analysis as needed to esteblish periodic test intervals.

The AWTS question is outside the scope of the DVP.

(b) RESAR-414 - the Design Verification Program does not include those systems presented in Section 7.7 with the I&C Topical, which constitutes the DVP report will be limited to the analysis and test required by the 414 SER and NUREG-0493. The functional requirements have been giver in the RESAR 414 and WCAP 8897, 8899 and 9190.

(c)

Equipment Qualification - this is limited to approval of test prograu input data sheets for equipment specific to IPS.

Does not include test results.

(d) As stated previously, WCAP 9172 N-16 Flow Measurement is not a part of verification program.

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TABLE (CON'T)

REPORT PAGE SUBJECT OR ITDI RECOM5fENDAT10N 7-30 Post Accident Monitoring System Agree - DVP will include data link to drive the post accident monitoring system but not the actual displays.

Test results will be included in Section 2 of I&C Topical.

Agree with the clarification that 7-30 Bypasa Indicator the II.C is part of the DVP.

The actual ESF systems will be covered in the FDA.

As stated the automatic bypass indication system is outside the scope of the IPS.

7-33 Signal Selector matters' identified in NUREG-0493 Agree that Signal Selector is included in DVP and will be addressed in Sec. 2 and Sec. 3 of I6C Topical.

Independence between protection and 7-39 Evaluation of Automatic Power Control System control system will be evaluated f'.

under DVP for IPS.

i,9 14-2 Initial test for IPS The results from the NRC study will be included in the FDA not in the I&C Topical.

1s-2 IPS Instrument Errors and Time Delays Agree based on recommendation given for Table 1-4 above.

16-1 Technical Specs. for IPS Agree this is not part of DVP.

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