ML20132A850

Requests Addl Info to Complete Review of Certain Draft Safety Evaluation Rept Open Item & Forwards RAI 410.300 & Staff Evaluations of Certian OIs

ML20132A850
Person / Time
Site:	05200003
Issue date:	12/09/1996
From:	Diane Jackson NRC (Affiliation Not Assigned)
To:	Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
FACA, NUDOCS 9612160358
Download: ML20132A850 (158)

Text

{{#Wiki_filter:; December 9, 1996 l Mr. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory Activities Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, Pennsylvania 15230

SUBJECT:

STAFF UPDATE TO CERTAIN DRAFT SAFETY EVALUATION REPORT (DSER) OPEN ITEMS (0Is) AND REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING THE WESTINGHOUSE AP600 ADVANCED REACTOR DESIGN

Dear Mr. Liparulo:

As a result of recent efforts by the Nuclear Regulatory Commission staff, the i l status of several DSER Ols has changed and additional information needed to l complete the review has been identified. Enclosed is a RAI, designated as ) RAI# 410.300, and the staff's evaluations of certain OIs. Please update the open item tracking system database to reflect this informa-tion. If you have any questions regarding this matter, you can contact me at (301) 415-8548. Sincerely, original signed by: Diane T. Jackson, Project Manager Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No. 52-003

Enclosure:

As stated G NRC Hl.E CENIER COPY e DISTRIBUTION: ! Docket. File PDST R/F TMartin PUBLIC DHatthews TRQuay TKenyon BHuffman JSebrosky p' DJackson JMoore, 0-15 B18 WDean, 0-17 G21 5 ACRS (11) MPSiemien, 0-15 B18 GBagchi, 0-7 HIS JLyons, 0-8 D1 Cli, 0-8 D1 JBrammer, 0-7 H15 \\ TCheng, 0-7 H15 Shou, 0-7 HIS NSaltos, 0-10 E4 1 MPohida, 0-10 E4 JBongarra, 0-9 H15 g DOCUMENT NAME: A:UPDA-0ITS.DEC I T2,eeelve a copy of this document, buscate in the bos: 'C' = Copy without attachnient/encio.ure "E" = Copy with attachinent/ enclosure "N* = No copy 0FFICE PM:PDST:DRPM_./ D:PDST:DRPM l NAME DJackson:sg lA TRQuay n J4 DATE 12/4/96 (T 12/q f96#M" ~ s0FFICIAL RECORD COPY 9612160358 961209 PDR ADOCK 05200003 A PDR

O t-Mr. Nicholas J. Liparulo Docket No. 52-003 Westinghouse Electric Corporation AP600 cc: Mr. B. A. McIntyre Mr. Ronald Simard, Director Advanced Plant Safety & Licensing Advanced Reactor Programs Westinghouse Electric Corporation Nuclear Energy Institute Energy Systems Business Unit 1776 Eye Street, N.W. P.O. Box 355 Suite 300 Pittsburgh, PA 15230 Washington, DC 20006-3706 Mr. John C. Butler Ms. Lynn Connor Advanced Plant Safety & Licensing Doc-Search Associates Westinghouse Electric Corporation Post Office Box 34 Energy Systems Business Unit Cabin John, MD 20818 Box 355 Pittsburgh, PA 15230 Mr. James E. Quinn, Projects Manager LMR and SBWR Programs Mr. M. D. Beaumont GE Nuclear Energy Nuclear and Advanced Technology Division 175 Curtner Avenue, M/C 165 Westinghouse Electric Corporation San Jose, CA 95125 l One Montrose Metro 11921 Rockville Pike Mr. Robert H. Buchholz Suite 350 GE Nuclear Energy Rockville, MD 20852 175 Curtner Avenue, MC-781 l San Jose, CA 95125 Mr. Sterling Franks U.S. Department of Energy Barton Z. Cowan, Esq. NE-50 Eckert Seamans Cherin & Mellott 19901 Germantown Road 600 Grant Street 42nd Floor Germantown, MD 20874 Pittsburgh, PA 15219 Mr. S. M. Modro Mr. Ed Rodwell, Manager Nuclear Systems Analysis Technologies PWR Design Certification Lockheed Idaho Technologies Company Electric Power Research Institute Post Office Box 1625 3412 Hillview Avenue Idaho Falls, ID 83415 Palo Alto, CA 94303 Mr. Frank A. Ross Mr. Charles Thompson, Nuclear Engineer U.S. Department of Energy, NE-42 AP600 Certification Office of LWR Safety and Technology NE-50 19901 Germantown Road 19901 Germantown Road Germantown, MD 20874 Germantown, MD 20874 l i I l l

e a i STATUS OF CERTAIN OPEN ITEMS l RAlf 410.300 - SPLB - SSAR 9.4.2 In SSAR 9.4.2.2.1.4, Westinghouse needs to clarify if high or low efficiency filters are used and provide justification for use. SSAR 2.5.4 OITS# 556 Action W - Westinghouse will identify SSAR reference to AP600 safety-related facilities. I OITS# 1870 Resolved l OITS# 3483 W Confirmatory - Response is acceptable. SSAR revision is needed. j SSAR 3.9.6 OITS# 805 Action W i OITS# 810 Action W OITS# 811 Action W l OITS# 1736 Action W OITS# 1740 Action W OITS# 1753 Action W OITS# 2066 Action W - see #1716 OITS# 2071 Closed OITS# 2072 Closed OITS# 2073 Closed i SSAR 5 OITS# 934 Resolved OITS# 1892 Resolved OITS# 1893 Resolved SSAR 9.5.1 - From November 19, 1996, meeting OITS# 308 Action N/W l OITS# 309 Action W OITS# 314 Action W OITS# 323 Action W DSER 21 OITS# 28 Resolved OITS# 29 Resolved On November 5, 1996, a telephone conference was held to discuss open items in SSAR 9.3.1; 9.3.5; and 9.5.4 OITS# 237 Resolved OITS# 239 Action W - Return text to SSAR from RAI# 410.154c regarding instrument air being 100% per train and no high pressure air. OITS# 243 Action W - Westinghouse will clarify SSAR 9.3.2.2.1 on p. 9.3-7 i second paragraph, first sentence and revise figures in Chapter 10 to show air supply to valves. 1 OITS# 244 Action W - Revise SSAR 9.3.1.4 to reflex pre-operational testing for a sudden loss and gradual reduction in instrument air. Enclosure 9 h e ^

= _. - - e J OITS# 1094 Action N OITS# 2815 Action W - revise SSAR to show drain valve on air receiver makeup in Figure 9.3.1-1; revise SSAR to reflect connect non-compatibili-ty; revise SSAR to add purity specification for instrument air in Table 9.3.1-2. OITS# 253 Action W - revise SSAR to show sumps and inputs into sumps. 4 OITS# 250 Action N OITS# 1099 Action N OITS# 254 Resolved OITS# 255 Resolved 4 OITS# 326 Resolved 0!TS# 327 Resolved i LifS# 330 Action W - Revise COL action item to address minimum requirements for diesel generator fuel / follow manufacturer recommendations. i OITS# 333 Action W i OITS# 335 Action W - Investigate need to add filter / review SSAR Figure 9.5.4-1 sheet 3 of 3 for correct figure. OITS# 337 Resolved OITS# 338 Action W - Return Table 8.3.1-1 and 9.5.4-2 OITS# 340 Action W - Westinghouse will investigate replacement standard for OEMA OITS# 341 Action W - Verify diesel generator subsystems are Class D and add j to Table 3.2-3 OITS# 342 Action W - Include from 12/13/94 meeting summary items a,b, and d j regarding DG cooling water system. OITS# 344 Action W - Revise SSAR 8.3.1.2.1 to meet manufacturer's design specifications OITS# 346 Action N OITS# 348 Action W - Revise SSAR 8.3 to meet manufacturer's design specifi-l cations OITS# 350 Action W - Revise SSAR 8.3 to meet manufacturer's design specifi-1 cations 4 OITS# 357 Action W - Revise SSAR 8.3 to meet manufacturer's design specifi-cations OITS# 1127 Action N OITS# 1128 Action N OITS# 1130 Action N OITS# 1129 Action W OITS# 1131 Action W OITS# 1132 Action W OITS# 1923 Action N OITS# 1924 Action N l 2

4 On November 21, 1996, a telephone conference / meeting was held to discuss open items in SSAR 11 and SSAR 9.2. NRC: Chang Li, Jin Guo, and Diane Jackson Westinghouse: Jim Winters (at NRC) and Gordan Israelson (on telephone) OITS #1171 Resolved - Acceptable response in 10/17/96 letter OITS #1192 Resolved - Acceptable response in 10/17/96 letter 11.1-4 Resolved - Acceptable response in 10/17/96 letter 11.1-5 Resolved - Acceptable response in 10/17/96 letter OITS #1189 Action N OITS #1194 Confirmatory-W - Acceptable response pending SSAR revision OITS #1195 Action W - SWS must have a continuous monitoring OITS #1197 Action W - Westinghouse will investigate adding standard review plan nomenclature to SSAR. Westinghouse will fix system identifi-cation error (SWS, not SES) in Table 9.3.3-2 #23. OITS #1199 Resolved OITS #3097 Action W - Westinghouse will add to SSAR Table 9.2.10-1: 1) heat exchanger capacity, 2) piping design and pressure, and 3) heating requirements. OITS #3099 Resolved OITS #3122 Action W - Westinghouse will investigate wording to SSAR to reflect that startup feedwater is a defense-in-depth system. OITS #3102 Action N Action Westinghouse - Provide a copy of legible P&I0s for all AP600 systems. d i n 3 L i i i

e n I i l On November 26, 1996, a telephone conference was held to discuss open items in l SSAR Section 3.7 and 3.8. l NRC: Tom Cheng and Diane Jackson l Westinghouse: Richard Orr and Don Lindgren l \\ OITS #621 Resolved - This item is administratively resolved. The resolution of the issue is tracked under OITS #3728. OITS #623 Action W - Westinghouse needs to review staff report l OITS #628 Action N/W - Further discussion is needed. l OITS #636 Resolved - Staff accepted SSAR 3.7.2.3.2 revision rogarding the weir frequencies. l OITS #640 Resolved - Staff accepted SSAR 3.7.2.3.2 revision regarding the j weir frequencies. j OITS #649 Action W - Staff will review SASSI 20 analysis in 12/96 meeting. l l Issue on the potential pounding between structures is resolved by Westinghouse letter dated 10/27/96. OITS #659 Resolved i OITS #660 Action N 1 OITS #661 Action N OITS #662 Action W - Telecon needed with staff OITS #663 Confirmatory Westinghouse - Acceptable response in Westinghouse letter date 10/27/96. Formal SSAR revision is needed. OITS #664 Action W - Westinghouse Seismic Margins Analysis in prog.ess OITS #668 Action W OITS #672 Action N OITS #686 Resolved l OITS #717 Action W - Response to staff letter OITS #720 Action N OITS #742 Resolved - Open issue to be resolved under SSAR 3.8.5-2 and 3.8.4.2-4 OITS #752 Resolved Oils #1889 Resolved OITS #3376 Resolved 1 l l I l l 4

l 1 STATUS OF ECGB DSER OPEN ITEMS IN EMEB SCOPE OF REVIEW (THROUGH REV. 9) l The status of these items were sent via facsimile on 11/25/96 to facilitate discussion. l 1. Open Item 3.2.1-1 (OITS 562) - Appendix B for Seismic Category II Action W The HQM8 RAls relative to the response in the letter from McIntyre to Quay dated October 14, 1996 should be sent to Westinghouse and discussed during the l December 5 and 6, 1996 meeting. l l 2. Open Item 3.2.1-2 (OITS 563) - Appendix B for fuel storage racks Action W L Same coment as that for Open Item 3.2.1-1. 3. Open Iten 3.2.2-1 (OITS 564) - Classification of ECCS l Action W l l In a letter to Westinghause dated August 20, 1996, this open item was reported l by the staff as being resolved. However, before this issue is considered l resolved, the staff needs the following information and/or clarifications from l Westinghouse: a. The staff has identified the components and systems listed below as part of ECCS systems that are classified as AP600 Class C (ASME i Class 3): e In-containment refueling water storage tank (SSAR Fig. 6.3-2)

• Accumulator (SSAR Fig. 6.3-1) l l
• Accumulator injection piping to discharge check valve V-028 (SSAR l

Fig. (6.3-1) e Containment recirculating piping and valves to IRWST injection l check valve V-122 (SSAR Fig. 6.3-1) Piping from 1st, 2nd & 3rd stage ADVs to IRWST, including e depressurization spargers (SSAR Fig. 5.1-5 & 6.3-2) l i j Westinghouse is requested to verify in the SSAR, Subsection 3.2.2.5, that l all of the above components and systems and any other Class 3 ECCS not j listed above are included in the comitment to random radiography for all l ECCS. 5 i (

e o i b. It appears that SSAR Subsection 3.2.2.5 is the only place in the SSAR that contains the above commitment. Since this comitment is not stated in either Table 3.2-3 or applicable P& ids, how can the staff be assured that it will be implemented on all AP600 plants? This issue will be discussed during the December 5 & 6, 1996 meeting. 4. RAI 210.216 (OITS 3506) - Main Control Room Habitability System Tanks Resolved 5. RAI 210.217 (0ITS 3507) - Table 3.2-3, Sheet 1, Compressed and Instr. Air System No Westinghotse response as of 11/20/96. ] 6. RAI 210.218 (OITS 3508) - Table 3.2-3, Sheet 4, Demineralizea Water Transfer & Storage System No Westinghouse response as of 11/20/96. 7. RAI 210.219 (0ITS 3509) - Table 3.2-3, Sheet 6, Passive Containment i Cooling System No Westinghouse response as of 11/20/96. 8. RAI 210.220 (OITS 3510) - Table 3.2-3, Sheet 7, Primary Sampling System No Westinghouse response as of 11/20/96. 9. RAI 210.221 (OITS 3512)- Table 3.2-3, Sheet 29, Reactor System No Westinghouse response as of 11/20/96.

10. RAI 210.222 (0ITS 3513) - Table 3.2-3, Sheet 39, Steam Generator System No Westinghouse response as of 11/20/96.

11. RAI 210.223 (0ITS 3514) - Table 3.2-3, Sheet 48, Central Chilled Water System No Westinghouse response as of 11/20/96.

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12. RAI 210.224 (OITS 3515) - Table 3.2-3, Sheets 49 & 50 - Liquid Radwaste System No Westinghouse response as of 11/20/96.

13. Open Item 3.6.2-1 (0ITS 592) - Subcompartment Design Action W The response to this issue in the letter from McIntyre to Quay dated Octo-ber 23, 1996 does not appear to contain the detailed information requested by the staff during the review meeting with Westinghouse on July 25 & 26, 1995.

As stated in the DSER, Section 3.6.2, page 3-94, the staff's position is that a minimum subcompartment pressure which bounds the effects of a high energy pipe break (with consideration of leak-before-break (LBB)ll subcompartments acceptance) must be determined. Specifically, the staff requests that for a l both inside and outside containment, SSAR Subsections 3.8.3.5 and 3.8.4.3.1.4 should be revised to state that those compartments containing high energy piping are designed to the worst case of either the 5 psi load (the 7.5 psi load for the CVS room) or the double ended pipe rupture of the applicable high energy pipe. This issue should be discussed with Westinghouse during the meeting scheduled for January 1997.

14. RAI 210.225 (OITS 3516) - Table 3.6-2, Subcompartments and Postulated Pipe Ruptures If necessary, this issue will be discussed during the January 1997 meeting.

15. RAI 210.40 (OITS 3702) - Break Exclusion in Steam Generator Blowdown and i

Startup Feedwater Lines Action W l In a letter from McIntyre to Quay dated October 23, 1996, and in the OITS 3702 report, Westinghouse stated that additional information on the startup feedwater (FW) line, including the isometric drawings will be provided during a forthcoming meeting with the staff. This issue will be discussed during the January 1997 meeting.

16. Open Item 3.6.2.3-1 (OITS 595) - Break Locations and Stress Summary Action W In a letter from McIntyre to Quay dated November 11, 1996, Westinghouse proposed a significant revision to SSAR Subsection 3.6.2.5 to provide addi-tional information on the pipe break hazard analysis. The staff's preliminary evaluation of this submittal resulted in the following request:

As discussed under Open Item 3.6.2.3-5 below, Westinghouse has proposed a revision to SSAR Subsection 3.6.1.3.2 which refers to the pipe rupture P j 7 l l

=. l hazards analysis. In addition to the proposed revision to SSAR Subsec-tion 3.6.2.5 in the November 11,.1996 letter, add a reference to the proposed information in Subsection 3.6.1.3.2 that is applicable to the hazards analysis. If the staff has any further questions related to this submittal, they will be discussed during the January 1997 meeting.

17. Open Item 3.6.2.3-2 (OITS 596) - Environmental Qualification Resolved

18. Open Item 3.6.2.3-5 (OITS 599) - Separating Structures Action W In a letter from McIntyre to Quay dated November 11, 1996, Westinghouse proposed a revision to SSAR Subsection 3.6.1.3.2 which provides a basis for resolving this issue as a part of the pipe rupture hazards analysis. Based on a preliminary review of this submittal, the staff has no further requests for information except to repeat the request in this open item to delete the exception to SRP Section 3.6.2 BTP MEB 3-1, Section B.I.c.(4) in WCAP 13054, Revision 2.

However, subsequent to a more detailed review, this issue may have to be discussed during the January 1997 meeting.

19. Open Item 3.9.2.1-1 (OITS 780) - Scope of Preoperational Piping Tests l

Resolved i In a letter from McIntyre to Quay dated October 23, 1996, Westinghouse submitted a response to this open item which states that the only systems that meet the criteria in SSAR Subsection 3.9.2.1 are the control room habitability system (VES) and the hot water heating system (VYS). The VES is not subjected to vibration due to low flow rates, and the VYS is not a safety-related system. Therefore, neither of these systems is applicable to the Chapter 14 " Initial Test Program." The staff has concluded that, based on this response, these systems need not be in the initial test program. Therefore, this issue is resolved.

20. Open Item 3.9.3.1-5 (0ITS 790) - ISLOCA Criteria i

Action N SSAR Revision 7 added a new paragraph in Subsection 1.9.5.1 which references SSAR Subsection 5.4.7 for design features which are applicable to the intersystem LOCA for the normal RHR system (RNS) only. The design criteria in SSAR Subsection 5.4.7.2.2 agrees with the staff's position on this issue which is discussed in the DSER, Section 3.9.3, and is acceptable for the RNS. However, as mentioned in DSER Section 3.9.3, if the staff's evaluation of DSER i Open Item 20.3-14 (OITS 1514) results in additional AP600 systems being applicable to the intersystem LOCA issue, the staff's position will be that j this same criteria should apply to those systems. In addition, the staff's 8

s preliminary review of the AP600 Technical Specifications may result in a concern relative to the deletion of leak testing of RCS pressure isolation valves, which is related to the intersystem LOCA issue. Therefore, this issue may have to be discussed during the December 5 & 6 meeting.

21. Open Item 3.9.3.1-6 (OITS 791) - HVAC Ductwork Design Criteria Action N This issue is included as a part of the staff's review of SSAR Section 3.8.

l

22. Open Item 3.9.3.3-1 (0!TS 792) - Snubber Criteria W-Confirmatory In a letter from McIntyre to Quay dated October 23, 1996, Westinghouse proposed a revision to SSAR Subsection 3.9.3.4.3 to add a commitment to l

include dynamic testing as a part of the qualification tests for snubbers. This agrees with the staff's request, and is acceptable. Therefore, this item is resolved pending formal revision of the SSAR.

23. Open Item 3.9.3.3-2 (OITS 793) - Anchor Bolts for Pipe Supports Action W In a letter from McIntyre to Quay dated October 23, 1996, Westinghouse responded to this item by referencing Revision 9 to SSAR Subsection 3.9.3.4.

Revision 9 contains no change to this portion of Subsection 3.9.3.4. It still commits only to the baseplate flexibility requirements of IE Bulletin 79 and is silent on the factors of safety for concrete expansion anchor bolts. Since the factor of safety issue is being evaluated by the staff under DSER Open Item 3.6.4.2-2, Subsection 3.9.3.4 should contain a reference to the applicable portion of SSAR Subsection 3.8.4 for information relative to these factors of safety.

24. Open Item 3.10-1 (OITS 813) - Use of Seismic Experience Data Action W In a letter from McIntyre to Quay dated October 14, 1996, Westinghouse proposed a revision to SSAR Section 3.10.6 which states that the COL appli-cant, as a part of the Combined License application, will identify equipment qualified based on experience and include details of the methodology and the corresponding experience data. This agrees with the staff's request on this item, and is acceptable. However, the exception to SRP 3.10 in Revision 2 to WCAP 13054 contains statements which either need to be deleted or clarified.

The first two sentences imply that IEEE 344-1987 is acceptable relative to the use of experience data. RG 1.100, Revision 2 states that this method of qualification in IEEE 344-1987 will be evaluated by the staff on a case-by-case basis. It appears to the staff that the exception in the WCAP is relative to RG 1.100, Revision 2. These two sentences should be revised to reflect the position in RG 1.100, Rev. 2. In addition, the discussion 9

relative to Generic Issue A-46 is not applicable to new plants. The staff's position is that A-46 is only used for verification of equipment in operating i plants, and is not acceptable for qualification of equipment in ALWRs. This discussion should either be deleted or revised.

25. Open Item 3.10-2 (OITS 814) - Dynamic Analysis of Valve Disks Action W In a letter from McIntyre to Quay dated October 14, 1996, Westinghouse responded to this item by proposing a revision to the fourth paragraph of SSAR, Subsection 3.10.2.2 to state that feedwater line valve disks are evaluated.for the effect of dynamic loads of pipe breaks by considering the effect of an equivalent differential pressure. This does not appear to address the staff's concerns. The staff considers equivalent differential pressure as being a static load. The SSAR should be revised to describe the methodology used in the AP600 design to analyze the dynamic closure of feedwater line valve disks when they are subjected to dynamic loads due to a pipe break.

26. Open Item'3.10-3 (OITS 815) - RCPB Valve Leakage per SRP 3.10 Resolved Revision 5 to the SSAR revised Subsection 3.10.2.2 to provide an acceptable response to this item.

In addition, WCAP 13054, Revision 2 revised page 3-68 to provide an acceptable comment. Therefore, this item is resolved.

27. Open Item 3.10-4 (OITS 816) -Aging by Analysis Resolved Revision 5 to the SSAR revised Appendix 3D to commit to the staff's position to use IEEE 323-1974 rather than the~1983 Edition. Revision 2 of WCAP 13054 revised the " exception" to SRP 3.10.II.l.c to " acceptable." Therefore. this item is resolved.

Open Item Status on 11/21/96 In AP600 Piping Design The status of these items were sent via facsimile on 11/25/96 to facilitate discussion. A. Items remaining open: l e Modeling uncertainties: Status: Action W/N l l DSER 3.12.3-1 (OITS #822) Item 2.b -- Needs discussion in 12/5/96 meeting on M response in 11/11/96 letter. l 10

.=..-... - { 6 r ~ e Piping functional capability: Status: Action W/N DSER 3.12.5.3-1 (OITS #832) Item 5 -- Needs discussion in 12/5/96 meeting on M response in 10/28/96 letter. DSER 3.12.5.12-1 (OITS #838) Pending resolution of OITS# 832.5 above. DSER 3.12.5.19-7 (OITS #847) Pending resolution of OITS# 832.5 above. e Thermal stratification Status: Action N l DSER 3.12.5.9-1 (OITS #836) NRC is evaluating EPRI report and will audit M calculations in GW-PLC-001. l DSER 3.12.5.10-1 (OITS #837) NRC is evaluating EPRI report and will audit W calculations in GW-PLC-001, o Composit damping: Status: W-Confirmatory (W 10/28/96 letter is acceptable. Await SSAR revision.) DSER 3.12.5.3-2 (0ITS #833) DSER 3.12.5.16-1 (0ITS #839) e Large snubber dynamic testing: Status: W-Confirmatory (W 10/23/96 letter is acceptable. Await SSAR revision.) DSER 3.12.6-1 (0ITS #848) 8. Items resolved per recent H responses: l DSER 3.12.4.2-1 (OITS #827) DSER 3.12.4.3-1 (OITS #828) DSER 3.12.4.4-1 (OITS #830) DSER 3.12.5.19-2 (OITS #842) DSER 3.12.5.19-5 (OITS #845) DSER 3.12.6.3-1 (OITS #850) DSER CN 3.12.3.6-1 (0ITS #1812) DSER CN 3.12.5.5-1 (OITS #1814) l f { 11 I l i

--_e w .A._. h ( l I l OPEN ITEM STATUS Part I i For facilitating resolutions in 12/4-6 meeting, the following is our evaluation of W letter I (NSD-NRC-96-4841) dated 10/14/96, which contains W response to certain AP600 open items related to reactor internals flow-induced vibration assessment, CRDM qualification for seismic and LOCA events, incore neutron thimble tube wearing issue, and reactor vessel upper head package deflection limits.

21. Open item 3.9.2.3-2 (783)- Flow-induced vibration prediction analysis Action W The W letter proposed a revision of the first paragraph in SSAR subsection 3.9.2.3 to indicate that the flow-induced vibration assessment is documented in WCAP-14761, which is also to be included i

to the reference list in SSAR section 3.9.9. This is acceptable. The staff has received WCAP-14761 as a replacement of previously reviewed report M101-GER 001. WCAP-14761 is acceptable. However, the fourth sentence in the revised paragraph states that *In the following discussion the term ' reference plant

• is equivalent to the term prototype
• should be deleted and replaced by
• Reactor internals of the first AP600 plant is designated as the prototype as defined in SRP 3.9.2 and RG 1.20 for vibration assessment of AP600 reactor internals." Information of vibration l

assessment from reference plants, which include H. B. Robinson, Doel 3 and 4, etc. may only be used in vibration prediction analysis for the prototype and should not be confused with the l prototype, in addition, the third and fourth paragraphs in SSAR subsection 3.9.2.4 should also be revised to avoid similar confusion between the " prototype" and the " reference plants" l L

22. Open item 3.9.2.4-1 (785)- Japanese CRDM seismic input tests - RAI 210.94 i

Action W i i The W letter indicated that operability of CRDM is assured by analytically establishing bending limits and validated in several testing programs. For ensuring structural integrity, the bending limits had considered conformance to ASME Code allowables under various load combinations, including seismic and other dynamic events. Functional capability is assured that the CRDM housing will not bind the drive rods during insertion under limiting bending condition. Westinghouse also proposed to add a new paragraph to SSAR subsection 3.9.4.3. l The W response appears reasonable. However, the staff is not clear what testing programs were performed and why the mentioned tests were not included in the proposed SSAR revision. Show l l documents to verify operability and design adequacy of the CRDM in AP600. If the information is l not AP600 specific, explain why the test and analysis results are bounding. In addition, we need better understanding on limiting seismic and pipe break loads used, and the basis why operability of CRDMs need not be verifel during the SSE event. i i

30. New Item - 20% damping value for fuel assemblies Action W The W letter did not address this item.

31. New item Potential thinning of incore neutron monitoring thimble tubes

6 Resolved l The W letter indicated that the AP600 incore thimble is an improved design which uses better wear resistant material, has larger diameter, is stiffer, and has smaller gap between thimble and guide tube. All these features results in minimized vibration, in addition, the double-wall design feature l will prevent non-isolable leak of reactor coolant, and preclude the need for inservice inspection. W i also proposed a revision of the final paragraph in SSAR subsection 3.9.7.2. We found that the response and the proposed SSAR revision is acceptable. This item is resolved pending formal SSAR revision.

32. Open item 3.9.71 (812) - Deflection limits for integrated head package -

RAI 210.97 Action W The W letter indicated that the deflection limit for the integrated head package is based on limiting the deflection of the CRDM. Westinghouse further indicated that whether 4" or 6' pipe break resulting from on going staff review in LBB is inconsequential to CRDM design due to more limiting LOCA loads being postulated. No clarification of the LOCA loads was provided. Thus item 3.9.7-1 remains open pending resolution of Open items 3.9.2.4 1, 3.6.3.4-1 and 3.6.3.6 4, and staff review and discussion of related information. l l i l l l 4

v AP600 Open Item Tracking Systeni Detsh se: Executive Senmcry Date: 11/21/96 Selection: [DSER Section] like *19? And [NRC Branch] like NRR/SPSlY Sorted by Item 8 i Item DSER Sectum/ Title.T)escnpeian (W) NRC No. Branch Question Tye Status Detail Imt kled Date Reap Eng staann Status I.,eer No. I tar Dese 69 NRR/SPSB 19 l RAICI t/28 96 NUS Closed Closed V NSD-NRC-96-4803 Questmn 720 280 (Fire PRA) De staff does not accept fire bemers in a fire probabilistic rid ammessment (FRA) that are not se least 3-hoar renad barriers. For each fee area that is not congletely surrounded by 3-hnur rated bemers, the location should le analyzed as part of the - ' ; fue aren Closed (at t!!7/95 meeting)- Issue subsumed by DSER open iterrL Closed - RAI response also provided in letter dated 8/26/96 { 70 NRR/SPSB 19.1 RAIOt 308.% NUS Closed Closed V NSD-NRC-96-4803 Question 720.288 (Fire PRA) Westinghouse should modify the fue rid assessment to treet the risk ingact of fwenched fire bemers due to operator error or

---

e (at 2/17/95 meetmg)-Issue subwmed by DSER open itent lo ed - RAl response also gwovided in letter dated t'26'96.

l 78 NRR/SPSB 19.1 RAIO: 303 % NU1 Reed Closed Clemed 4 NSD-NRC-96-4803 i Question 720 282 (Fire PRA) Westinghainee has discussed the electrical and spatial separation between the control rurun and the remote shutdown work station with the stafE Ilomever, the presence of a spatially and electrically separate remote shutdown station does not guarantee that the risk frorn control room fires is negligibly senali. Westinghouse should modify the fwe risk assesssmere as follows:

a. quanistatively evahaste control room fwes (the dominant risk contributor in many fire PRAs). This=====nent st. auld include potential hardware, software failures, and human failures in transfemng control to the mnase shutdows; work station.

b. provide the rationale for placing the switch (that transfers power to the remote shutdown workstation)in the remote shutdown workstation area rather than outside of the main control room separated by a fire barrier.

l

c. evaluate the risk inyect ofswitch location (that transfm power to the remote shutowm workstation) with respect to posential fees in the remote I

shutdown workstatiert

d. discuss and clarify whether pinch points exist in the rooms carrying cable between the control roen and remote shutdown work station.

v

e. discuss and clarify whether pinch points exist in the remote shutdown work station roant f descrhe what equipmma can be operated at the remote shutdown workstation g evolusse the w,

.- oflue shorts in the control r6arn for equipmere that cannot be opmeed at the remote shutdown workstation

h. Include the failure probabilny of the operator successfully transfming coenrol to the remote shutdown workstation in Table D. "Sunanary ofIturnen i

Error Probabilities? I Closed (at 8/17/95 eneeting)- Issue subsumed by DSER open itent i Closed - RAI response also provided in letter dated B/26S6. 72 NRR/SPSB 19.1 RAIOl S/28'96 NUS Closed Closed t NSD-NRC-96-4803 i Question 720.283 (Fire PRA) The staffdoes not accept spatial separation oflacasicewrones (without intervenmg 3-hour rated barriers) to dismiss posential fire propagation scenanos-Therefore. Westinghaine should analyre and report f' e propagation scenanos between the feedwater and compresent cooling water pump areas. w Westinghaume should also analyze and report fire propagation between the service water pumps in the updesed PRA Closed (at 8/17/95 meeting)- Issue subsumed by DSER open itent I Closed - RAI response r.lso provided in letter dated S/26/96. l Pase: 1 Total Records: 187

AP600 Open item Tracking System Database: Executiv Summ:ry Data 11/21/96 Selection: [DSER Section] like '19.* And [NRC Branch] like NRR/SPSB* Sorted by item # Item DSER Sedson/ Title /Descnpaion (W) NRC No. Brandt Question Type Status Ddail Last Mod Date Resp Eng Status Status leter No. / Ltr Date 73 NRR/SPSB 19 I RA!Of 3/;s% NUS Closed Closed ( NSD NRC-96-4803 Question 720 284 (Fire PRA) As the August 10,1994, meetirig, Westinghouse agreed to re<va!aate fire-induced loss of offsite power eveses. Westinghouse should include this evaluation in the updated PRA Closed (at E!I7/95 meetmg). Issue sulmsmed by DSER open item. Closed. RAI response also provided in letter dated S/26% 74 NRR/SPSB 19 I RAlot s/1995 Stewnann.P Closed Cloard Question 720.285 (nood PRA) Westinghouse should modify the FRA Gooding assessnent as follows: a provule the quantitative analysis for the normal residual heat removal (RIIR) flooding scenano in the updated PRA. b evaluate in the flooding analysis if flood water can disable a&htional equipment outside of the normal RHR pung roons should the normal RIIR pump room flood.

c. prende the details of the analpes for the other anunant floodmg scenanos listed in Table I-5. These details should include how the floodmg initiating event frequencies for each floodmg area were estimated and the associated safe-shutdown equipment that was damaged l Closed (at ts17/95 meetmg)-Issue subsumed by DSER open stem.

l 1398 NRR/SPSB

19. l.3. I-I DSEROI 9/1996 PRA ISueter Action W Action W V

l Westinghouse should justify assumgeons and data used in calculating the pipe break conenbution to t' e LOCA irutiatmg event frequencies l n Action W - At 4/20.95 NRC meeting. W provided detailed list to NRC of where in PRA Rev. 2/3 this informatmn is escussed NRC renewed the info and issued follow-on questions (82804,2805,2206) Westmshouse responded to the follow-on questions and believes they are closed NRC then issued follow-on question #3257. Westinghouse to respond to that question. 1399 NRR/SPSB 19,l.3 f.2 D5EROI 9/19/96 PRA-ISurter Action W Action W l Westinghouse should address the conenbution to the LOCA frequencies associated with non4reak faikurs that lead to IDCA l Actum W. At 4/2095 NRC meding, Westinghouse provided detailed list to NRC of where in PRA Rev. 2/3 this information is escussed. NRC reviewed the info and issued follow-on questions (#2807 A 2808) Westinghouse responded to the follow-on queshens and believes they are closect NRC then issued follow-on question #3258. Westmshouse to respond to that eguestion. NRR/[S I400 19.1.313 DSEROI 10/2496 nuncev@ucterukmD Action W d% [ lWestmghouse should address the success entena assumed for the systems and operator actions modeled in the evers trees. l Action W - This of relates to T-II uncertainty and passive system rehalulity. Westinghouse and NRC have agreed on the resolution path (br this topic. Westinghouse is currer.tly working on resolving tlus issue. I401 NRR/SPSB 19.1.3.l.4 DSEROI 9/1996 PRA-l/Scohelohkawa Action W Action W

• b l Westinghouse should assess the core damage frequency of LOCA sequences with impaired c~a-W l

Action W. At 4/20/95 NRC meditWestinghouse provided detailed list to NRC of where in PRA Rev. 2/3 this information is discussed Appen&x AS.2 explains why this is not an issue anymore. NRC reviewed the info and issued follow-on question (#2809), which more appropriately relates to DSER Of 19.l.3.1-6 than this DSER 01. Westinghouse responded to the follow-on question, but lelieve this Of is closed, NRC then issued follow-on question #3259 mhich further clanfies their question. Westinghouse to respond to this question. I402 NRR/SPSB 19.13.15 DSERot 3/195 Sancaktar C hed Resolved ( l West'.4.c se should address ;. istencies associated with several sequence transfers between event trees. l l Closed - In Rev. 3 PRA, Section 33.3.3 escusses comcquential events and explains how WestM. se _'" ' g- -- + trarmfers twtueen event trees. l Page: 2 Total Records: 187

W AP600 Open item Tracking Systeni Datab se: Executive Senunary Datn i1/2I/96 l Selection-(DSER Section] like 'I9.** And [NRC Branch] like NRR/SPStr Sorted by item f leem DSER 5edson/ Titiemencnytion (W) NRC No. Branch n-Type Status Detail 1me Mod Dane Resp Eng Staeus Sesass tener No. / IJr Duse [ 1403 NRR/SPSB 19 8.3.14 DSERol 9/1996 PRA-l%urterMkmD Actiort W Action W Westinghouse should evernd the mission time (24 hours) meal for long4ensi core coolms in esquences where the reestar is initially snaustaused at high i Preure. l Action W - In PRA Rev. 2/3. section 6 3 I descussed general success cnema andjustificatim for a 24 hour ei-a= tinee for all core damage esquences Westingliouse is following standard PRA convemions when assessing success enema and mission times. W ' ; eies not agree that the numeien time should be extended for the condwiens stated in this DSER 01. NRC reviewed W positiosi and immeed follow <ui cysestion (#2909). W ^. responded to the follow <ui question, however Westinghouse's position runnins the same. NRC then issued followen questicss 83260 and 3261. Westinghouse to respond to these additional questions. A_ [ I bMC-95-441E 3115,95 1404 NRR/SPSB 19f.3.1 7 DSERol S/2496 Haas Closed E lWeeinghouse shoisid docunient the support synaem fauk trees. _ __ ~ ' ' l Closed - The Rev. 2/3 PRA fauk trees are provided in WCAP-13275. Rev. l. Transmitted via leece NTD NRC-95-4418 dated Mardi 15,1995. NRC has provided a follow-on ques" ion (#2810) related to this DSER 01. Westinghouse responded to the followami quension and believe the question is close.1 i 1405 NRR/SPSB 19.l.3.1-8 DSEROI t/3.95 Momson Closed Resolved lWestinghcesse should clanfy the nomenclature of modularized fault trees used for differne failure niedes. l k lCloerd - Nomenclature is discussed in section 7.5 of the PRA l 1406 NRR/SPSB 191.31 9 DSEROI 9/1996 PRA-2Surter He'S Action W Action W lWeninghaisse shonald venfy thee the PRA models are reprearneative of the AP600 desigrt l h Action W -It is Wessinghouse's intention that the funni PRA models represent the AP600 desigri. However, as design changes may carennue (mainly due to changes initimard to address NRC questions' concerns), a table will be provided in the final PRA report that idersifies design changes not includal in the noodel and the expectee impact on the overall core damage frequency for insemal events based on a quainative ammessment. This was discussed with NRC during the 5/8/96 PRA nereting, 1407 NRR/SPSB 19 8.3.1-10 DSEROI 9/1996 PRA-lSurier/Sancaktar Action W Action W t l Westinghouse should address the applicabihty of genme failure dass to ruk-insportant AP600 (., I { Action W - Rev. 2/3 of PRA contains explanations for why genme data is acceptable for use on passive syneem eiyanpenent (i c., IRWST CVs). NRC f reviewed the info and issued follow-on question (#28 II) Westinghouse responded to the follow-on synession and beheve it is closed. NRC then issued [ follow-on question #3262. Wessinghouse to respond to the question. 1408 NRR!SPSB 191.31-11 DSERot S/2496 BurterTreciand Closed g(N C (* Iweainshause should ad*ess the losic and insiru=er.aiiosi raehire den for the nucropmcessor-based =, derived from WeWinghouse data-l 8 Action W -IAC failure data is discussed in Chapters 26-28 of Rev. 3 PRA. NRC revwwed the PRA and has issued follow <ui speemian (#2812). I Westinghouse respon&d to the follow <ui quession and believe it is closed. The detailed data is propnetary and is hoissed in Westinghouse calculation I noses, which can De made availshie for NRC to review. This has been discussed during several anectings wish NRC-1409 NRR/SPSB 19.l.3.5-12 D5ERol 7/16/96 Burger /Sancaktar Closed IP NSD-NRC-f770 ]Weeinghouse shouldjustify the assumed error factors associated with ruk-importase ewnes. bJ: W W' C. ' l ( l Closed - Unentainty analysis insaned as Chapter 58 of PRA Error factors are discussed there and in the data analysis chapeer of the PRA (Chapter 32). ] r ? l i i Page: 3 Total Records: 157 i t

i AP600 Open Itent Tracking Systen Database: Executive Sumni ry Dat:: 11/21/96 Selecties: [DSER Section) like *19. And [NRC Branch] like 'NRR/SPSB* Sorted by Item # leem DSER Section/ Title >Descnpaion (W) NRC No. Branch Quesaan Tne Status Detail Ims: Mod Date Resp Eng Status Status teeer No. / IJr Dese 1410 NRR/SPSB 19.13 1-13 DSERol W1996 PRA-1/Buner/Sancaktar Action W ActionW / Westenshouse should justify the assumed multiple Greek letter (MOl.) factors used in calculating the conuren<suse failure (CCF) probabihty of the IRWST gravity injection ime check valves. Acten W - At 4/20/95 meeting with NRC, Weemghouse povided detailed list of where in PRA Rev. 2/3 this unformation is presented NRC reviewed the mfo and issued followen question (#2813). Westmghouse responded to the followen question and believe it is closed. NRC then issued followa question #3263. Westinghouse to respond to the questices I_ 1411 NRR/SPSB 19.13.l-14 DSFROi 50496 BunerTreeland Closed AntagfT h yg< y l Westinghouse shouldjustify the assumed heta factor used in calculaimg CCF probabildies for several hardware LAC congonents of the PMS. l Chagder 28 of Rev. 3 FRA discuss PMS l&C conunnn cause faihsres. NRC reviewed the info and issued followen question (82814). Wedmghouse l responded to the follow-on questiest I 1412 NRR/SPSB 19.53.1-15 DSERCI SO496 OucterTreeland Closed g gg / l Westinghouse shouldjustify the assurned probalmtrry for lac soRware m +...:. l l NRC reviewed remed PRA and issued followen question @2891). Westinghouse responded to the followen questiort l 1413 NRR/SPSB 1913.116 D5EROI 50496 Bucter/Sancakte Closed aff ^^ "^ Westinghouse should justify the frequency of unscheduled maintenance, the assumed or allowed outage tem and the assumed error factors (or distribution parameters) for maintenance duration and component unavailability associated with maintenance. Maintenance assumpt.ons are provided in each PRA system chapter. Error factors ihr maintenance unavailabihties will be povided. as applicable,in the uncertainty analysis. ,NRC reviewed revised PRA and issued followen question (82899) Westmghouse responded to the followen questiest i. 1414 NRR/SPSB 19.83 1-17 D5EROI 50496 Pacier/Wallace Closed g 4 ("I l Westinghouse should revise the human rehabihty analysis. l At 4/20.95 enectmg with NRC, Westinghouse provided a detailed list of where in PRA Rev. 2/3 this information is presersed NRC reviewed revised PRA i and issued followen questions (s2946,2959). Westinghouse responded to the follow +n questions and believes they are closed 1415 NRR/SPSB 19.13 1-13 D5ERol 1!!995 Wallace Ciceed Resolved \\ f Westinghouse should identify assumntions n de in the IIRA about the centrol room design and about the emergeng operating procedures for all nsk-impostare human actions modeled in the PRA. l Closed - At 4/20/95 meeting with NRC, Westinghouse povided a detailed list to NRC of where in PRA Rev. 2/3 this info is peesented l 1416 NRR/SPSB 19.13 1-19 DSEROI 50496 BucterNallaccMorsemann Closed Resolved '. Westinghouse should demonstrate that it has considered the current understanding ofcrew responses during a ceenmonwause failure of several IAC l hardware and sonware m.m.c i Closed - At 4/20.95 meeting with NRC, Westinghouse provided a detailed list to NRC of where in PRA Rev. 2/3 this informatwn is presented. NRC reviewed and statused as resolved j 1417 NRR/SPSB 19.13 1-20 D$ERot 3/195 Wallace Closed Resolved \\ Westinghouse should justify the operator stress levet used in calculatmg the pobabihty for the operator action to scram the reactor within I nunute during an ATWS. t l Closed - Information pesented in Sections 30 6.38 - 30 6.42 of PRA. l Page: 4 Total Records: I87 t

AP600 Open Item Tracking System Datab:se: Executiv2 Summ:ry Dat:: 11/21/96 Selection: [DSER Section] like 'l9 And [NRC Branch] like 'NRR/SPSir Sorted by Item 8 liern DSER Sectsonf Title /Descriggion (W) NRC No. Brancit Qaestion Type Status Detail Imt Mod Date Resp Eng Status Status tener No. / IX Date 1418 NRR/SPSB 19.l.3.1 21 DSEROI S/2496 Burta/Sancaktar Closed Resolval Westinghouse should discuss the dominard cuterts (by accidem sequence) for eacts of the tg accident . -- that cunnalatively contribute at least 90 percere to the total core damage frequency (CDF) from internal events. Closed - Information is provided in Chaptee 39 of PRA Rev. 3 (Top 13 sequences cunwrustatively egsal 90% ofireernal events CD9 NRC reviewed info and statused as resolved. 1419 NRR/SPSB 19 f.3.1-22 DSERot 9ct95 Sawaktar Closed Resolmi l Westinghouse should venfv that the omninant cutsets do not contain correlated events. l Closed - If" correlated events' rneans comrnon cause or dependent failures, this.s addressed in Section 29.2 of Rr t. 3 PRA N AC reviewed PRA and statused as reschwi 1420 NRR/SPSB 19.l.3 l-23 DSFROI 7/16/96 Burta'Sancaktar Clemerl D RC-96-4770 l Westinghouse should identify the maja canributors in the uncertainty of the CDF estanate for the plare. l l l Closed - The uncertainty analpis has been provided in Chaper 5 I of the AP600 PRA l / 1421 NRR/SPSB 19f.31 24 DSEROI til995 Trarvsancaktar Closes gW ./ l Westinghouse should expand the importance analpis to provide proper irnerge etation of the results, l l Closed - Importance analyses are provided in Chapters 33 and 50 of the PP ( l ht g 1422 NRR/SPSB 19.1.3.5-25 DSERot 3/1995 Tran/Sancaktar Cloem! Amrft Westinghouse should perform additional sensitivity analpes to determine (1).he sensitivity of the estimated C0F to poterarat biases in numerical salues. (2) the irnpact of pdential lack of rnodeling details on the estimated CDF. and (3) the sensitivity e f the estimate 1 CDF to previously raised issues l Closed - Sensitivity study analpes are provided in Chapter 50 of the PRA l 1423 NRBL3PSB 19.l.3.5-26 DSFRol 9/1996 PRA.1BueterHaag Action W Actica W Westinghouse should use insights from the sensitivity, uncertairwy, and importance analyses in cenjunction with assumpti:wm from the entire PRA to identify design certilication and operational requirements, as well as COL an I interface requirerrents. l Action W - Westinghouse is currently working on "Jiis. ~~ l 1425 NRR/SPSB 19.l.3.2-1 DSEROI 9/19/06 PRA.2/SktAMaagWay Artiert W Adion W + lThe staff has not yet completed its review of the revised seismic margins anafpis. l Action W - NRC audited Westinghouse calenotes on llCLPF calculations. Westinghouse respamling to NRC rnecting action items. On 8/295, received a fax from NRC containing seismic margins questM 1426 NR R/SPSB 19 I 3.2-2 DSEROf 80896 liangHUS Cined j NS C-964803 l Westinghouse should provide specific references to SSAR information used in the fire PRA "~ ' ~ l l Closed - response issued t'2N l _,.,g,,,y

~-

1427 NRR/SPSB 19.l.3 2-3 DSEROI t/2tM6 ItaagHUS C% sed .AsessarW-NSD-NRC-96-4803 l Westinghouse should provide ir formation on fire areas and fire zones considered in the PRA ~ l l Closed - response issued 8/26.96. l l Page: 5 Total Records: 187 i

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AP600 Open Item Tracking System Datbase: Executive Summcry Date: 11/21/96 > election: [DSER Section]like'19

• And [NRC Branch] like NRR/SPSIY Sated by item 8 dd b Item DSER Section/

Titk/Descrrgvion (W) NRC pM No. Ihanch Question Type Staras Detail last Mod Date Resp Eng Status treter No. / 1Ar Dane a 1439 NRRJSPSB 19.8.3 2-15 DSERol IM4% PRA-10nad Closed , lNTDyC-95-4513 [ l Westinghouse should povide adddeonal information for each Doo&ng area credded in the floodsng PRA Closed - De requested information can he found in the PR A Good ana*pis powded in Chapter 56 of the PRA NRC redewed PRA and issued follow-on questions (#2900, 2901, 2902, 2903. 2904. 2905, 2906). Westinghouse responded to thnee followen questiere in letta NSD NRC-96-4836 (10/23.96) 1440 NRR!SPSB 19.l.3 2-16 DSEROI 19 % StevewntP Closed Resolved NRC-95-4513 lWestmghouse should evaluate Hondmg areas that cors.ain safe-shutdown equipnent. l Closed - PRA flood analpis evaluates areas that cordain safe-shutdown equipmers as modeled in the PRA PRA flood analpis is provided in Chapter 56 of PRA 1441 NRRISPSD 19.l.3 2-17 DSERot gmt% thlHand Closed Actio NTD-NRC-95-4513 l Westinghouse should documers how the floodmg initiatmg event frequencies for each flamhng area were estimated. l Closed - PRA flood analpis growded in Chapter 56 of PR A The flooding analpis domnents the flood initiating event frequency calculatmns NRC reviewed PRA and issued follow-on question (82907). Westinghouse respeded to the follow-on questi<m in letter NSD-NRC-96-4tS6 (10/23 96). I442 NRR/SPSB 19 1.3.2-13 DSERol IM4% PRA-lOnnd Closed Action NTD-NRC-95-45 t 3 l Westinghouse should hst a!! human actions that were credded in the floo&ng PRA l Closed - PRA flood analpis is provided in Chapter 56 of PRA The operator actions developed for floodmg scenanos are presented in tius chasacr. NRC reviewed PR A and issued follow-on question (e2902). Westinghouse responded to the followen question in letter NSD NRC-96-4856 (10/2396). 1443 NRR/SPSD 19I.3.219 DSEROI iM4% PRA.] Tinad Closed Action NTD-NRC 95-4513 l Westinghouse should identify all risk dommant flood minimal cutsets in the flondmg PRA l Closed - PRA flood analpis dominare mmimat cutsets are novided in Chapter 56 of PRA NRC renewed PRA and issued follow-on questmn (#2909). Westinghouse responded to the follow-on question in letter NSD-NRC-96-4856 (10 'Z3,96). 1444 NRR/SPSD 19.1.3 2-20 DSERot 3M4% PRA-ITinnd Closed Action NTD-NRC-95-4513 l Westinghouse should prodde deta is of the normal RilR pipe rupture analpis in the floodmg PRA l Closed - PRA flood analysas, provided in Chapter 56 of the PRA includes a discussion on pipe ruptures. NRC redewed PRA and issued followen question (82910) Westmghnuse responded to the follow-on question in letter NSD-NRC-96-4856 (10/23/96) 1445 NRR/SPSB 19.I.3 2-21 DSERot IW24% PRA-lTland Closed Action N NTD-NRC-95-45 l0 l Westinghouse should report its Focused PRA results in the AP600 flomhng PRA l Closed - The focused PRA sensitivity study resuhs pertammg to flood PRA are prodded as part of the RTNSS focused PRA sensni6ty study (Chanter $2 of PRA) NRC issued follow <m question (#3241) Westinghouse responded to the followen question in letter NSD-NRC-96-4356 (10/23.96). I446 NRRSPSH 19 l.3.2-22 DSERot 10'24 % PRA-1Tiond Closed 'RC 95-45[ [ Westinghouse should provide sensitivity and importance analyses in the AP600 floodmg PRA l Closed - A sensitivity study was performed pertaining to the floodmg eversaleveloped operator actions. Since the flood PRA is a limited analysis with various conservative assurvytions, it is not appropiate to perform adddional sensitwity analysis or importance analpes since it could produce Inased msights. NRC reviewed PRA and issued follow-on questions (#291I A 2912) Westinghouse responded to those follow-on questions in letter NSD-NRC-96-4256(10/23.96). Page: 7 Total Records: 1R1

AP600 Open Item Tracking Systent Database: Executive Susantry Date: 11/21/96 j Selection- [DSER Section] like 'l9? And [NRC Branch] like NRR/SPStr Sorted by item # [ Item DSER Sectionf TitleDesenpeian (W) NRC-No. Branch Qisestion Type Status Detail 1mst Mod Date Resp Eng Stanum Status 1.meer No / IJr Deer 1447 NRRMPSB 19.13 1-1 DSER ol 504 % weilace Closed Action W NTD-NRC-94-4510 i Westindeciset sinnuld sulugue a detailed tault analysis justifying die wahse assumed for operseer error during desadouni deal would inadwestently &aut die i reactor vessel level inveinery through the normal RilR syment Action W. Infornntion dircussed in the Shutdown PRA (Chapter $4 of PRA). NRC roiewed PRA and issued followen questiosa (s2939) Wessinghouse l responded to the follow-on question and helines it to be closed [ 1448 NRRJSPSB 19133-2 DSERol sc4% Wanace Closed Action W NTD NRC-95-4510 [ t l Westinghouse should evehsase the nsk for safe shutdown when the RCS temperasure es gresser dien 177 aC (350 eF). l v Action W. Descmsson of events evaluated in shutdown analpis is paesevned in subsections 54 2 3 and 54 2 4 of the PRA NRC reviewed PRA and issued followen question (#294J). Westinghouse responded to the follow-on questiest 1449 NRR/SPSB 19133-3 DSERol 11/395 Wallace Closed Resolved NTD-NRC-95-45 80 j lWestinghoisse should usang a seperate event tree to assess the risk associated widi overdraining shming shusdowst l 7 f M. Shutdown PRA (Chapter $4) provides overdraining shutdown evaluation. ] 1450 NRRSPSB 19.13 3-4 DSERol 544 % Wallaceiteul Closed Action W NTD NRC-95-4510 [ Westinspiouse shoisld document the functiosus of the plant snarutoring sptem, diverse actuation spteni, and everse indication sparen during safe sinadower, [ cold shusdown, and nueBoopfvessel Sange operatiost Action W. Section 54.5 of the PRA provides information concerneng the modeling of PLS, PMS, and DAS during the low power and shutdown conditions niedeled NRC reviewed PRA and insised follow-on question (e294I). Weeinghouse. " f to the followen questicet 1451 NRR/SPSB 19.13 3-5 DSERot l/9% Wallace Closed Resolved NTD-NRC-95-4510 t Westagliouse should develop separate event trees far loss of normal RilR and loss of offsite power (IDOP) during safe /celd shutdown and '",w: II'ner. lCloerd - Separate event trees for loss of RNS and loss of otNte power are provided in the low power and shuidown PRA (see Section 54 4 of PRA). ] f 1452 NRRJSPSB 19.1334 DSFRol 544 % Wanace Closed Action W NTD-NRC-95-4510 lWestinghaisse should docurnens the --- e unavailabsinies and related assumptioses used in the slusadowns PRA l f Action W. Maineenance infonnation and assumptions at shutdome is presented in Chapeer $4, low power and shutdown ruk assessment. Specific f information on maintenance can be found in Table 54-8. NRC reviewed PRA and issued follow on apsestion (#2942). Westingpiouse responded to the follow-on qisestiost I 1453 NRR/SPSB 19.133-7 DSERol ll*395 WaMace Closed Resolved NTD-NRC-95-4510 Westinghouse should justify the snissiosi tune used in the shutdown PRA for normal RilR operation, for boeh het/ cold shutdown and enidloop/ vessel flange j operation. i l Closed. Mession times for shutdown. - are escussed in suheettion $4 3.2 of the PRA l h 1454 NRR/SPSB 19.33.3-3 DSERol 11/395 Wallace Closed Resolved NTD-NRC-95-4510 l lWestinghoisse sinould document the donunant shutdown sequences and cuasets, assismeng that no safety-relased systems are available. l Closed. Shutdown focused PRA sensitivity study enleases the case with no crecht for nonsafety-related system snitigatiost Die results,inc ndung e dominant cutsets, are presided in Chapser 52 of the PRA I r r i Page: 8 Tolal Records: I87 i i b

m AP600 Open Item Tracking System Database: Executive Summtry Dett: 11/21/96 Selecties: {DSER Section] like '19

• And [NRC Branch} like NRR/SPSB' Sotted by item f fle5n DSER Section/

Tnle/Dacnytion (%) NRC = No. Ivanch Questim Tne Status Detail last Mod Date Resp Dig Status Status 1meer No. / IJr Date 1709 NRR/SPSB 19.1 MTGol t/199 Sancaktar Cloard Resolved t NTD-NRC-95-4510 Per Oct. 20,1994 meeting: The staff requested that Westinghouse conrum why cumets identified by the staff were not included in Table F 14 of the PRA report Westeghouse agreed to review the focused PRA sensitivity study for the potential missing cutsets as part of Revisinn 2 of the PRA (NRC inceting notes dated 1I/1/94) Closed - The focused PRA sensdivity study has been updated as part of Rev. 4 PRA The focused PRA senshisity study is presented in Chapter 52 of the PRA Sanc 5Etaas Cloard Resolved s NTD-NRC-95-4479 1710 NRIUSPSB 19.1 MTGol tit 9s Per Oct.20.1994 eneeting: Westeghouse to provide an electronic version of the Isvel 1 PRA, Pev 2, fault trees and cutsets. The same information prmided in response to RAI 720 58 for Rev. O will be provided De staffis interested in using the information to update data for the IRRAS modeling of the AP600 desiyt (Per NRC meeting notes dated I t/I194). l Closed -Information provided on tapes to NRC en letter dates June 2,1995. / ] 1973 NRR/SPSB 19.1.31 1 DSERCOt. 7/15.96 waam Cloard Action N /NSD NRC-96-4662 [19. I.3. 5 -l The COL applicant should incorporate the list ofimportare SSCs in the D-RAP and snaintenance pograms. l Closed - SSAR subsection 16. 2.7.2 Revision 7, includes a COL information item covering the holder's activities for listing and --' ;SSCs in the RAP rogram / 1974 NRR/SPSB 19 l.3 1-2 DSERCOI-5/t,96 Wesm Closed Action N NSD-NRC-96-4662 19.l.3.1 2 The COL applicant should use the list of risk-important cperator tasks to prevent or nutigate severe accidents in the control room design and I fixed display panel, as well as to irnplement pacedures and develop training programs. Action N - See resporne to DSER Ols it 5.3-1 and 18.5.3-2. Closed - Resposee provided by NSD-NRC-96-4662. l 2046 NRR/SPSB 19. DSERCISO t/1995 Sancaktar Cloard Action w ) W D( h

30. Treatment of Common Cause Iailures According to DSER OI 19.l.3.1-13, the Staff believes the Multiple Greek letter (MGL) factors used to calculate the common cause failure pobabilny of the IR WST gravity injection line check valves are significantly lower :han those recanunended by the ALWR URD.

Closed -The MGL factors used for IRWST equirrnent is from tJRD Rev. 5/6. See subsection 29 4.3 and Table 29-2 of the PRA for more information. (At the 4/20/95 mec*ing with NRC, Westinghouse povided a detailed list of where in the PRA this information is resented ) ,1 2047 NRR/SPSil 19. DSERol50 6/5/96 1%ucter/Wallace Closed @N kQmh E St. Ilumen Reliabdity Analpis l This is pimarily a documentation issue where Westinghouse needs to ' nprme the docurnersation of Rev. O PRA assumptions and justifications for human u error pobabilities. Iluman Reliabdwy Analysis was updated as part of Rev. 2/3 PRA At 4/20S5 meeting with NRC, Westinghouse provided a detailed list to NRC of where in the PRA the information is discussed. Waning for NRC review. t Page: 9 Total Records: 187

AP600 Open Item Tracking System Database: Ereestive Summ:ry Date: 11/21/96 Selection: [DSER Sectionj Itke 'l9.** And [NRC Branch] like NRR/SPSIY Sorted by item # Item DSER Sectionf TitleDescription (W) NRC No. Branch Question Type Status Detait tast Mod Date Rey Fmg Status Status t,tter No. / 1.* Date 2048 NRR/SPSR 19. D5FRotM 9/11 % Haas Closed Action W l52. Integrated the of PRA Majw Insights DSER Ot 191.3. I-26 is a reminder that Westvighouse needs to use insights fmn the PRA in an integrated fashion to identify design certification and tional rapsirements (ITAAC, RAP. Tech Specs. grocedures) as wel: as COL and interface requirements. Dnciassed at 29.95 SMM) Rev. 2 to PRA to include these insights. 5/2/95 Status: Insigins noe submitted yet. Issue descussed briefly during March 29 30.1995 mig. CIDSED This item number is being closed since it is a duplicate and is already in the datebase under DSER Of I9;1,3.1-26. 2049 NRR/SPSD 19. DsERolM 51 % BucterTeeeland Closed Act N D RC-96-4688

53. Instrumentation Failure Data for Microprocessor-Based Components NRC requests for information on the Westinghouse instrumentation failure data used for nucroprocessur4msed m.,-a.= (DSER OI 19 I.3.1 1I).

Action N. IAC inforrnation is presented in Chapters 26 tfrough 28 of the PRA Waiting NRC review. Closed. Response provided by NSD-NRC-96-4688. _l 2050 NRR/SPSB 19. DSER olM 6/5.% Butte'esencakur Closed Action gp (_.

54. Applicabihty of Generic Failure Data in PRA NRC are comrned with applicahitity of generic failure data, derived fmn current plants, for the AP600 passive zystem equi An NRC concern is that the AP600 emironment and operating conditions are different than current plants. An example is IRWST injecti<m line g g(DSEROI 19.t.3.1-10)

Action N. Rev 2/3 of the PRA corsains explanations for why generic data is acceptab!c for use on passive system equipmers (i e., IRWST CVs). Waiting for NRC redew. I A b C 7 L1 O( sr l $ () { o, (( ", (V vj ", ~ N up s c x F ".r G -Q 19.1 3.1 l;, I' [{ ) l G S b?R ~ Se Q RkT 790n ( /3 n Page: 10 Total Records: I87

AP600 Open item Tracking System Database: Executive Summ:ry Detn 11/21/96 Selection: [DSER Section] like *19? And [NRC Branch] like NRR/SPSB* Sorted by ltem # Item DSER Section/ Title /Descnpion (W) NRC Na Question Type Status Detail last Mod Date Resp Eng Stasus Status I,eee Na / IJr Date l 20$1 RR/SN 19. D5ERol56 9/11/96 llangohkawa Closed Active r -)

55. Passive System Relistahty

/ Per DSER OI 19.l.3.1-3, the Staff requests detailed ernmerention on the success enteria assumed for varitans symems and operator actions modeled in the d -) event tree top events. I At 7/27/95 meeting twtween NRC and W. Westinghouse presented how we were proceed ng on the T/II uncertainty evaluation. NRC's interpretation of the scope of what T/II uncertainty evaluation should be was evanded NRC Acten to provide to Westingiumne again what the mission of this evaluation is to be. At 6/2995 SMM, W/NRC appear to be dwerging on the purpose of the evaluation Actions were providal for both W and NRC. At 4/20c95 meeting between W/NRC, agreed to the purpose of the Till uncertainty evaluation and the steps involved l [ / Descussed at 2/9.95 SMM) l Staff will develop focussed issues that will define path to resolution 5/2.95 Status: Discussed at April 1995 SMM. Issue dncussed during March 30 A Apnl 20,1995 meg W A staff agree on a resolution path for this issue (margins approach). p (Discussed at 4'4.95 SMM)

55. Passive System Rehability Westinghouse will he benchmarkmg MAAP4 against NOTRUMP to demonstrate the adequacy of using it for addressing this issue. The staff will also henchmark M AAP4 against RELAP to identify any poblems with using this code.

The staff r~_...._..M that Westinghouse identify preferred analysis cases of polonged, rnamirnum core uncovery emes, and evaluate these cases (weh [ sensitivity runs) first to provide some confidence and feedback in the areas of conmn in the short term. Action W Westinghouse will provide the NRC with the list of preferred analysis cases. (5/295 Status) Action W - Analysis cases to be provided as part of MAAP4 T/f t uncertainty bencianarking process. Action N The staff will provide details of a calculation using the RELAP code that indicates that MAAP4 is nonconservative. ($295 Status) Action N - Still under stafIreview. t CLOSED-This item number is being closed because it is a duplicate of another every in theas h==e and is covered by DSER Ol19.1.3.5-3. 20$2 NRRjSPSB 19. DSER ol50 orlW6 BlassNUS Closed Action W

56. Quantification of Control Room Fires L

Per DSER O119 I.3.2-5, NRC requests AP600 quantify control room fue in the Fire PRA. t Dncussed at 2/9.95 SMM)

• ,,, a t ("

t % 0Y f .}g q t.0 issue to be clarified at upcoming nating. ( r, u ,i i g. [ 5/2.95 Status: Not discussed yet. d A Cl.DSED - This inem number is being closed since it is a duplicate of another every in the d=*=k==- and is covered by DSER of 19.1.3.2-5. (PSR 19.I RA!OI 10r3096 Orr tmz Closed Action W NTD-NRC-96-4617 t /4.96 2714 NR O Follow <m question item I2: I In Peta Section 42.4, coefficiers of variation, not coefficient of variance, should be used h l Closed - See response to this meeting item (Westinghouse letter dated I f4,96). Chapter 42 of PRA has been revised I Y i l I r Page: II Total Records: I87

AP600 Open Item Tracking Systent Datab se: Executive Summ:ry Dat2: 11/21/95 Selection: [DSER Section] like '19.*' And [NRC Branch] like NRR/SPSlY Sorted by Item 8 Item DSER Sationf Title /Drscription (W) NRC No. Branch Question Type Status Detail tast Mod Date Resp Eng Status Status 12eer No. / 1Ar Date 2792 NRR/SPSR 19 I AAIOt W19% PRA-2/SMABucier Adian W Action W j Seismic Marams Analpis follow <wn question I: The risk-based senmic margins (SMA) must be updated to reflect revisions made in the internal ewnt analysis. Such rednions include changes in event and fault tree models, sucass cntma, hardware failure and hurnan errw gunbalmiities. The updated analpis should state explicitly all inyortare assuncions made in constructing the seismic evers trees, starting with the internal event trees. h 2793 NRR/SPSB 19.1 RAIDI 9/19 % PRA 2'5KMBucier Action W Action W Seismic Margins Analpis follow <ai question 2: W guidance provided by NRC for SMA requires that in addition to seismic only conenhutions, combinations of neismic and ran&wn failureshuman errors need to be idernified and reported Uniy randm 6 fai:ures Irir g, fe. lure probabitary of I E-3 or greater need to be : " 1 The eglanation provided in Sections H.3.5 and 2 2 is not clear. Please explain how potential- ~ ions of seismic and random failures were sptematically iemtified. 2794 NRR/SPSB 19 1 RAlol 10 9 % PRA.2/5MABueter Action W Artica W V Seismic Margins Analysis followwwi question 3: Because of the extra demands on the operators following a seismic everd, human error probabilities (If EPs) used in newsmic ewnes should be reviewed to determine their applicabilny to the conditions expected to exist aAcr the seismic ewns of the postulated magyntud. Please idersify which of the innernal ewnt's " operator failure to start ADS 7 is used in the SMA and provide a twiefdiscussion ofits applicability. l 2795 NRR/SPSB 19,1 RAIOl WI9% PRAESMABucter Action W Actinui W ( Seismic Marguns Analpis followwwiquestion 4: A mission time of 24 hours is assumed in the SMA (as for the intemal events analysis). This assurrpion enust be justifeed on the basis of the plare state at [ 24 hours. If the plare is nre at a stable state, the beyond 24 hours risk must be assessed or shown to be nigtigible (e g; in terms of available options, tune I windows for human actions, etc.) An example is the scenanos of a seisnic evert that causes loss of cifsite power and loss of all norMafety related " active" l systems (Iow HCLPF values)conhned with failure toisolate the - __a (random phas seismic) 2796 NRR/SPSB 19.1 RAIOl 9/t9% PRA@SMABucier Action W Action W v Seismic Margins Analpis follow <wi question 5: The seismic fault tree for the passive RilR (Figure 2.2-2) shows a system failure when the D power needed to open the AOVs is lost. Do not these AOVs fail open upon loss of 125 V DC power 7 Please explain. 2797 NRIUSPSB 19.1 RAIOR 9/19 % PRA45MABucier Action W A;: tion W D Seimnic Margins Analysis follow-on question 6: Section H 3.2.8 states: "a consequeveial small 00CA could occur because the pressurizer safety valves open and do not clone, small pipe breaks occur, or for any other ressort" Are these small pipe breaks due to the seisenic event? If the answer is yts please provide the llCLPF valves for such small pipeg 2798 NRR/SPSB 19.1 RAIOI 9/t9% PRA.2/$MABueter Action W Action W D Scismic Margina Analysis follow-en question 7: l No scissnic ewed tree is included in the analysis for main steam line tweaks inside i .7 (MSBI). The explanation for this (gwodded in 11.3.3 5)is t not clear. Please provide a seisenic event tree for MSBl or explain why this ewnt tree is not needed to gain addnional insights than those already available through other seismic eveva trees. 2799 NRR/SPSB 19.8 RAlot 9/19 % PRASSMABuceer Action W Action W { Seismic Margue Analysis follow-on question 8: Westinghouse should correct several errors in reporting combinations ofscismic and random failures (rnixed cut sets). For example,in sequence 27 of MSDO evers tree, l.29g + OA(2.2E-3)is repceted. The correct result should be stated as: 1.28g + 1.2Rg

• OA(2.2E-3)- 1.2tg.

I Page: 12 Total Records: I87 r

9 AP600 Open Item Tracking System Database: Executive Sanunary Datz: 11/21/96 Selectlea: lDSER Section] like 'I9.** And [NRC Branclij like NRR/SPSir Sorted by Item 8 l'em DSER Sect =n/ Title 9escrgeian (W) NRC No. Branch Quenhan Type Status Detail tant Mod Dese RespEng Stams Stams faaer No. / ur Dane j 2900 NRR/SPSB 19.1 RAlot 9/1996 PRA.2/SMAPueter Actkui W Action W ( Semme Margins Analysis fonow<ai question 9: ^ The only failure mechensen considered for loss ofe .. cochng, as a resuk ofidockage of the baffle,is tier seructural failure of the baffle itself flowever, it is possible for the baffle to be idocked as a resuk of release of water following the seismic induced failure of the Passiw C ^ - Cooling Weser Storage Tardt (PCCWST) and failure to drain the water below the baffle plate ese to, for example, blockage of the drains by debris frons the failed [ PCCWST. Westinghouse shoisid report the llCLPF for the PCCWST and evaluate and discuss the feasibility of this - ^ cooling failure mode. 2801 NRR/SPSB 19.1 RAIOI 91996 PRA43MA9arter Action W Action W ( l Sersmic Margins Analysis follow <me questeon 10: For several components, the reported HCLPF and median values seens to be 6- - For example, the HCLPF vahme for the RCS cosuponents V001 A/BCD is estirnated to be 2.8Sg This is higher than the fisied nudien value of 2.38 (Table H-l). Please enplaint 2002 NRR/SPSB 19.1 RAIOl W1996 PRA 2/SMABurier Action W Action W Seismic Margins Analpis follow-on queniori l1: Westingliaine should evaluate the resuks of the seismic analpis. This should include sensiti6ty analyses to evahnese the efects ofchanges in certain assumptions. For esemple, the efect on the plant flCLPF of a reduction in the assumed HCLPF valws of certain syssema, seructures and compiments (e g, due to uncertainties) Such sensitivity analpes provide important insights shout the design. The documentathm of this evaluation should include: (1) a f discussion of the plant HCLPF;(2) a discussion of the donunant seisnue and mixed (seismic /norHeismic) sequences,(3) conclusions and escussion of the conclusions; and (4) a list ofimportare assumptions and innigtes. i t 2803 NRR/SPSB 19.1 RAIOt 9/1996 PRA4'SMASurser/LaPow Action W Action W [ Seismic Margins Analysis follow-on question 12: Passive systems depend on wry low eidng heads to generate the required flow. The specific orientation of etysipment and piping may hase a significant 6 unpact on the abihty of these speenu to generate sufficient head. Seismic events in excess of the SSE have the posermial to resuk in inesahic behavior and associaeed,. ..; distortion of speenes or the str.etures they are anchored to. In forced flow speems, such nunar estortions (such that the operability fo the,; ^ would not be congremised) womald not resuk in syseein failure. since pumped flow would be able to overcome minor changes in flow [ resistance. Therefore, predoens SMAs (for operating and advanced evolutionay reactor designs) do rue consider auch finiture inades. Homewr,it is not i clear that this assumption can be hatty supported for passive speems. f Changes in the orientation ofequipnwie or piping (e g, the downseream end of a pipe being raises above the upmereans event) could resuk in loss of suftkieve driving head through increases resistance or the formation of gas bubbles (" loop erals-) within the piping nsas. There is a need to tanderstand the j unpartance of piping orientation to the success of these speems. Similarly, seismically-iruhaced faihare c(check valves to open Inas not been considered-While the existing guidance en SMAjentifies this assunytion for chedt valves in active speems, that guedence did not consider whether such an i assumption would be valid under the operating cond,tions presese for pasive systerns. A systemmeic investigation is needed to determine whether there are passive system related" fadure niodes with HCLPF values lower than those already considered in the SMA If such faiksre mndes are found. they should be addressed in the SMA or show (e g, using remshs from the passive system performance reliability analysis) that they will not affect the conclusions and insights expected froen the SMA, [ ? i i i r Page 13 Telal Records: 187 4 1 V

QU" p U c c#.A c- ^ [b[p AP600 Open item Tracking System Database: Egecutive Summ:ry Date: 11/21/96 c-Selectiott: (DSER Section] like '19.** And [NRC Branch] like NRR/SPSB' Sorted by Item # j c \\ Item DSER Section/ Title Desengeion / (W) NRC g .N No. Dranch Question Tne Status Detail last Mod Dese Resp Eng Status Stanum i 12acr No. I Ltr Date 2904 NRR/SPSB 19.1 RAIOl 1/12N Sdm12 Closed RPitnerW-NSD-NRC-96-4662 At-S,,p. 7". N N N [- 720 W 'h M boM "^ 1. The Passive Residualilcal Removal (PRl!R) tube rugeur. frequency was dioacn try Westmshouse to be 5.0E-4' year on the bania that it should he t-agswossnately an wder of magrutude lower than the Erquency of a Steam Generator Tube Rupeure (SGTR) evose. If Wessingpiouse's appM, bened on n [ pipe break failure rate of 4 25E-10 per year per section, was followed, tius frequency would be S OE-3/ year. If the failure ruse fer PRl!R heet exchangers d, the PRifR tube rupture frequency would be 2 OE-3/ year 1 M of I DE-7/ year (_..._.1/ by EPRI in its ti shtv Requirements ib-- t SirM, dCk'I', More detalTed RAls W'f' *ubmitted anSuper seded

• ins: (

j' '. i lgCy W rien" "' ,,;ca ace,imt,,,ndo,ta,,, ant.,d,t;on, by anowing iocai lye this open item. d gtem is admingstrative1Y resolve.e items W$I1 technically r,3o _.eams io a y 1 g. 6edy orwe,r (in the iRwSTx uaer stagn condaions, _,,,,,,,,,,,,,,;,,,,,,y;,,3,,,,, y,,,,,g,3,3,p.,;,,,,,,,,,g ,a,,;,,,io,d,,,3,, -r. ng and supports, includes pnternial steam hansner load caused by phase separation within the tubes uMer accident conditions, and (5) the [3g5reSO]gtiOn OE, 3 ~.) i the tubes during accident conditions where entical heat fluz and vagblanketing of the tubes may be of concern. unaHe beauransfer area of PRifR heat exchanger, as compared to steam generators, combined with the potential for two-phase flow in the IRWST side of 1 KdLg.44[s rW(e /) fy /J [ ,,fp 5 $tt'A tttilk i Y ) [ Closed -lisued RAI response 2205 NRR/SPSB 19.1 RA!Of 111m Sancdur Closed A W* NSD-NRC-96-4662 Us Related to DSER Open item 19.l.3.1-1 MW 2. The primary sutem pipe Iweak analpis assumes a certain,v i,.c-.; of the failure rate, amedmg to pipe sires, into "large"," medium", " intermedium

• and "smatt" LOCAs. Although sud

,r c,.cc-.; is logical. the assumed percermages are rather arbrtrary. Sensitmty analyses are needed to assess the impact of this assertionment en the PRA resuhs and insights. (Closed - RAI respome issued.,,g C k C eygpwtp ((M 44Og,$.a g d g 4 Q M-W 2R06 NRR/SPSD 19 I RAIOI 5/24 % Sancatar Closed Asicerf NSD-NRC.'96-4662 RAls Related to DSER Open item 19.1.3.1-1 J

3. The next PRA revision should reflect the PRllR desiep change i e., one instead of two heat exchangers.

} Closed - One PRIIR ltX is reflected in the PRA update. ] d' f NSD-N,RC-96-4662 2R07 NRR/SPSH 19.1 RAIOl $/24% 11ucter'Sancuts Closed RAls Related to DSER Open item 19.1.3 1-2 J ', q'. * ?C c/ 1. Westinghouse is requesting the extension of the testing interval, from quarterly to semi-annually, for the ADS stage I,2 and 3 mot v operated valves (MOVs) The FSAR states in 3 9 6 3 I that the ADS stage I through 3 vake exercise testing represents a risk ofloss of coolant and depressurization of the reactor coolant sptem if the test sequence is not followed Operator error during exercise testing of ADS MOVs (e g., failure to follow test sequence)must he addressed in the PRA. l Closed - Puential operator error during testing of ADS stages 1-3 leading to spunous ADS actuation is addressed in PRA update. l Page: 14 Tota 1 Records: 187

AP600 Open item Tracking System Database: Executive Summ:ry Dat:: 11/21/96 Selection: [DSER Section] like 'l9.** And (NRC Branch] like NRR/SPStr Sorted by item # Y l'em DSER Section/ Title /Descrileion (W) NRC - 5d No Branch Question Type Status Detail 12st Mod Date Resp Eng Status Status,e gaerr No. / IJr Date 2008 NRR/SPSB 19.1 RAIOI Wi1% Bueter!5ancaktar Closed NSD-NRC-964662 7 ,f, gg h -f [y4] ' /,Q rj,M S ( [ j-lRAls Reled 2 DSER Open leren 19.1.3.1-2 This item is administratively resolved. W e S=6an tl.12 resolution of these items will techntcally resolve this open item.More detailed RAls were sub by RAlf Supe rseded how *e c==**on= = t en-di .n d um and large tnCA. reponeo m mm ~... . me snaiya (% ,-__, data and associated bases) used to calculate ADS spuncus actuation frequencws and their comerdutions to the vario.as IJX'A initiating evese fmluesicies. / of/e l [ l Closed. RAI resporne issued. j 2809 NRR/SPSB 19.8 RAIOl yt1% Bueter/$ancaktar Closed NSD-N RC-96-4662 { 4g( fg / 1,j Q A'l 7 y g 3 7 'f. f ;( IRAls Related to DSER Open Itema 19.I.3.14 and 19 8114

• ~

This item is administratively resolved. More detailed RAls were submitted an resolution of these items will technically resolve this open item. Supersede ,,,,,,g ,,3 ;,,,; gg .-.uu ena is not migpeificant). h. l Closed. RAI response issued l 2810 NRR/SPSB 19.1 RAtot 93 % Bueter'5ancaktar Closed NSD NRC-946tt 7 RAls Related to DSER Open Itern 19.l.3 l-7 XI $ 4 v g f ~ I. Westingpiouse needs to correct several inconsistencies or provide an explanation indicating that the agparend inconsistency rewhed from a , Several entries in the "Speern Dependency Matrix" tables, at the end of each specific speem chapter, are inconsisters with the "AP600 Support Symem Interi;,..i. y Matrix

• table located in Chapter 5. Examples are:

- For the Passive Containrnent Cooling Speem (PCS). Table I 34 on page I 3-9 of the PRA. shows that IDS is the support sptem required to operate AOVs and MOVs. Ilowever, PCS-PCT in Table 54'on page 5-30 of the PRA does not show that the IDS sysseni is a support system. t For the Normal Residual llent Removal Speem (RNS), Table 174 on page 17-10 states that PIS s>wern provides manual actuation logic for pumps, MOVs, etc. Ilowever, RNS-RilR and RNS-RNP (Table 54 on page 5 33) indicate the FMS synem (not the PLS syvem) provides support. In addition, Section 21.4 2 refers to subsection 3.3 I ofreference 21-1. Reference 21 1 is the revision I fauk trees and there is no subsedien 8 3.1. The carect reference should be given. Resolved. The second and third items wdl be addressed in the updated PRA. Cloacd. Response provided by NSD-NRC-96-4628. v Page: 15 Total Records: I87

9 AP600 Open Item Tracking System Database: Executive Summay Datn 11/21/96 Selecties. [DSER Section] like *19.* And [NRC Branch] like NRR/SPSB* Sorted by Item 8 Q35 hem DSER Section/ Title'Deacnpaion ggd (W) NRC ~ ghgiIt*bOE* sgfed . No. Branch e--- Type Stem DWeil IJ8 Med D8' SWm SWm Emma No. / 12 Der A ped WE Obed NSD-NRC-96-4662 2sti NRR/SPSB 19.1 RAIOl gl$ eg, kI [ 2' bJ_d [. hf 098U lRA8-deII $5 3 fr p 's 1 ' C d.fe /v a ly T* solved. reSOI"* 1 tow w W% %dh*mWmW== I I g 389k gS rIIgyeggT IIggic1 M. the conetiom under which they willlw operming in the plant are sulmantially &fferem from those mi cumm generation nuclear t reams. For example, they will have to gen on dnnend under very low differemial preasures after long pmods of being held closed by fluid at RCS "{hi5 gte9$0g O9 the50 gte#S tempeistire, pressure and chenustry. In the revised PRA sutouttal the failure rate of the IRWST check va?ves was changed, as suggested in EPRTs Utility Requireniere Document, to accouse for "less than ideal con &tions* winich may exist at the time the valves are dennanded However, no dracussion is ,,cluded in the subnunal which shows thauhis diange addresses the faihn des apphcabilsey cecern for the IRWST check relves or for any other ye50D components. Please provide this infonnation and*cr perform sminivity studies to assess the inW ofchanges in failure rates of rie-irnpartant componens QY to mk. t l Closed. RAI response issued 3S% l 2012 NRRISPSB 19.8 RAIOI 5/24 % Bwiev'Sanedur Closed Action W NSD-NRCf6-4688 n.. 1 RAls Related to DSER Open Item 19.1.31-1 I ML F"'"_ { l. He staff was unable to faid in the revised PRA submittal a complete respome to DSER Open Item 19.l.3.1-11. Please prodde documentation of IAC failure data derived from Westinghouse data or idemify specifically where this information can be found f l Closed - RAI respome issued NSD-NRC-96-4688. Information was dracussed in meetengs with NRC. $(._, ( l [ 2813 NRR/SPSB 19.1 RAIOl Ultr96 Sancaktar Closed NSD-NRC-96-4662 c (, Qj ')

• p I 7

(( j /,. I,[; RAls Related to DSER Open item 19 f.3.1 13 .~ - -.. A w..,..-. - ,alvan. MOL factors teen Rewaxame 5 and 6 of FPRTs This item is administratively resolved. More detailed RAls were submitted and iom s a 6cfihevRD. nisi.n=chiowersianihe resolution of these items will technically resolve this open item. Supers eded iy*= 8M N=P aaa== fa shi' i= r'***d l by RAlf ' "' ""d i" Preneus PRAs. IChed-RAI respame imued j f 2814 NRR/SPSB 19.1 RAIot $/3.% Bwter/Sancakur Cleard NSD-Ny-96-4688 RAls Related to DSER Open hem 19.1.3.5-14 h,t t /*' 8.*4. ' l. He staff was unable to find in the revised PRA suhnuttal the beta factor, or MGL paramder, valoes used in calculating 4 - cause failure probabilities ofIAC hardware components (as requested in the DSER Open item 19. l.3. l-14). Piemme prodde this informatmn, includste sources and related docummtatioet in addnion, please prodde detailed documentation of the calculation of probabihties for the niost risk-imguwtars CCF events (in terms of both hemeline and focused PRA rnuits) related to IAC hardware --, - - - - i l Closed - Respame provided by NSIANRC-96-4688. l ? i i ~ i i { t Page: 16 Total Records: 187 6

AP600 Open item Tracking System DatabcSe: Executive Summ^ry Date: 11/21/96 Selectiott: lDSER Section] like '19? And [NRC Branch] likc NRR/SPSB* Sorted by ttem # Item DSER Sectum/ Title /Desenption (W) NRC No. Branch Quest' m Tme Status Detail test Mod Date Resp Eng Status Statua letta No. / Otr Date u 2298 NRR.3PSD 19.1 RAlol Sc4% Burte Treetarus Closed Action W NSD-NRC-96-4688 y RAI Related to DSER Open item 191.3 I 15 N Wua -

1. The staff was unable to find in the revised PRA submittal how the soAware conumm<suse failure pobahitrties were calculated The following statement is made (see pages 26-25 and 28-20)-

"The software common-cause failure evaluations are based on a enodel that incorpente: a number of factors that can afect the development and mytemmtation of software modules, This model yields a resultant software comrvm mode unavailabilrty of 1.1 E-05 failures / demand for any particular software mo&le, and a soflaare common mode unavaileN!rty of I.2E-06 failures' demand for soRware failures that would mensf-se themacives across all types of sonware nuddes derived from the same basic design pogram en a!! anlications

• The above staterrent does no povide adequate information to the staff to understand inw software failures were modeled in the PRA Please explain the "model* and the "particular software modules" you are refemng to in your statement. Also, please explain how the corrmon mode unavailabildies (f lE45 and 1.2E-06) were obtained.

l Closed - Response povided by NSD-NRC-96-46tt. l 2399 NRR.3PSB 19 1 RAIOI 50496 Burter/Sancaktar Closed p ig W 'NSD-NfC-96-4662 RAI Related to DSER Open item 19 1.3.5-16 V V'

l. h is not clear whether unscheduled mamtenance that could affect the unavaitabilrty of safety-related " passive" sptems is modeled in the PRA. For esample, it is mentioned (Table 9-5) that the normally cloed airqm ated valves in the Core Makeup Tanks are exercise 4ceed every three morahs Although failure unavadahihties are based on quarterly testing, which emplies that faulty valves will be repaired upon detectum, the valve unavailabehty due to such unscheduled maintenance is run nuwieled in the PRA (nerther a justification (ce not modelmg it is provided). This seems true, also, for seveial other systerra, such as the PRIIR and the ADS. Please address unsaeduled mai denance 'm the PRA.

l Closed - PRA updated as necessary. See RAI response g g l DAction W pSD NRe-964tS6 2900 NRR,3PSB 19.1 RAlot 1C 496 pRA.I NdBueter/Stevenmut Clonad RAls Related to DSER Open Item 19. l.3.2-15

1. The PRA irsh layout dranings of tie ~ **W and auxiliary buildings only. Please include layout drawinp of the manes and turbine budding.

} Closed Weeinghouse responded to this follow <m question in letter NSD-??RC-964tS6 (10/23/96). l NjD-NRC-96-4856 2901 NRR/SPSB 19.1 RAjo! IM496 pRA-l TlondBurter'Smensnn Closed w RAls Related to DSER Open item 19 I.3 2-15

2. The potential floodmg sources in each area are now given by system name. Please provide the maximum water available from end of these floodmg sources. For those areas where credit is taken for mitigation actions or drainage through the drain system, please also preside the assumed break flow rates.

l Closed - Westinghouse responded to this follow <m question in letter NSD-NRC-96-4856 (10/23.96). { l 2902 NRR/SPSD 19 i RAlol IW2496 PRA-ITimdBucter/Srnenson Closed Action W NSD-NRC-9(p4tS6 RAls Related to DSER Open Itern 19. l.3 2-IS =y>d

3. The SSAR (page 9 5-2) indicates that the fire suppression water sptem must be al4e to supply a minimum of 500 gpm for fire hoses plus the demaruf of any automatic sprinkler. Page 56-1I of the PRA states that fire hose stations in the Armex buildmg are assumed to dehver 125 ppm. Please novide an explanation of the difference between these values and if the assumption of a masimum 125 ppm instead of 500 gpm flow rate has an in pact on the result of the floodmg analysis.

l Closed Westinghouse responded to thie follow <m question in letter NSD-NRC-96-4856 (10/23/96). Page: 17 Total Records: 187

w AP600 Open item Tracking System Database: Executive Summ:ry Datn iI/21/96 Selection: [DSER Section} like '19.* And [NRC Branch] like NRR/SPSB' Sorted by Item # Item DSER Satim/ Title.T)escnption (W) NRC No. Ikanch Questum Type Status Detail last Mod Date Resp Eng Status StatM No / 1* Date i 2903 NRR/SPSB 19.1 RAlol IW24% PRA.lOnodheter/Stevenann Closed Amt SD-NRC-pt36 RAls Related to DSER Open Item 19. l.3.2-15 g ffg

4. Dom in the AP600 floodmg analysis are assumed to remain intact in their normal position (page 56-8). Due to uncestamanes in door loading and str-ngtIn, nn:I the awvement of pmannel, this assumption may be opeirnistic: that is, the awr may be open, w fail to remain cloacd, or the exw may be closed, or mi takenly closed by personnel, er ese to gwessure frorn the flood water it may are be pansrble to open or close a exw. Please ideredy the scenanos where the assurnption that the exws remain intact in their normal position nutigates the effects of floo&ng, and justify the -

, ~.a, that the door will remain intact in that position [ Closed. Westinghouse responded to this followa question in letter NSD-N RC-964856 (10/23/96). g g l 2904 NRR/SPSB 19.1 RAIOl IW24% PRA tCo.dhrter'Sanerman Closed 3asort U )!SD-NRC464856 RAls Related to DSER Open item 19. I.3.2-15

5. De flood Zones and Barnm Plans in the flooding riiA include a '+' symbol in&cating " WATER TIGIIT RDOR.1tOOF.* Picase clarify if this indicates that the rooms with that spnbol on a given ',evel have a watertigin floor, roof, or botit Some cases, assuming that both the floor and teof are water tight, result in inconsistencies between the Merent level drswings. If such a syvnhol does not exist for a room, has the possibihty of water running tlwough pipe and electrical penetrations betweat noors been considered?

j JClosed - Westinghouse responded to :8= - f,Jaowen question in letter NSD-NRC-96-4856 (10/23 96). ( l 2905 NRR/SPSB 19.1 RAIO: t&24% PRA l Mondheter'Stevensan Closed W NSD-N C-964256 RAls Related to DSER Open item 19. l.3 2-15

6. On page 56-10 of the PRA, *t. Assumptions enade about the Annex building," states that in Sation 3.4 of the SSAR, no creet is taken for Door drains.

In the referenced SSAR section on page 3 4-22 however, floor drains are dacussed and credited with routing water away from adjacent rooms Please clanfy this apparent Ascrepancy and identify what impact, if any, the clarification migle have on the PRA analpis. l l Closed - Westinghouse responded to this followen question in letter NSD-NRC-964tS6 (10/23/96). h] l 2906 NRR/SPSB l9 I RAIO! IN24% FRA lSondheter/Stewnson Closed att W NSD-NRC-964856 RAls Related to DSER Open item 19.1.3.215 [

7. Please justify the assurnption that l* line tweaks can be neglected in the flooding analysis.

l Closed Westinghouse responded to this fWlowen question in letter NSigRC-964856 (10/23/96). 2907 NRR/SPSB 19.1 RAIOI t&24% pRA-tBomiheter/Stevensaa Closed Act NSD-NRC-964856 RAls Related to DSER Open Item 19.1.3.2 17

1. The SSAR indicates that the fire suppression water system must be able to supply a minimum of 500 gym for fire hoses plus the demand of any automatic sprinkler. It further states that there are 2,2000 gym rated pumps and that gwessure switches are used to start the pureps to maintain full line pressure. When the S* fire line in Aruwx Buildmg 135'.3" North flandling Equigwnent Area Ruptures, two hours is allowed fiw the secunty guard and operators to mitigate the event before the 1 E DC bancries in Auxihary Building non-RCA 66'4* level would fail. Please identify andjustify the flow rate used to estimate this 2 lunar time intersal, and address the sensitivity of these flow rates on the flood MH DC power failure probahit ty.

} Closed. Westinghouse responded to flus follow-on question in letter NSD-NRC-964856 (10/23/96). l e Page: I8 Total Records-l87

r Y AP600 Open Item Tracking System Dat: base: Execidive Summ_ry Dat2: 11/21/96 Selectice: [DSER Section] like '19.*' And [NRC Branch] like NRR/SPSIY Sorted by item # Item DSER Sectionf TitleDesengeiost (W) NRC No. Branch Question T pe Status Detait last html Date p,,p Dig Status Status 3 g gener No. / IJr Date 2908 NRRSPSB 19 1 RAIOl IW2496 litA.IHandhrter'Stewrom Closed Action NSD-NRC-96-4336 RAls Related to DSER Open item 19.1.3.2-11 ~ I. De assunytion that human actions in the consol room credited in the intemal ewees models and thua e edited in the flooding analysis, are not seriously inyected by the flood is reasonable. Some human actiore cral ted in the internal event PRA ase, nmaeva actiors taken outside of the coserol rooni. These actims include CCN-M AN02, CVN-MAN 04, REG-M AN00, and TCH-MAN 02. Please wrify that the human actions which are perfarnied outside of the control room are; a) not credited in the nwulcis used in the flood analysis, b) not in an area inyected by the fload if they are used, c) or that the inyect of flooding on the prohahihty of successfully congleting the action, will be negligible. l Closed - Westenshouse responded to this follow-on questian in letter NSD-NRC-964856 (10/23/96) l i 2909 NRR/SPSR 19.1 RA!Of IW2496 PRA-l TinndBurter Stevenue Closed Action NSD NRC 96-4tS6 RAls Related to DSER Open hem 19.l.3.2-19 6 I. He floodmg CDF was quantified using approximately 2,500 applicable cut sets from the intemal events analysis A flooding event changes the failure I probability of many normally reliable conyonents to 10, and major changes to the donunare cut sets can be enmied. Please provide the results of the final flooang scenarios based on quantification of the original logic models, na on the reduced set of 2,500 cut sets l } Closed. Westinghouse responded to this followen question in letter NSD-NRC-96-4856 (10/23<96). ) l 2910 NRR/SPSB 19.1 IWOI 10r2496 l'RA-t 71ondBucter'Sammnn Closed Action NSD-NRC-96-4856 RAls Related to DSER Open item 19832-20

l. Please wrify that, when selecting which initiasma event to use in Table 56-5 (e g scenano I vs. 2 ; 3 vs. 4 ; 5 vs 6 vs. 7 ; etc ), identical compnners/ system failures were used and only the event trees were chariged to identify the most conservative IE to use.

Unlike the scenanos in the selection process above, Scenanos 15 and 16 are quantified using the same initialmg evere and initiatint;ewre frequency, but 15 has a much wider geopagation and many more component failures. It is not surprising that sequence 15 has a greater CDF, if 16 is intended to model the partial flood event - ,, successful actions to prevent flood propagation to the auxiliary building, it should have a higher initiating ewnt frequency. Please clarify the reason for evalualmg both scenenos 15 and 16 in Table 56-5. l Closed - Westinghouse responded to this follow-on question in letter NSD-NRC-964836 (10'23.96). l 2918 NRR/SPSB 19.1 RAIOl IW2496 PRA-I TlondBucter/Sammon Closed Action NSD-NRC 96-4256 RAls Related to DSER Open Item 191.3222 4

1. Due in large part to assumed human mitigating actions, the frequency of flooding the non-RCA Auxiliary building 66*-6" level and failing the 24 hour l IE DC batsmes is estirnated to be 4 4E OS/ r Smce this appears to he the lowest level in the plant, floodmg everes caused by check vahe failures and 3

I hackflow tirough the drain 33 stem may occur with comparable a higher frequency. Please gwovide a discus 6 ion indicating why drainage to this lowest levelis expected to be less frequent than 4E-OS/3t l Closed. Westy. se m.,-.C to this follow-on question in letter NSD-NRC-96-4236 (10/23/96). l j 1 t v l Page: 19 Total Records: 187 i t d

a AP600 Open item Tracking System Database: Executive Summ:ry Datz: 11/21/96 Selection: [DSER Section] like '19.** And [NRC Branch] like NRR/SPSIY Sorted by Item # Item DSER Sectumf Title.1)esenption (W) NRC ) treer No.1 No. Branch Question Type Status Detail tast Mad Date Resp Eng status Status IJr Date 2912 NRR/SPSB 19.1 RAIG 1072496 PRA.1/FlandheenStewnwm Closed Action, N ' NSD-NRC-96-4:56 ) RAls Related to DSER Open item 19.l.3.2-22

2. The FRA states that the site is to be chosen such that the annual frequency ofoccurrence of a floo&ng evem is less then 19E 06 year and thus extemal Goo &ng need not be evaluated The staff notes that the IE DC banery rooms are at 66'4"(the lowest Icvel) in the non-RCA y of the Auxiliary buildmg The IE DC Buses are at 32'4",one level higher. Grade levelis 100'so both areas are below grade. Conseguemly.extm m asures would be necessary to prevent external floo&ng frown failing all I E DC and preve: Wing any foreseeable recovery Chapter 2, Site Charactenstics, et 1w SSAR ascmses the 10E-06 per year mecria on page 2-2, but appears to esclude external floods from consuleration under this cntma. Floods are &scussed separately on page 24, where informetkm collection requirements are discussed tot no cntena are givert Please explain why an external flood will not lead to

• severe consequences", or identify whese the mamanum acceptable annual frequency of 10E4 for external floods will be addressed in the AP600 documentation.

l Closed - Westmghouse responded to this follow-on question in letter NSD-NRC-96-4856 (10/23.96). g7(. [ l 2939 NRR.SPSB 19.1 KAIG IWsw E%eter%IM Ciceed Artitsrr% NSD-NRC-96-4680 Shutdown PRA f(dlow<m question to DSER OI 191.3.3-I: g] 7{g. g A /O /k Open item 19 l.3.3-1 requested Westinghouse tojustify the low human error rate for inadwrtent drauung of reador vessel anventory though the Normal Residual IIcat Removal (RilR) system In respome Westinghouse quantified the IAchhood of the operator overdraining the reactor coolant system dunng drain down operations to reach midlog con &tions. Westinghouse also quantified the lachhood that a tDCA could occur by inadwrted opening of Normal RitR valve V024. The staff needs the following information to conclude that the frequency ofoverdraining the reactor vessel to reach midloop con &tions is on the order of E4 per year, whkh is much lower than current operstmg expenence Westinghouse should use operating experienct to determine the a. frequency of the operator inadvertently overdraining the RCS during midloop, or justify that current operating experience is nm applicable by descrit ing any AP600 design improvements over current plants. b. Westinghouse needs to add more information in the shutdown PRA about the available level instrumentation ering the drain down process. A description of how the pressuriier wide range level instrumentatica is connected to the RCS would be helpful. c. Westinghouse needs to clanfy in the PRA how the two het leg instruments are cormected and clanfy whether they share corranon reference legs. d Westinghouse needs to document in the PRA the basis for the beta factor of 045 for the hot leg instrumems. This value is nm listed in Chapter 29 or Section 54.7 of the PRA. For drain down scenana 2. Westinghouse needs tojustify the laelihood that the air operated valves fail to close on demand Westinghouse needs e. to (I) documem the testeng interval for these valves and (2) calculate vahe unavailability using ((starmby failure rate)*(testing intervaly2) or a demand failure rate (such as ! E-3 listed in Table 54-58). l Closed. Response prodded by NSD-NRC-96-46RO and revision I of RAI response NSD-NRC l Pese: 20 Total Records: 187

m AP600 Open Item Tracking Systen Database: Executive Summ:ry Date: 11/21/96 Selection [DSER %ction]like'19.*' And [NRC Branch]like NRR/SPSB' Sorted by item 8 Item DSER Sectumi/ Title /Descntwinn (W) NRC i No. Brandi Qaention Type Stames Detail im Mal Dane Reap Eng Stansa Status 12eerNo. I tar Date 2940 NRR/SPSB 19.1 RAtOf S196 Hurtava!!are Closed AssnwrW NSD-NRC-96 46s0 I Shathusa PRA follow-on question (DSER Of 19.l.3.3-2): 4 / CLO5C >J With respect to Open lieni 19. I.3.3-2, Weminghouse responded in Section 14.3 2 of the FRA that t to 350F and 400 guig is negligible --, d to hnecold shutdown and midionpNennel flange opershons. In anctson 54.3.2, W - _ _ justifies this assuergition based on 1) the cool down pmod to hat shuthwn of 350F and 400 psig lasts only eight hains, and (2) all mitigstag syneenis available when i the reactor is at power are available except the accumulators. In order for the staff to conclude that this shutdown period does not need to be quasertatively evaluated, the staffis eding Westmghause to: Modify this argisment to indicane that the risk is low corgered to the aim risk The argianent alwt Westinghaisse gave exa not directly lead a to the conclusion that the core damage risk is low compared to the rid freen harcold shutdown and nedloop/ vessel flange operstaans. b. Clarify in Sedian 54.3.2 of the PRA if all actuating signals that are available me full power are also available duringihis time period In Table 54-2,it would he helpful if an additional column was created for full power operation to allow for a simple comparison of available signals. c. Document in Section 54.3 2 of the PRA and Table 54-8 if any maintenance can be perfanned on any system during this period Document how these snaintenance assungeions will be met (i e., Tech. Specs, meninistrative coeurols, etc ). l Closed - Revonne provided by NSD-NRC-96-46SO. l 2941 NRR/SPSB 19 8 RAlot S1 96 Buciava!! ace Closed AnamarW NSD-NRC-96-4680 Shutdown PRA follow-on question (DSER OI 19.1.3.3-4)- ( Q g In reference to open item 191.3.3-4, the shutdown PRA still does not clearly identify when automatic injection is available from the IRWST and when only manual injection is available (i e., &sring draindown to midloop conditionsk in Section 54 2.5 of the PRA, the PRA states,"The low has leg level signal, used to monitor and control the reactor vessel water level dunng the drain down of the reactor coclant system for the nedloop/ vessel flange shutdown phase,is available." The PRA gnes on to state,"This iratrumentation autornatically actusnes the IRWST MOVs on low level & wing the midloop/vesselllange shutdown phase? Ilowever, the staffidanified that in event tree RCS4)D (overdraining of the RCS during draindown to mid-log), o.Jy rnanual actuation of the IRWST was credited. The IRWST success criteria summary for this evere tree (IW2AO and IWRNSlasted that there were no automatic injection signals. The staff also identified that following a loss of offsste power without grid recovery, autosnatic IRWST injection was not cred ted. To resolve this 6---.a7, the staffis asking Westinghouse to: l Dncument in Section 54.2.5 of the PRA ( Actuatmg Signals and Speems Available) when IRWST automatic injection is available and when ordy a. manual IRWST injection is available during medlonpNessel flange operatiost b. Document in Table 54-2 (Speems Availability and Actuating Signals Type) when IRWST autornatic in,ection is muitable and when only manual IRWST injection is available &aring nudionpsessel flange operation. Document in Table 54-2 for each available actuation signal what instrumentation is used to deliver the signal (PMS and'or DAS) [ c. l Closed - Respome provided by NSD-NRC 96-4620. l Page: 21 Tolet Records: I87 I

I s AP600 Open Item Tracking System Detsbase: Executive Samsmery Date: 11/2t/96 Selectims lDSER Section] like *19? And [NRC Hranch] like NRR/SPStr Sorted by item 8 l / Insm DSER Sectionf Title /Deacnytion (W) NRC / No. Ihanch Quesnoon Type Semeus Detail tant Mod Duse Resp Eng Stasma Stasua see No. / 12 Date 2942 NRR/SPSR 19.I RAlot 51 % Bueterwdtwe Closed ion W NSD-NRC-96-4680 Slusadown PRA followwwi questeen (DSER Of 191.3.34): U In reference to open itens 19.1.3.34 regarding shutdown unmineenanm, the staff asked WestisWoouse to documnant all - aannytiam and pmide l cross <eference to the SSAR. Westinghnuse responded by clearly docunneneing testing and aimenernanz assungeions for spedic syinans in TaNe 54-8. In addition, Westinghouse stated that no test and enaintenance activities will be conex 1ed airing neuNoop/vammel flange cmndeions (Section 5410 2 of the I PRA). Ilowem, the staff found that Westinghaisge povided no cross references to the SSAR. The staff also concluded that maintasung equipniese avaitahiley (particularly the IRWST) esring shutdown is necessary to achscw the low shusdown core daninge frequency esiinisses. Therefore, the staffis requesting Westinghouse to-l State in Table 54-8. the snaiseenance assumptions indiviesatly for PMS and DAS. Justify and docunirse in the PRA liow these snaiseenance a. assumpeions will be met (i e, Tech Specs., etc ) b. Justify and docunine in the PRA liow each maiseenance assunytion for each speern in Table $4-8 will be niet (i e.. Tecit Specs., etc ) Justify and docunnent in the PR A how the requirement for no test and meineenance activities esring nudlonp' flange operation will he met (i e.. c. Tech Specs.,etc.) l d. Defwie and docunient the assumed " allowed" time to return to a filled conditiori given a Narnial R11R congsonne failure &aring midlomtessel flange operation Document how this

• allowed" time will he niet (i e, Tedt Specs, etc.).

e. Clanfy and docunient in the PRA if the " Normal RHR component failure * &ning rrudlanpliange operation includes Normal RHR support f speenis such as CCS and SWS. l } Closed - Response provided by NSD-NRC-%-4680. l l 2943 NRR/SPSB 19.1 RAICI 11 % RorterNative Closed Aseems W NSD-NRC-96-4680 l Y'A .L \\ l[ Q, V 720 286 The staffis requesting Westinghouse to document in the PRA what AP600 auxiliary and passive speems were exarnened to idersify shutdomin [ initiating evenes (section $4 2.1, p. 54-2) and the resuks of this evaluaten. l Closed - Response povided by NSD-NRC-%-4680. l 2944 NRR/SPSB 19 I RAIOl 11 % Burierwdtwe Closed Aasias4 NSD-NRC-96 46R0 Sb'***** LAl Q f - ] 720 287 The staffis regnesting Westinghouse to explain the screenmg process in more detail (Section 54.2.4 p. 54-4). Sewal screeneng cnteria are I nientioned. Ilowem, the staff would hke Westinghouse to docuenent in the PRA how each of the *at power" initiating ewses was screened out. [ t l Closed - Response prmided by NSD-NRC-%-4690. l 2945 NRR/SPSB 19.1 RAIOt 11 % ButterWallace Closed ( Action W SD-NRC-96-4680 3 Shue&mn PRA-V i [ 720.288 11 e staff nyees that leases c(Nonnel RIIR &nring refueling are e9ected to have a negligiNe addeion to the total core damage frequency i (Section $4.2.4 of the PRA). Ilowever, the concluding statement in that parayaph mentions all lommes of water inventory rasher than just teil off ( Weeinghouse sieeds to evaluase and docuenent in the PRA the pntessial for LDCA and drasning evenes applicalde to the refueling niode f l Closed - Regponse povided by NSD-NRC-%-4690. l f I Page-22 Total Records: 187 i i

AP600 Open Item Tracking System Database: Executive Summary Date: IU21/96 Setuties [DSER Section] like *19 C" And [NRC Branch] like NRR/SPStr Sorted by Item f Item DSER Section/ Title /Desaigeion (W) NRC = No. Branch Question Type Status Detait last Mod Dese Resp Eng Stama Stahas, (etter No. I lir Date 2946 NRR/SPSB 19.1 RAICE 5.1 96 Bweervaltace Classal pD-NRC 94680 RAls Related to DSER Open Itern 191.3117: Mh8 i I. In page 30-2 of the redsed IIR A it is stated: s "Because of some depee of uncertainty in the data, in tans ofestimates for human erter prohahilities, it is onen useful to perform a acnsitivity analysis of the operator actions, during which the estimated human error pahabihties, stress levels, dependency levels, or other human perfannance factors are speematically changed to detemune the effect on the human relialulity analysis resuhs." He staff ayres with this statement but could not fmd such semitivity analpis in Westinghouse's submstants. Such sensitivity analysis, combined with usights from the importance and uncerteinty analyses, would he ver) helpful to undentand the planrs tolerance of human errors and to decide which (if any) human actions require more detailed analysis. l Closed - Response novided by NSD'NRC-96-4680 l 2947 NRR/SPSB 19 I RAIG $1% RwterWallu Closed SD-NRC-96-4620 a RAls Related to DSER Open item 19 1.3.!-17. j 2. Several operator actions modeled in the ATWS evem tree are required to be performed in a very short ti ne. For exangle: (a) ATW-MANO3 (manually trip the reactor through the PMS in one minute), (b) ATW-M AN04 (manually trip the reactm sough he DAS in one minute, giwn that an t cartier attenyt to trip the reactor tiuough the PMS fails), (c) ATW MANO R (manually step-in control reJa in one minute, using the Plant Control Splem, given that carher aneng4s to trip the reactm ilwaugh the PMS r r DAS fail). These alwee actions have the same " time window" of one minute, defined in page 30-8 as the time froen when cues are prodded to the tine when spann failure is expected af no operator ac* ion is taken Westinghouse estimated that approximately one niinute is needed to perform lnth ATN-M AN03 and ATW-MAN 04 (30 seconds each) t Sinularly, Weeinghouse estimated that approximately one minute is needed to step-in the control rod s (ATW-MAN 01) to prende " sufficient

• negative reactivity so that openmg of the pressuriser safety valves can pevem RCS pressure from exceedag ? 200 psig. Pleew provide the following mformation What is the " net
• time wmdow to manually trip the reactor through DAS (action ATW-mad 4k given that ehe attenyt to manually trip the a.

reactor through PMS (action ATW-MANO3) fails? What is the actual time needed to perform this action? What is the slack time for ATW-MAN 04 assummg that this actim follows an attempt by the operator to manually inp the reactor through PMS (action ATW-MANO3) and failed? Ilow were _,,-- evaluat d7 Please document your response by refening to specific suhtasks and analpes and by stating cicarly your assumptions, b. What is the " net" time wmdow to manually step-in the control rods (action ATW-M AN0 l k given that the aLemges to manually trip the reactor I through PMS (action A1W-MANO3) and threugh DAS (action ATW-MAN 04) have failed? What is the actual time needed to perform this action? What f as the slack time for ATW-M ANOI assunung that this action follows the attempts by the operator to manually trip the reactor through both the PMS (action ATW MANO3) and the DAS (action ATW-MAN 04)have fa. led? Ilow were in..L1 evaluated? Please document your response by referring to i specific suhtasks and analpes and by stating clearly your assumptions. 6 Ilow were "methanical fauks," such as bmdmg ofrods within their channels and red drive nicchanens failing to disengage, modeled in the l c. AP600 PRA? d. Westinghouse esimated that approximately one minute is needed to step-in the control rods (ATW-MAN 01) to provide " sufficient' negative } reactivity so that openmg of both pressuriser safety valves can prevent RCS pressure from exceeding 3200 psig. Is this true ewn when an advene" moderator temperature coefficient (MTC) exists, such as at the beginning of fuel cycle? Ilow is this noodeled in the ATWS event tree? Please podde calculations of RCS pressure for the tuniting transiew (e g.. total loss of feedwater without tutbine trip) assunung early core life MTCs. Ilow was the l failure ofone safety valve to open modeled in the ATWS event tree? l Closed - Response provided by NSD-NRC 96-4680. l f i r r Page: 23 Total Records: 187

l ( AP600 Open Item Trackiat System D:-.tabase: Executive Summ:ry Dat : II/21/96 l Selection: [DSER Section] like *19.*" And [NRC Branch] like NRR/SPSB' Sorted by item # l i Etem DSER Section/ Title-1)escription (W) NRC No. Ikanch Quessim Type Status Detail Imt Mod Date Resp Eng Status Status, teace No. / IJr Date 2948 NRIUSPSB 19.1 RAIOt st% lbeter'wattare Closed NSD-Njc-96 4680 RAls Related to DSER Open item 19.l.3.1-17; 3. Sewal assumptions shout " time wmdows," used in the llRA, are not clear to the staff For exangle, a " time wuew"of 30 nunutes is assumed for events LPM MAN 01/ LPM-M ANOFI PM-M AN07 (opnator failure to recognize the need for RCS 1, M,-4 A 30 nunute " tune window"is also assumed for event ADN-MANOI (operator fadure to perform RCS depressunration, given LPM-MAN 014 PM-MAN 03tPM-MAN 07 success) Does this iryly that the total "tirne window" fiw depressuriring the RCS (i e. recognirmg the need for 4, 4, and manually actuating the ADS)is one hnur? Does the 30 minute " time window" for tad IfM41AN01 irgly that task ADN-MAN 01 (aduale ADS) will not be successful ifit is initiated after 10 minutes, even if the estanated actual time to complete task ADN-M ANOI is 20 minutes? Is it true that the need to actuate ADS has twen diagnosed when the 30 minute " tune window" tor task ADN4f ANOI begins? Westmghouse respmues to same questions are also needed for the " time window" of 22 minutes fiw everas I.PM4f AN02UM4t AN041PM-MAN 02 (operator fadure to recognize the rued fbr RCS 4, W. durirg a medium or mtennediate IDCA)in comhmation with the 30 mmute " tune wmdow" for ADN4f ANOI. Please explairt } Closed - Response provided by NSD-NRC-96-4620 l 2949 NRR/SPSB 19 I RAIOl 5/3 % BucterMal? ace Closed W D-NRC-96-4620 l RAls Related to DSER Open item 19.I.3.1 17. 4. The " time wmdow* estimates used in the IIR A, could be significanaly affected by the various thermal 4ydraulic (T-il) uncertainties associated with passive system T-II modeling Do the " time wmdows" assumed in the IIRA accoure for T-Il uneartairaies? Please explain how the issue of T-II uncertainties and their potential impact on " time windows" has been a&lressed, or mit be addressed, in the llRA [ Closed - Re pense povided by NSD-NRC-96-46t0. l 2950 NRR/SPSil 19 I RAlot 11 % Bactermaliace Closed W SD-NRC-6-4680 RAls Related to DSER Open item 19 l.3.1-17. T~ 5. Here seems to be a conflict between the operating philmophy as documented in the SSAR and the operating philosophy as nmdeled in the PRA The PRA states that the operator does not need to do any significant knowledge-based diagnosis and decision making (operators will only need to detect alarms, ed cations, etc., and then will be guided by the symgtom-based pocedures). On the contrary, in the SSAR (e g., pages 18 8-14 and I* 6-7)it is stated that operators will be thinking ahead of the plant. This irglies that the operators will not just be deta1ing information and then acting, but that they mit be ponctive. These two operating philosophics requere a very diff' rent !!RA model Operating experience has shown that, even when "spegtomatic" e pace & ares are used, operstars do still &agnose and, in fact, will circumvent Facedures, skip ahead to solutions (which Westinghouse plares also allow) when operators know what the event is. This is modeled best by Table 20-3 of the llRA llandbook which includes perceytion, discrimination, interpretation, diagnosis arvi fust level decision making. Please respond to these comments. l Closed - Response provided by NSD-NRC-96-46t0. l 2951 NRR/SPSB 19 I RAIOf 51 % BucterMallace Closed 3-NRC-680 RAls Related to DSER Open Item 191.3.1 17: 6. In the IIRA quantification cre&t is ellen taken for separate recovery actions by the senior reactor operator (SRO) and the shift tedriical addsor (STA). De AP600 IIRA is assummg a very low degree of dependence between recovery adiers for a single sultask. One would argue that comrmm operator training, communication and short tune inservals prodde strong sources ofig..:...;y between operators. For this reason, the TilERP methodology does not allow to take cre&t for more than one reco try and only if there are formal diecks. Given that the AP600 PRA credits recwery for every action by the control room crew will there be formal checks in the pocedures for each step for both the SRO and the STA7 in adlition, according to the IIRA llanhook, the "one-of-a-kmd checking with alert futors" recovery probability of 8. I E-2 is agplicable to normal operstmg con &tions, only-Please explam. l Closed - Response provided by NSD-NRC-96-4680. l Page: 24 Total Records: 187

AP600 Open Item Tracking System Datattse: Executive Summ:ry Date: 1I/21/96 Selection: [DSER Section] like '19

• And [NRC Branch] like NRR/SPSIY Sorted by Item 8 Item DSER Section/

Title /Descnytion (W) NRC r No. Branch Question Twe Status Detail Last Mod Date Re p Eng Status Status treter No / In Date 2952 NRR.TPSB 19 i RAIOl $1% BuctaM'a!! ace Closed NSD.NRC-96-4680 h A RAls Related to DSER Opne item 19.1 31 17; 7. The passive nature of the safety systems in the AP600 design, combined with the reliance of the design on advanced istrumentation and control (IAC), has the potential to change the operatoi's interactions with the plard (as cargared with operstang plants) enring accideve cormhtsons. In mahtm operators may ireentionally chnoac to circumvere proceesres to avoid economic e,+.m (e g, avoid contairunent nucanung, avoid thermal shnd ese to overcoolms w avoid mater hammer) Please perform at least a qualitative evaluation oferrors of commissi<m that could irgact the performance and i reliabihty of the plare during accedern conditions. This, also._.a..id by EPRI in its ti lay Requirements Documere (URD), is needed to idnsify t poteveial errori of comrmssion (and their consequences) and ensure that appopiate design certification and operational

• requirements
• will be used to prevent such errors.

l Closed - Response provided by NSD-NRC-96-46to. l 2953 NRR/SPSB 19.1 RAIOl 7/21.% Burta Waitare Closed NSD NRC-96-4620 RAls Related to DSER Open item 1913.5-17; 2 Westinghnuse needs to evaluate the uncertairwy associated with human error prohabitay (IIEP) estimates (e g. present the if RA resuks a terms of a mean value and an associated error factor) l Closed - Response prodded by NSD-NRC-96-4680 and the uncertanwy analysis (PRA Chapter 5 I) was subrrutted. l 2954 NRR/SPSB 19.1 RAIOl 03 % Burta Wallace Closed NSD-NRC to RAls Related to DSER Open Item 19 l.3.1-17; 9. Is evein RNS-V024 (operator opens MOV 024 to replerush the IRWST inventory using the NRilR purnps) included in the redsed PRA models? If yes, mas its prohmbility revised to address DSER concems? Please explairt l Closed - Response provided by NSD-NRC-96-4680. l 2955 NRR/SPSB 19.1 RAIOf $1% Burta W an Closed NSD-NR 96-4680 RAls Related to DSER Open item 19 l.3.1-17; p

10. The cues for I.PM-MAN 02 (failure to recognire the need for RCS depressurization) and CMN-MAN 01 (failure to actuate the CMTs) are identical (see page 30-26). Could the operator fail to diagnose the need fbr CMT actuation believing that only depressurization is needed? What meuld the operator de fint? Ilow does this affect the estimated

• actual time
• and the diagnosis of either one of these eveves?

l Closed - Response provided by NSD-NRC-9646RO. ] 2956 NRR/SPSB 19.1 RAIOt is% PurtaWallace Closed M NSD-NRC-% 80 RAls Related to DSER Open item 19.13.5 17; i 1. The " actual time" it mill take the operator to actuate the CMTs (evera CMN-MANO R ) was estimated to be approximately 20 minutes Aning a small IDCA and only 8 nunutes during a meeum II)CA (see pages 30-26 to 30-28). Given that the operator mill have to follow the same procchsre and perform the same sulwasks in both cases, what is the basis for the much shorter " actual time" daring medium IECAs? ] Closed - Response provided by NSD.NRC-96-4680. l Page: 25 Total Records: 187

AP600 Open Item Tracking System Datab:.se: Executive Sumntry Date: 11/21/96 Selection: [DSER Section) hke 'l9 ** And lNRC Ikanch) hke NRR/SPStr Sorted by item 8 Item DSER Section/ TiticVesenption (W) NRC No. Branch Question Twe Status Detail Inst blod Date Regp Eng Status Status g,cer No. / lir Date 2957 NRR/SPSB 19.1 RAla 54 % BacterWa!! ace Closed SD-NRC-96-4680 RAls Related to DSER Open Itern 191.31-17: 12 hfukiple alanns, close in time, could impact event &agnosis. By refening to the most risk important Imanan adions, as detergruned by the irrpnetance analpis, please discuss how multiple alarms has been analyred and accounted for in the IIRA models. l Closed - Response provided by NSD'NRC-96-46R0. p T l ~ 2958 NR R/SPSB 19.] RAICI S4 % Buctervalke Closed Action W D-NRC-96 46R0 [ Shutdmm PRA IIRA: 1. The time wmdow far operator action RCS46 ANOD2S (detect failure of automatic closure of air-operated valves CVS-V045 and V047 and manually close them) is very small(5 minutes). The shut &mn PRA, as the PRA for power Teration, states that the operator does not need to do any sigraficare knowledge-based diagnosis and decision making (operators will only need to detect alarms, indications, etc., and then will be guided by the synptonehased pace &sres) Operating experience has shown that, even when "s3mptomatic" procedures are eased, operators do still &agnose and, in fact, will circumvent procedures, skip ahead to solutions (which Westinghouse plants also allow) when operators know what the event is. This is modeled best by Table 20 3 of the IIRA llandbook which includes percepion, escriminaticei, irwerpetation &agnosis and Grst level decision making Please respond to these comments and re< quantify the pohabihty of event RCS-ht ANOD2S as necessary / h l l Closed - Response provided by NSIANRC-96 4680 ] 2959 NRR'SPSB 19.1 RAICI 3 % BurterWallace Closed Action W SD-NRC 96 4620 Shutdown PRA IIRA: \\ / 2. Regardmg DSE R open item 19.13.31, Operator action, RIIN41 ANDIV, repesents the hkelihood that the operator would inadwrtently drain reactor coolan: into the IRWST through Normal RllR valve V424. The prohalwhtv of RIIN-EtANDIV was assigned a value of IE-3 in Chagter 30 of the PRA The correspondmg task ana!ysis for RifN-ktANDIV evaluated the likelihood that the operator selects the wrong control to align Normal RllR and fails to close the & version path This pobabihty was then used as a frequency (I E 5 per year)in the shut &mn PRA to repesent the frequency of overdraining the Normal RilR spiem through inadwrters openmg of V-024. This frequencv is very low and suggests that a pipe rupture of Normal RilR is more IAcly than an inadvertent draindown everd. Please search for otfrr potertial reactor coolant drain down paths that the operator could create, considenng that the reactor coolant sptem may a. be pressurized (i e. during hot mustdown) and &xumera this searth in the shutdown PRA. b. The task analyses for R flN41ANDIV only evaluates the likehhood of the operator seleoing the meong control (V424) to abgp Normal RIIR. The staKbelieves that other cond sions could create an opportunity to create this drain path (i c. valve testing, etc.). Please use operating expenence to e obtain a frequency ofinaJvertere drain down events or justify in the shutdown PRA why operating experience is nit applicable. Please explain why ate failure gwohabildy of RifN4f ANDIV is used, also, as the frequency ofoverdraining the NRIIR swtem. c. d. Same time win &ms are used in the task analpis of ewne RIIN-AN DIV for both pressurized (i e., het shut &mn) and non-pressurired (i e cohl shutdown) con &tions. A draindown event when the RCS is pressurized would &ain the RCS faster than an event with the RCS non-pessurized This may require separate analysis of same scenano for hot and cold shutdown con &tions, respectively. In adation, please povide the following & tails in the shutdown PRA for each potertial drain path: i) Define in the shutdown PRA mhat the term " time window" rnesns for each scenano (time to core damage, time to core uncovery, etc ) ii) Define in the shutdown PRA uhat the term

• actual time" means for cath scenano ii) Develop time windows considenng twwh pressarired and non-pressurized con &tions.

l Closed - Response provided by NSD-NRC 96-4680. Revised response provided in NSIFNRC-96-4803 dated R/26/96. ] Page: 26 Total Records: 187

AP600 Open item Tracking Systemi Datab:se: Executiv2 Senime:ry Detz: 11/21/96 selection [DSER Section] like '19.* And [NRC Branch] hke NRR/SPSir Sorted by item # j leem DSER Sectumi/ Title /Descnpsumi (W) NRC No. Brancti Quasemus Type Sameus Detail Lam Mod Dane Resp Eng Stsaus [E \\ Immer No. / IJr Danc [ ( ActimsW f NSD-NRC-96480 f 3007 NRR/SPSB 19.1 RAIG S1 96 BurierNellere Clemed 720.303 The following gaessions pertain to elesadsum operatsen with the RCS open. According to the SSAR Chagner 6. Stages I,2, and 3 of ADS are nianually opened PIUOR to inshmeng RCS dreesdman operathus to nudoop r s cenetions. However, no infornimaion is provi&d in the shutdown PRA as to when ADS is opened prier to drain dmen opernascus. Please doceness in the shutdown PRA how this SSAR assungeion will be niet (i e Tedt Specs., menin controls, etc.)? b. Disring RCS esindown operation with Stages I,2, and 3 open,if Normal RilR coolms is lost, the operaner has to manually initiate gravity injection I from the IRWST. If the operasar actusses gravity injection AFTER the RCS begins to boil, could surge hne flooeng occur and cause pavey injection to f stop7 The senf reepseses Westingliouse to provide analpes wnfying thee surge line flooeng is not a problem, nasunung any RCS level. p [ ] IClaard - Respanne provided by NSD-NRC-%4680. f _ f NSD-NRC-964680[ ( 3008 NRR/SPSB 19.1 RAIG $496 Burservenere Clemed 720 304 ~ " ",,WM In the sensitivity usedy for test and nomintenance outages derisig drained = " . only electncal., Wie AC and DC power, were i ancheded. The seatrequesas Weningliouse to evahsase throingh sensitisity usu&cs the inyect afinuctisesled - e of ' - frnen the PktS l system Nonnel RilR, and Normal RifR's support speems. [ i l Closed. Response provided by NSIANRC-%-4680. _/ ' / l l Closed ( _ fSD-NRC 96-4680 Action W 3009 NRR/SPSB 19 I RAIG I'2896 BurwrNattem In the PRA, snany of the potesdial baron elution initiating ewnts are discussed and dropped scanL Howewr, since the shutdown core damage frequency is 5.5 E-8 per year, the staKcannat conclude that these initissors how freepsenews less than this value. Based an previous i screening calculations and the Surry shutdown PRA, the staKrequeses Westingliouse to apsentify the ibilowsng boren elution esents idreWified in the l AP600 PRA: i Chemical and Volume Control Speem (CVS) eering hrt shutdown using the DILUTE nonde of operassaut n. b. CVS wseer injection and baron &lution during plant startup. CVS water injection and baron &Iunion following a loss of offsite power event, with - ' aartup of the reecent coolant pungs. c. s S_.sor tube _.ws. m_fer o,w.ser -om er p, r, - i Closed. Resposee provided by NSD-NRC-96-4680 and by Rev. I of RAI provided in NSD-NRC-96-4739. Revision 2 respannes provided in NSD-NRC-96-4803 dated s'26/96. t I ? O t L l i i ? Page: 27 Tolet Records IB7 I I )

AP600 Open Iteen Tracking Systein D:tattse: Executive Seinsurry Date: 11/21/96 Selection- [DSER Section] like '19.** And [NRC Branch) like NRR/SPSIF Sorted by Itent # l I (W) NRC hem DSER Sectianf Title'Dearnpteam I No. Brancit C^ Type Stasma Detail Ims MedDaar Resp Lig sisans Stams gjeer No. / IJr Dane 3080 NRR/SPSB 19.1' RAIO MW6 Eh=www.tle Clamed Action W NSD-NRC.96 4600 I 720.306 The PRA clearly senses that containnues iseryny is snaintaard eming medss 1 IlmeisWt 4. However,ilme seams ofcessamuneue ewing ames 5 and 6 is unclear in the PRA(Sation 54.2.5). The PRA maars thss eming saidkup operation, c-*= "clenwe"is " However, midoop w - is l f anly a suheet of shutdown operations in minde 5 with the RCS epen Also, the term closure" is nas defuissL line stafInsuunise that "clanse* is ddlesne frcan: inseyey The statis concerned that the resuhs of the PRA do not include the risk impact of a pnessenally open - given a care daninge evese daring mode 5 The snaff nents this information since eveses acnunne ming nudionp/wsnel flange aparation aceeine far over 90% elthe shundown case damage i e frapnency Therefore, Weminghause is snynessed to provide the following information in theameaan PRA: Westinghouse is sapsessed to dansenent in the PRA how she rapsiranene for. merywy will be maintaand during Modes I-4 (i e Tatt s. Specs, a4nin. caserols, etc.). b. Weeinghaisse is sapsessed to document in the shundown PRA the status o(creamininese eming anid skuedawn (made 5) whsst the RCS is congleerly { issact This explanesian should include the staeus o(the., and pennnnel haecties, penetrations for eperating systeens, and :, _y ensensament and elatncal penetrations This explanesian shaisld aho desenhe the nyerator's abihty to claar contauunese stiauld a core damage event ocasr. i Weainghouse is requested to dansment in the PRA how these assismpeinns will be met (i e. Tak Specs., senia controls, etc.) I Weminghouse is requested to danunne in the shundown PRA the status of comesinrnese sharing cold shutdown up to when the refenelung cavity is ( c. flanded with an open RCS (nudicap operation /wesel flange operation is a suinet of this phone of shundown). This explanation shaisid include the stanas of j the equapnirse and penannel hatches, penetrations for operatag systems, and temporary electrical and instrusnent penetrations 1his explanation should f she desenhe the operator's alminy to close - .: twfore seenming through an open RCS makes -- ^ conditions insolerable to the operator. Westinghouse is requessed to dansnient in the PRA how these assungsumis wdl be snet (i e. Tecit Specs., menin ceserols, etc.) f d. For bash of the shutdown phases addressed above Westinghouse is requested to identify in the shundows PRA the probabilities assumed for l l isoistacet j l For beeh of the shutdown phases addressed above Weninghouse is requessed so report the fraction ofcare desnage scenanos occurnng with an open [ e. l ^ and their combined fresyseneses. j l Closed - Response provided by NSD-NRC-%-4680 and by Rev. I of RAI prodded in NSD NRC-96-4739. , /) ,] l f CF i 3038 NRR/SPSB 19.1 RAIof 5156 NeverTreetand Clamed ,,Assen W NSD-NRC-96 4688 4 720.307 The stafIwas unable to find in the revised PRA subnusal sunplified enganes for clie PWnesctuosi and Safety Monstanng Sperm (PMS) and for the f Plass Caneral Syseesa (PIS) as they were nondeled in the PRA The review of the lac PRA models wilinout sisnpisfied process blad espams is extremely l _.~ if at all possible. There o senum to be significant differences in ^... ' g and *. _ between the PRA and the SSAR (Chapeer 7). Such pmcess blod anyams should show [ ilne various subs 3 stems, youps, trains, and divisions mindeled in the PRA (with the same : " ;, and designations used in coher parts a(the PRA) In ad& tion, singlefied espams showing 1, Lc components within each block or subsyneeni, are needed to detensune winether,

failures have

{ ^ heen nondeled and to isndeneand unpartant modeling assumpeians as well as their 1, " This infonnasian was available in revissan 0 of the PRA h i diauld be =pased and included in the redsed PRA, aho i ta m g [ l l ,8s lClamed - Response provuled by NSD-NRC 96-4688. 3039 NRR/SPSR 19.1 RAlot $496 Neier falsnd Clamed , Acteasi W NSD-NRC-96-4688 720.300 1he seaKwas unable to find in the revised PRA submetal the unavailabihties for the various PMS and F13 IAC suherees. This informatmun is [ needed for cWicient review of the lac PRA mndels. Please prodde this informatiost in additican, please provide lines of the top 200 cuenets for ICII A (line l t of ADS stage #1 fails to open) and ICI 2A (lune 2 of ADS stage 81 fails to open). [ Closed. Response provided by NSD-NRC-96-4688. l I Page: 28 Total Records; 187 ~.

AP600 Open item Tracking System Datab:.se: Executive Summ;ry Datz: 11/21/96 Selection: [DSER Section) hke 'l9.** And [NRC Branch) hke NRR/SPSir Sorted by item 8 e item DSER Sectsant Title.Descritwien (W) NRC i , g # g,eterNo.I No. Ikundt Question Tvre Status Detasi Imt Mod Date Resp Eng Status lar Date inrIW NSD-NRC 964680 3040 NRR/SPSB 19.8 RAlol

5. 3,%

lhseter5muaktar Closed 720.309 File IRW-ICl 3 WLK (*.WLK files contain resuks) includes basse event REN-MANO3 in the most importers (" top") cut act for sulece IRW-ICl). A manually constructed IRRAS model(developed based on the fauh trees contained in WCAP-13275, *AP600 Probabihstic Risk Assesseners Fauk Trees, Revision I,1995) for IRW ICl3 does not generate a cut set including this esent Is REN-MANO3 correctly located in the !%T tree (which is fed tw the IRW.ICI1 subtree)? Please explain [ l Closed - Response provided by NSD.NRC-964620. ( ] 3048 NRR'SPSB 19.1 RAIOl 73% Bueter freeland Closed W NSD-NRC-964688 720 310 Sulwrees IRW-ICI 3 IRW lCI4,IRW-IC15, and IRW.IC16 all appear to have sinular logic. Ilowever, IRW !CI 3 has some 737 cut sets (according to file IR W-ICI 3 WLK) while only 4 cut sets are reported Iw IR W-ICI 4, IRW-ICI 5, and IRW-ICl6 (aanrding to their.WLK files) t4te that the pohatulay of subtree IRW lCl 3 is reported to be about 0 004, the pobahildy of sultrees IRW-ICI4 through IRW-IC16 is reported to be about l $E-9. Is some of the logic ir. subtrees IRW-ICI4, IRW-ICl 5, and IRW-ICI6 to he neglected in the analysis? If so, please provide a justaficahon (w this treatment. y l Closed Resp _onse provided by NSD-NRC-9646tt. [ ] 3042 NRR'SPSB 19.1 RAIOB 5 3.% BueterTreeland Closed W NSD-NRC-964688 L 720 31 I According to TaNe 26-2e (trees CVS-IC4 and CVS-ICS, pages 26-79, to) e appears that suhtree MPLIA3 should transfer eso subtree MESOLTTA De staff was unaNe to find this transfer in the WCAP 13275 fauh trees Does fauk tree MPLIA) affect CVS-IC4 and CVS-IC57 If so, please indicate where MPLit3 should transfer irdo MEsotJTA p l Closed Response povided by NSD-NRC-964688. 7 g n.f_ /. _. _ -] p q 304) NRR/SPSB 19.I RAIOl S t% Durter Treeland Closed Acteori W NSD-NRC-%4688 720 312 Table 26-II, page 26-215 SG l and 2. FW NR (Narrow Rante) FIDW. In general, the SGI and S(12 semors support SGI and SG2, [ respectively. In the case of the feedwater narrow range flow sensors,it appears that the "SG2 eensors support SGI and the "SGl* semors support SG2. Is Gas dm Liion correct? Please explain. l Closed - Resportse provided by NSD-NRC-964688. ,( c./ l q 3044 NRR'SPSB 19.1 RA!OI 5/2 % BueterTreeland Closed Action W NSD-NRC-%4688 720 313 RHR-IC2A, Figure 2642, page 531. Event TRANS-E2 is found in the RilR-!C2 A.WLK file, Inst there appear to be no transfer labels or logic structwes for TRANS-E2 in the WCAP 3 3275 fauk trees. What does this event represcus? What filedogic are associated wah it? l Closed - Responsepresided by NSD.NRC-964688. (eys ] 3045 NRR/SPSB 19.1 RAIOl Sct% Bucter/Sancakur Closed Action W NSD-NRC-96-4620 720.314 Event tree ATWSC (page 4-153) shows top evere PRilR2 as being sulatituted with SFWAAPRTA. & Westuishouse XSRT IN Gle (the

• IN files provide instructions to generate cut sets) includes SYS-SFWA and SYS-PRT (and not SYS-PRTA). Should SYS-PRT or SYS-PRTA be used in the suhutdution for PRIIR27 Are the cut sets in file ATWSC developed using SYS-PRT or SYS-PRTA7

/ l Closed - Response provided by NSD-NRC-96-4680. l 3046 NRR/SPSB 19.1 RAIOR 5't% Bucter$ancakser Cloned NW NSD-NRC-964680 [ 720 315 W data fw basic evere CASMOD03 (IAS system, page 25 86) has been truncated (in printing). re there any other conenbutors to the l probalahty fa CASMOD03, or is is the same as that for CASMOD02 (i e.,2.3 I E-2)? v l Closed - Response provided by NSD-NRC-96-4680 l s Page: 29 Total Records: 187 i

AP600 Open Iteni Tracking Systen: Database: Executive Sonini:ry Date: 11/21/96 Selecties: [DSER Sectionj like *19 *" And [NRC Branch] like NRR/SPSW Sorted by item # han DSER Section' Title /Desenpaion (W) NRC Na Branch Quewian Type Status Detail Last Mod Dane Resp Eng Stamas Seaga} leeer No. I la Dane l 3047 NRRJSPSB 19.1 RAIOl w% Berta/Sankcasar Cloaal AIfnDyk ' NSD-NRC 96-4680 720.316 h following pairs of syeen tops appear at speciSc eveva tree andes: CM2NUltCN, CM2SI/RCl, CIB50Hl. CSAXAADF, CM2AR1tCT, SFWAAPRTA, CN2SURCS. Basal on the notating it would he expected that the "A* inglies an AND operation between the two top events, yet it appears that scenetimes an OR operation is employed (e g, for SFWA&PRTA). Picase provide the logic used to test eacep(these sep ewns pairs. l Closed - Respnnse provided by NSD-NRC-96 4680. r a.e / l 3048 NRR/SPSB 19.1 RAIOI nw Burter/Sancaktar Cleard h+ W NSD-NRC-96-4680 720 317 Operator actions LPM-M ANO3 and I.PM-M AN04 are each shown en Chapem 26 and 28 with probabilsties of 8.3E-2. Ilowever, l_PM-MANO3 as shown with a probabiley of 2 2E 3 in Chapem 30 and 33 (Table 334,page 33 45), and LPM-MAN 04 is shoue with a probabilsty of 6 SE-3 in Chaptm 30 and 33 (Table 334, page 33-43). Are same of these values incesrect or are all of thern unal(under ddrerese condstions)? If the laser interpretation is correct, please provide the rules used to specify when each wahar should be mard f l Closed - Response provided by NSD-NRC-96-4630- _ r_S# l 3049 NRR/SPSB 19.1 RAICI v24% Burta/5ancatar Cleart Adian W NSD.NRC 96-4680 720 3 I e h fauh tree of Figure Il 5 I (22AP fauk tree with "P" ind catang loss of offsme power) includes suberee IC22All(*lr indicates station [ bladout). According to the apperne AP600 PRA naming conwntion, one would expect that subtree IC22AP should he used Nose that the cut sets for IC22AP are very d:Herent than those for IC22AB and this can afect a large number of syssevnsiop evnes. %%h subtree spauld be used? Please explain. i l Closed - Response provided by NSDwNRC-96-4680. / l 3050 NRR!SPSB 19.1 RAlol 5/sw BuetaTreeland Closed W NSD-NRC-96-4688 720 319 Table 26-2e (page 26-42) h sulHrees involved with tree IC22AP are AESOlJFBP and MESOUTBP. Also, Gle IC22AP.WLK includes basic j events ADREP002BSA and ADBErol2BSA. Again, this seems to contradict the naming convention is the apparent mismatch intentional? If so, should the IC22AP event description use V0028 and VOI2B instead of V002A and VOI 2A7 Plenar explain. l Closed - Response provided by NSD NRC-96-46st. (JM l h 3051 NRR/SPSB 19.1 RAICI M% Burter/Sanukter Closed NSD-NRC-96-4680 720 320 Events TRANS-AA, TRANS--BB, TRANS-CC and TRANS-DD are found in Westinghouse Gles ADO.WIX,43ALWLK,43MLWI K, 44 ALWlX and 44MLWlX, flowever, the stafIwas unable to Gnd these events in the WCAP-13275 fauk trees. What are these events? Are they basic eveses or do they involve logic (i e., are they fauh trees)? If they involve logic, please provide the logic and show how they are used. i l Closed - Response provided by NSD-NRC-96-4680. l 3052 NRR/SPSB 19.1 RAlol M% BurtnTreciand Closed At p NSD-NRC-%-4680 720.321 Operator action FWN-MANO3 (prehabiley = 103E 3) appears in the Wessinghouse SFW-ICIP.WlX file. Ilowcwr, this evne is n#ound in the related WCAP-13275 fauk trees (pages 921 and 967). On the ceher hand, basic ennt F%W-MAN 02 (probability = 1.65E-4) does appear si these fauk trees. N cut sets for SFW-ICIP generated frain the WCAP-13275 fauk trees (using IRRAS) nissch the annocioned cut sets in the Westinghnume SFW-i ICIP.WlX Ele, except that the SFW.lCIP.WlX resuks show FWN-MANO3 in place of FWN-MAN 02. Based on the descrignions of the eveses, F%% [ MANO3 ap: wars to be enore apprepnase, since it is relevant to loss ofpower scenarios (FWN-MAN 02 is relevare to loss of feefweecr scenarios) is this correct? Please explain. I lCloard - Response provided by NSD-NRC-96-4600. l [ t [ i b Page: 30 Total Records: 187 f i I

AP600 Open Item Tracking System D:.tattse: Executive Summ:ry Datn 11/21/96 Selecties: [DSER Section] like 'I9 ** And [NRC Branch] like NRR/SPSB' Sorted by item f j leem DSER Secteenf Title /Demenparan (W) NRC l No. Branch W -Type Status Detail tass Mod Daar RespF;ig Staeus Samass _ tease No. / tar Date 3055 NRR/SPSB 19.1 RAIG IW2496 PRA.lSoo4 L A _ Claamd Action NSD-NRC-96-4tS6 720 322 Westinghouse stated on page 56-43 that nestant RHR pipe ruyaare sommenes are inchsdad in die deedsue IJOCA analyses and ant in the floodug analysas. The staff noses that RHR pipe rupeure was the danunant floodmug acenano in the AP600 engsmal flandag analyssa. Upon review of the i shutdown PRA, the staff found that RilR pipe rupeures are anal >2ed as the shutdowne PRA isming event tresa De event trees i*=s+ that operatiosi of the t passiw sysenne, including gravity injection, is nos effected by any rupture of RHR piping De senFT accepts this nestiend far analyring RHR pipe rugeures,

( Westingliansse can venfy that passive sysnem operation is not affected by any rupture of RHR piping Devefore, the staffis amitisgtW'"

_ to: i I

a. Docunient in else Shindown floodug PRA that passiw system operation is seat affected by any rupeure of RHR piping far i

both hat / cold shusdann and midlanp' vessel flange operatiost f

b. Docunnese in die Shutdown Flooding PRA that losses ofIRWST inventory freen -

^ can not occur as a resuk of any r rupture of RHR piping for both hat / cold shutdown and snidloop%tssel flange operation. JClosed - Westeighouse responded to this question in lene NSD-NRC-964856 (101396). 3 l 3056 NRR/SPSB 19.1 RAIOf IW2496 PRA-I floneBuner$temmon Cluied Actiosi NSD-NRC 96-4856 720 323 De flooding scenano following the rupture of the fire water linein Assier Building 135%3* esables both non R E & swindiscar ronms, and evensisally esahles the IE banmes in the auxiliary insilding basement if no nutigation is takert his scenano is incheded in high the shutdown and at Power analyses. f ne shundown analyses semead thee the DAS would be failed by the flan &ng in the swechgear voorns. Distribution paael EDS3-EA-1 (Table 27-4)is i included in the failed eqisipnient list he power analpis stated that the PCS (PlS) would be failed by flooding the swindigear rannt Distribution pancis l EDSI-EAl and EDSI-EA2 (Table 28-4) are included in the failed equipnind hut. Dus, it appears that both DAS and PIS will he failed in these flooding j n'4psems-t Since power depesidency is cylicitly noodried in the logic noodels the PIS faiksre ese to power failure shaisid be logically included in the requentification. i Use of a factor a(100 for scenarios 5 and 6 in the shutdown PRA to account for failures of the DAS and PLS is =-, ' '. but please identify and eglain i what values are assagried to the DAS and AILIND-Fall basic events during the evahsation of mequences 15 and 16 in the aspwer analpis De floadung scenarios in the focused PRA are dewtoped from the scenarios in the base-tune flooding PRA in four of the five scenarios in Table 52-19 the j flood damages no safety espespnient, the only differences are dasnage to non safety.,, Compenson of the conditional CDF (CCDF) given the unitiating event indicase that sequences I and 3 have the same CCDF and sequenm 2 and 4 have the same CCDF. Since the focused study &ws not creet naswafety _ . pieuse eglain wiey all four are not die same (SHO) scenario i IClosed-Westinghouse, " " to this question in keter NSD-NRC-96-4856 (10/23.96). l f i 3235 NRR/SPSB 19.1 RAlof 7'2196 Burier Cinmed Closed l Dis detshase item has been removed. It was a duplicase ofitens s3055. l I 1 3237 NRR/SPSB 19.5 RAIOl ?!2396 Burier Cloard Closed l Dis danshame item has been veniaved. k was a daylicase ofitan s3056. [ [ t t t t i I 1 [ I f f Page: 31 Total Records: 187 t t l t s

O AP600 Open Item Tracking System Database: Executive Summary Date: 11/21/96 selection [DSER Section) like *19. And [NRC Branch) like NRR/SPStY Sorted by item 8 Item DSER Sectionf Title /Demenpeian (W) NRC No. Branch Quenhon Type Status Detail 1mt Mod Dane Resp Eng Status Stasma i twie,No. p g3 p, 3241 NRR/SPSB 19.1 RAlof 30'24 % PRA-R OoadBueter Closed Action 'k NSD-NRC-96-4tS6 A RAI Related to DSTR Open item 191.3 2-21: De noo&ng scenanos in the focusal PRA are developed frorn the scenanos in the base-line floo&ng PRA. In four of the five scenanas si Table 52 39 she Good damages no safety equipenent, the only efferences are damage to non.aafety equipment. r- ,,-, of the con &tional CDF (CCDF) given the initiating event in& case that sequences Iand 3 have the same CCDF and aequences 2 and 4 have the same CCDF. Since the focused study does not credit non-safety equipment, please explain u4iy all four are nce the same (SHO) scenano l l Closed - Westinghouse responded to ilus question in letter NSD-N RC-96-4tS6 (10'23/96). _f 3242 NRR!SPSB 19.1 RAIOl 9,19/96 pRA 3Sarter Action W Action W 720.324 As part of the AP600 PRA review, the samtis perfarming confwmatory re<quantification of selected accidere sequences. To coneare with Westinghouse's results, hsts of top mirumum cutsets for each of the sequences gsantified by Westinghouse are needed Each list should provide an adequate numher of cutsets to be used for a meaningful compenson of results (e g, top 50 cutsets or, if less than 50. top cutsets carenhuting to 99*.of the sequence frem-) Pleve provide such lists. 3243 NRR/SPSB 19 I RAIOs 9/19 % pRA-l Bueter Action W Action W 720.325 An important insight, reported by Westinghouse in Chapter 59 (Results) of Revision 6 of the PRA,is that the conenbution of the steam generator tube rupture (SGTR) event to the at power core damage frequency (CDF)is very small(about 1.5*i4 If true, given the low total CDF estimate for the AP600 design, this is a significant improvemne with respect to operating pressurited water reactors (PWRs). One of the reasons, reported by Westinghouse, for the small conenbution of SOTR to CDF is that "the fwst line of r defense is the startup feedwater system (SFWS) and chemical and volume control sptem (CVCS)." Please provide &wumerestion showing that operation of CVCS only provides adequate now for inventory control and that there is sufficieve time to stabilire the plant before core uncovery occurs. Such dxumentation should clearly state all major assumptions ma& in the analpis. I i l Page 32 Total Records: 187 O e

D AP600 Open Item Tracking System Detabase: Executive Summary Date: 11/21/96 Selection: [DSER Section] Iike '19.** And [NRC Branch] like NRR/SPSB' Sotted by item # flent DSER Section/ Titleseecnpaion (W) NRC No. Brandi Questien Type Status Detail last Med Dat* Re,Eng Stanas Stanas Imer No. / IJr Date 3244 NRR/SPSB 19.1 RAlot $1596 f1tA.84Wner Action W Action W ( 720 326 Please provide the followmg information concenung the steam generator tube rugnure (SGTR) event tree mom t

a. De description of ewnt CVCS in Sectuai 4.10 2 (page 4-29L entitled " Event Tree Model and Nodes,"is not referring to the function (i e., invewcry control) CVCS is assumed to serve in the SGTR event tree. Please cylain.

b. Eww SGISO (failure to isolate the rupured steani generator (SG)), as modelcJ by Westinghouse, does not include the possibihty of an unisolable leak (e g, stuck open SG powerwied relief valves (PORVsysafety valves er atmospheric dinnp valves (ADVs)) If an uniso'able pash exists frnra the ruptured SG to the annunphere, the differersial pressure between the pnmary and the secondary side wi!! remain higli since the ruptwed SG could be at er near atmosphenc Fessure. His scenano would require decreasing the pnmary pressure down to the atmosphenc presswe to termsnate the leak pior to depletion of the available RCS inventory. Please cylain why this scenano is nce modeled in the SGTR event tree. If your answer is that unisolable leaks cannot occur, include appepriate documentation to support this assumptxat

c. Please test and drsenbe the specific AP600 design features that reesce the prehability of SGTR events resuhing in I

containment bypass with respect to operating reactors Sudi featwes should irnprose SGTR diagnosis, increase the time available for eperstor actions, lead to less reliance on operator actions and reesce the hkchhood ofchallenging the secondary side safety valves Please ref-r to applicable event tree models and related analyses,

d. h is stated in page 6-13 (Chapter 6, Success Criteria Ana!ysis, of the PRA)that "the passive response paths on i

the SGTR event tree pessumstically model active S0 isolation, which would not be required, since turbine trip would provide an akernative to active SG isolation

• Ilowewe, this is not a "pessansstic" modehng of the

" passive response paths." On the centrary, credit is taken for SG isoletum mi all " passive response paths," as ~ I andscated by the awhirlication of the frequency of these paths by the probability of failure to isolate the ruptured SG (ewres CIB and ClftSGitL). Please clarify.

e. Following t!'.: SG11t event, an Emergency Safeguard Features (ESF) actuation signal is generated due to low pressuriier pressure. De ESF signal is supposed to trip the RCPn and actuate the CMTs. Ilowever, a statement made in page 4-27 ireplies that the event can be temunated by use of nonsafety i

svitenuuuLarmexansnutelyJhanuviam. Page: 33 Total Records: 187

L e ! ^ AP600 Open Item Tracking System Database: Executive Sununary Date: II/21/96 Selectien- [DSER Section] like '19.** And [NRC Branch) like NRR/SPSB' Sorted by item # ham D5ER Sectionf Tittet)encnytion (W) NRC Na Branch Quesison Twe Status Detail tam Mod Dane me.pEng Staans Stanua tm No. / ur Date

f. k seems that there are e arepsenes queween the PRA mndeling of the SGTR accident seipmences and the AP600 Enwrgency Resprmee Guidelmes (see Guidebe AE 3, Rev. 4 July 28.1995). For exangde Table 2-1 of the ERGS shows CMT and PRilR actuation and need for operator acti<m to isolate them when certain conditions are enet. Please provide documentation epaining how applicable emergency procedures are incorporated nWo the PRA rnodels of SGTR L

accident sequences.

g. The following statemene is made (see Chapter 4, page 4-28 of Revision 2 of the PRA): "Analyws show that no overfdling occurs and no autornatic depressurbasica is actuated, even if muhiple tubes have rupsured in the steam generator."

E Please provide docurnentation justifying the reason for not I snodeling in the PRA ermhiple SGTR events. This should include. in addition to the frequency of the initiating eveis, time wmdows availeNe for required operator actions to isolate the fauhed SG and stabilire the plare.

h. Please provide documentation justifying the reason for not anodelmg in the PRA SGTR comeidene with loss of offsite power.

P h l i l ? t i Page: 34 Total Records: I87 4

_ - ~. -. -. - - 3 i AP600 Open Itesa TracNag 9ystemi Database: Executive Samuntry - Detn 11/21/96 j Selecdas. [DSER Sectioni like *19

• And [NRC Branch] hke NRR/SPSB' Setted by llem 8 t

i l hem DSER Secenan7 Title'Descripeiast (W) NRC e No. Brancti rN ~ Type Sessus Deeme! Ima Med Dese Resp Eng Summin samous ImaarNo. I tJr Deer I 3257 NRR/SPSB 19.8 RAjol tit 96 pRA-19 uria l schulz Adust W Aceien W 720.327 Followan RAls relased to DSER Open lemm 19.l.3.1-1 he a prr6anse RAI W - f : was asked to eveheaar Ilie ingact ofneural unises j i raised, by the staff an the estinameed PRflR tube rupture, y The staffreviewed Weeingpinesse's response and idanified the need for the followung.Aam==t infanamanan It is stased shot " Die Tedenical Specificanians will allow plant aperation with a senall PRHR IM lemk and win rugsire that the pinse be shundown befee m. a PRIIR HX leak could degrade into a tube rupswe? What are the criema (and suppnetag analysms)thsa W j _ is propossnato une in decidmig } when to shut the pland down before a PRHR HX leak could dryade isso a tube rupeure. Do these crissein take isso accoise the nasch higlier sersemes that f would be established in the PR HR HX subes in came of an accideas that rapsires the PRHR to apermar? Theme leider seremmes could cause the pre-existsag drfect (u4 midi causes the leak) to reach its

• critical" sire and beccane a rupeure, thus adversely adacting the a% of the PRHR when desinanded to

( apersee to neitigste an accident. Please explain i b. Accordung to Redsinn 4 of the SAR (see pp. 16.1-459 througli 16 f.465), it appears thus the plant will be allowed to aperuse for an as-vet - ,J' period eJainee even if the PRHR is declared '. A. The impiscanian of Actinst D 2, p.16.1 464, is thus siis period e(tune may be madefuune ifit is [ vendied shut the saariup feedweser synem (SFWSk in addeson to the meann generators, is aparable. Piemme clarify. Irshe Teclunical Specifications allow for T/M unavailability of the PRHR due to Icaks, such unavaitelmisty should be included in the feesk tree rumsdel. f

c. Ahhnugh several desigri features which reduce the IAeldined ofprunary side conosinn are listed, none ad6eus the innse of secondary side corrosion

[ u4tich could accelersee under stagpiant condaions by allowing local concenerations ofimes or orygen Please Inst (wnh adapasse enplanation)the AP600 t desispi and operational features that aim at preventing secondary side corrosion (e g, how proper dienumery is eenised?). How do sudi features cenyere to [ features used to prevent secondary side cerrosion in sacern generator tubest j st heni(e) of Westinglioisse's response loses several PRHR flX leak dreectinn features. Please clarify the locmason of the pressure transnumer, ses functinsi [ end the tvye ofinfonnasion it =owles ohnut she leal Also, please prodde dacumentation showing shut the RCS leak detection instruments sessed in your (i e.,. .c surnp levels radiation, and RCS mass balance) can be used so epsentsfy relishly small leaks, such as those that [ would be allowed by your proposed teclunical specifscatica Westinghoisse argues that choosing a PRllR IIX euhe rupture ewse frequency of SE4)r (a factor of to lower than she EPRI PRA KAG,v e. AI.WR SGTR frespnency of SE-3/>r)is conservative Some af ehree argunienas seern to be valuL lloweven,it is seat clear that a factor of to reAxtian is pustdid let slane conservative. One could anenyt to rationalire the factor of to reduction by looking at ihr SOTR events seins how occured and screening out shame events that are not applicable to the PRHR HX tubes. Due to these uncestausies in die assusned PRilR HX tube rupture frayanicy please evalisate the sensitivity of PRA resuhs to the PRHR ltX tube rupture inieisting ewnt freiparacy and report die resuhs in Chapter $9 of the PRA (Resisits and insighes). ? ( One of the argumenes eased to show that the PRHR HX tube rupeure frequency is srnaller than alue i, y of SO tube rupeures, item (ck is that the i primary side water has low orygen content while the secondary side is "not really stagpiant" and its tanymysteme is nonnally low. Ahhoengh, the lower [ ovvgen consent and low weser temperature of the prunary side do yeasty reduce the prehleni of prunary waaer sareas corrosion cracting (PWSCC), it is less clear that the argument bokk for the outside diameter stress corrosion creding(ODSCC) De dasa far low tengeratiere behavior of Alloy 690TT empused to arcandary weser chesmetry and crevice condaions are wrv lunited er nonesistent. It is not clear what W ' J is referring to regarding the [ staannent that the secondary side is "not really stagpiant

• Is there a circulating pump? If so, is the operation of this piump necessary to reduce the e

IAelihood of corrosien en the secondary side of the tubes? Please eglain I 3258 NRR/SPSil 19.1 RAIOl 9/1996 PRA-ISuener Acties W Actiest W g 720.328 Followan RAI relesed to DSER Open leem 19.l.3.5-2. Weeingpiouse's response so RAI s2, relased to this open inan, did nie address the apsemien ne epnestian was: "The staff was unable to fand in the revised PRA suhminal a descripsica of the annipes with ennugh deemins to understand how the comenhussons to interninhase, medium and large LOCA reported mi Section 3.5.3, were calculased. Please provide a clear elescripsian of the analysis (including assumptions. ( data and associated bases)insed to calculate ADS spiances actuation freepsencies and their comenhuticas to the various LOCA initissing ewns freepsencies? Please explain how the niethodology, given in Section 26.5.3, for calculmains the freepsency of spurious ADS l actuation from a 2 out of 2 sispiel eram applies to the fault tree I ADS-IC83 which uses a 2 mt of 4 logic. f Page 35 Total Records: 187 i

s. AP600 Open Item Tracking Systesa Database: Executive Sasuniary Date: 11/21/96 Selection [DSER Section] Iike '19.** And [NRC Branch] like WRR/SPSB' Sorted by item f leann DsEn section/ Title.Dracnytion (W) NRC No. Brandi Qaamion Type State Detail im Mod Dane Reap Eng Staass Status gm No. / la Dane 3259 NRR/SPSB 19.1 RA!Of Wl9% PftA-l%srter Actie W Action W 720.329 Followan RAI related to DSER Open lesen 19.l.314. DSER Open Item 19.l.3-4 cencerne IDCA anpaences with inyowed - - ^ 1kse sequences (leading to endstate #2) were not quanti 6ed in Revision 0 (pre-DSER)of the PRA The staKrequested Westinghouse to either modify the evem trees by noodeling recovery actions or cours these sequemes as leading to core dernage with open commin-mess. Westinghouse responded by remanng the top evnd CI(cordain-ment not ernpaired) froni the event trees in the revised PRA Accord-ing to Westwighouse, t<p event CI is not needed because analyses show that sufreciew water fw long4mn re;irculation cooling of the core is available for at least 2.7 days when 7 - isole-tion fails. Westinghouse argued that the une of a 24 hour mission tiene for long4erm cooling was adequate for all academ scenance in a followg RAI the staKasked Westinghouse to either slow (e 3, through a bounang analysis) that the resi& sal risk (beyond 24 hours)is not sigrm6 cant or extend the ewns tree enodris beyond 24 hours (to a pois in time where it can he argued that the residual risk is not sigraficant). Ahhough statements enade in Westinghouse's resporme to the follow up R Al seem to ayee with the staE regar&ng the need to look beyond 24 hours (e g.,

• core damage is assumed...ifcare damage is anticipated following 24 hours without further system er operator action"), the residual risk issue eas not addressed. Iflang-term cooling snust continue (e g., beyond the estimated 2.7 daysk what actions are needed to be perforened by the operator and what systems must be available to perform these actions? Ilow important are such actions and systems to plare risk?

Please preside documentation, inclu&ng impiwtare assumswiens. Page: 36 lotal Records: I87 L F e

w AP600 Open item Tracking System Database: Executive Sumatry Date: 11/21/96 Selection [DSER Section] like 'l9.** And [NRC Branch] like NRR/SPSB' Sorted by Item # hem DSER Secticonf Title /Descegwim (W) NRC No. Branch Question Type Status Detail IJst klod Date Resp Eng status Stanas beer No. / IJr Date 3260 NRR/SPSB 19.1 RAIOR 9/19/06 PRA-t Sweer Action W Action W f 720.330 Followen RAls related to DSER Open item 19.I.3.14. DSER Open item 19. l.34 concerm the mission time (assurned to be 24 hours) for long4erm cooling in saquences such as those where the reactor is initially maintained at high pressure (i e, non-IDCA sequences with the startep feedwater or the passive RllR availabic). Exangdes are:

a. Sequences ending with startup feedwater system operating-

[ Operator action is needed to replenish the condensate storage tank (CST).

b. Sequences ending with passive RilR operating The IRWST mater starts boihns (Westinghouse analpes show that it reaches saturation in about one to two hours). If the evaporated IRWST imentory does not return to the IRWST, whicli is probable, the heat exchanger will be uncovered at some time (estimated by Westinghouse to be beyond 24 hours) and the IRWST inversary must be replenished or the plant must be depressurized to cxmtinue core cooling by recirculatiort % hat actions are needed to be performed by the operata to bring the plant to cold shutdown conddions and what systems snust be available to perform thehe actions? Ilow irnpartid are such actions and systems to plant risk? Please prodde documentation, including importard assurry-tions.

3261 NRR/SPSB 19.I RAIOl 9/19/96 PRA-t/Bwier Action W Action W \\ 720.331 Followan RAls related to DSER Open Item 19.l.3.14. Another example of sequences, categwired as successful in Revision 2 of the PRA, which need additional developmere er explanation are sequences with an open path outside-(e g, sequences initiated by a steam line break or a stuck open secondary side valve with cecae. quernial SGTR) and normal RllR available for long-term core cooling. These " success" sequences, as modeled in Rev 2, end wnh normal RilR operating. This scenano eventually requires q'-

the IRWST or sump inventory (because it is lost through the open path outside l

ceraminrnent). This is true (ahhough to a lesser extent) also in newes when IRWST injection and passive sump recirculation is used instead ornormal RifR. Can recirculation (either using the normal RllR pumps or by gravity)be esaahtished for long4crm cooling when a considerable amount ofiacrdory has been lost (and in some sequences continues to be lost aaring passive recirculation) tlwaugh the open path to the - , e7 % hat actions are needed to be performed by the operator and what systems must be available to perform these actions? Ilow important are such actions and sptenu to plars risk? Please provide documentation, including important assumptions. Page: 37 Total Records: 157

_ = - ~...-. AP600 Open item Tracking System Database: Executive Summary - Date: 11/21/96 Selecties: [DSER Section] like '19.** And [NRC Branch l like WRR/SPSB' Sorted by item # Item DSER Section/ Title /Denmption (W) NRC No. Brana Qaamion Type Status Detait tmst Med Dese Resp Eng Staeus Seagas 1,mer No. / tir Date 3262 NRR/SPSB . 19.1 RAlof WIW96 PRA l%wser ActirA W Action W [ 720.332 Followen RAI related to DSER Open item 19.I.3.1-IO. The staff requested Wessingpmuse to assess and docuneva the applicability e( gmme failure data to the AP600 desiyt %%Ie chat valves are nm unique la the AP600, the con &tions under which they will be operating in the plam are substermially &Kerevd from those in current gmeration nuclear plants. The concern is that they will have to open on demand under very low deferential pressures eAer long pmods of being held closed by Guid at RCS temperature, pressure and chemistry. Westingliouse re panded that this is not an I issue anymore because some check valves in the IRWST injectim iene have iwen replaced with squib valves M "reesces the number of I check valves and eliminates the high efferential guessure normal operating mvironenew that the valves in the IRWST inja1 ion and recirculation lines would expmence in the previous design.* flowever, Westinghouse's response does not fully address the fact that these valves will have to open on demand under very low &Ker-ential pressures (because gravity is being used instead of pumps) Useful information could be obtained by looking at failure histories of check valves at operating nuclear power ptares that nwst open on demand under small efferennial pressures, such as the cheti valves used as vacuum breakers at the turbine exhaust lines for BWR 11PCI and RCIC sprems (the lines that go from the turbine exhaust to the suppression pool). Please address this question in your next response. Also, as part of the insigins sation (Chapter 59), please include sensitivity studws that assess the impact e(poem-tially higher failure rates far such chest valves to nsk. 7 i Page: 3R Total Records: I87

s AP600 Open item Tracking System Database: Executive Summary Date: 11/21/96 Selection [DSER Section] like *19.** And [NRC Branch] like 'NRR/SPSB' Sorted by item # Item DSER Section/ Title,1)escription (W) NRC d No. firasua Wm Twe Stanas Detail Imt Mal Date Resp Dg Status Stasua im No. / IJr Date 3263 NRR/SPSB 19.5 RAIO W1996 PRA-ISuner Action W Action W i 9 720.333 Followan RAI relased to DSER Open leern 19.l.3.1 13. The staff requessed Westingpunene to explain why in calculating the conuman came failure (CCF) probabihty of the IR WST injection line check valves. MGl. factors froni Revisions 3 and 6 of EPRfs L4ility Requirernents Document (URD) were used A twta factor of 0 026 is ..14 in Revisions 5 and 6 of the UR D which is erasch lower than the value recornrnended in prevsous revmons of the URD(i e 017) as well as in previous PRAs (e g.Sysseen 30+). Westingpiouse i responded that the reduced value of the beta factor for ckt valves reported in Revmons 5 and 6 of EPRfs URD, as conyered to the value.- _ ..J J in previous redssons of the URD was ene to better .?.. ' ; of individual events involving failure of check valves at nuclear power plants It is further stated in Westinghouse *s response that *EPRI found no conunon cause failures to l open ofcheck valves (ether than failure snades unique to testable check valves).* Please explain what you mean by " failure snodes unique to testable check valves" and why such failure modes do not apply to check valves used in the AP600 desigrt An NRC-sponsored evaluation ofIIR and NPRDS events, which occurred between 1980 and 1993 at operating nuclear power plants, has found about twenty (20) events involving common cause failure of ckt valves. Such events should he reviewed for applicability to the AP600 desigst Please state the AP600 design and operational features whih ensure that such evens cannot occur with AP600 check valves. k I 9 4 f L Page: 39 Total Records: 187 h

P AP600 Open Iteen Tracking Systen Database: Executive Semini:ry Data 12/W96 Selection- [ item no] betweea 3427 And 3427 Sorted by item i (W) NRC han psER Secesenf Title!Descrireien No. (W, Queshen Type Semeus Detail last Mod Dese Resp Fag Staeus Stamma EmeestNo. I IJr Dese f RAIOt R&w96 N ame Closed ' Action W NSD NRC-96-4808 ) 19.1 l 3427 R/S Question 720.279 l in Q720 II, the staf asked for documentation drambuig how the rensits of MAAP 4 calculations canyare l menenst the results of hest estimmee thmnabydraelse eners, lake RELAP. The staf also asked WW - - to \\,k' q docuenent the snargins frcen care damage given by the asccess meeria as calculased by MAAP 4 for each of the l s / unitiating evese youps. The statundereands that this congienson will he perfarnied inning the NOTRUMP canyuter code. However, the sten fwther undensands that NOTRUMP was not used far deaiyt basis calculations for ATWS and large IDCA evenes, and that MAAP cannat snadet ATWS and large EDCA scenanas appropnately. 11ee following is a clarification to Q72011. Westindiassee should provide the remshs of casupannan calculations [i fw the follownig very samall and small IDCA success pash scenarias using NOTRUMP and MAAP. Westinghasser should also nse compensen cainstations for the following ATWS and large IDCA - pedi [ scenanas using MAAP and the m.., * ;dreipi basis accidet computer ende. The selectaca af these scesiones (with the exception of ATWS) was based on Westingpunnse's October 20,1993 response to Q720.109. { I 1hree success pashs are amanned to lead to peak clad temperatures less than 2200 F and core uncovery. t Two inch maall IDCA in the direct vammel isynction line assumma andy,he follow' ass equgunuse is at i avnelable: reactor coolani pun, trip, fiell ^_, __- using one Stage I lane and one out of two lines of the fausth stage of the ADS, I out of 2 accumutmears, I out of 2 yavity inJactsen lunes, j l cemamunem snacywy, and reactor pressure vessel water recirculation t

b. One indi anell IDCA in the presserker SRVs assumeng endy the followag equspanent is avadalde-l 4

reacter coolam pusup trip, I out of 2 C64Ts, fielt depressurization using one Stage I line and one out of twolines af ahe fourth stage of the ADS, I out of 2 yavity injection lines. - uneyny,and seacter pressure vessel waner recirculation

c. FreementerlevelE

-ion line lucak (less than 3/4 in) assusning only the following ogmpinas is I avaitalde: reactar coolems pun, trip I out of 2 CMTs, fisti depressuriration using three out of four lines of the second and third stages of the ADS, one line of yavity injection, contamunent snarymy, and j reacter presswe vessel weser recirculation r

d. Very aniell IDCA in the pressunres level insonnnent ljaes (less ilman 3/4 in) ammanung enly the famowingequerneem is availaide: full depressurussion using 2 out of 2 =--{

-, full depres-sunration using four out of four ascend and third stage lines of the ADS, one out of one pavisy injec-eeyWy, and reacter pressure vessel water recirculation tien line. - s

e. tarse IDCA in the direct vessel isijection line assumma only the following equipnient is availeMe: I h

out of 2 care = . I out of 2 yavity injection luies, reactor pressure veemel water recuculasian, = and censmanniem enerymy l

f. ATWS assenung endy she followag ogmpeness is avestable: turbine trip via DAS, namnual barataan, two J

cut of two pressurizer safety valves, and passive RHR. t Far each scenario above, provide alie follevnne code cusput fresa the PRA and DBA code calculations: [

a. Tienediependem plass of the collapsed lipsid newl and the sninsure level in the cere.

l 1

b. The Gesel tinie period in winicle the care is isncovered,

e. T'

- af due mask clad - far the ' -- ^ and -- ilsmiseat [ Page: 1 Tolet Records: I r i m... m. m

-D AP600 Open Item Tracking System Database: Executive Summary Date: 11/21/96 Selection- [DSER Section] Iike '19 ** And [NRC Branch] like NRR/SPSB* Sorted by item 8 hem DSER Sectaanf Title /Desenytion (W) NRC No. thandi Quantion Type Status Detail 12st Mad Dane Resp Eng status Staeus 1,eer No. I tm Daee

d. A tirne<lependent plot of the reactw system power, Time <lependern plots of the secondary speem pressure for teth steam generators, e.

f. For each of the three phases of ADS blowdown (subcooled blM two phase blowdown, and superheated blowdown), a table listing 9 e time of cruct and cargletion of each phase along with the mass remaining in vessel & wing the depressurhation transient, e

g The mass of cootard remainmg in-vessel prior to rebod or core recovery and it A table listing the actuation tirnes for each passive safety feature. The response should include a comparative analysis of the efferences between the srJues predicted by MAAP venus the values pre &cted by NOTRtAlP,inclueng an explanation of the source of the &fferences and a &scussion of their significance. [ Closed - Response prodded in letter dated R/30% l 3895 NRR/SPSB 19.1 Rale! IW2S6 PRA-lTre/ Burier Action W Astion W 720.334 The infannation docwnented in the sutmuttal(Chapter 57, August 9, 1996, latemal fire Analpis DrnA Markup) does not state clearly the major assurveiens inade in inadehng c-' - fres. The ~..: is a single few area which is made up of several v . _ --- -. called fue "rones* (see Table 57-5) It appears that the several fue zones, included in the single containment fue area, are tressed in the analpis similarly to the fire areas for fwes outside the -_ -- flowever. it is nas clear whether and how fire propagation between fue zones is modeled and what is the tecluiical basis for distinguishingthe afferent fire scenanos. Please prodde this infonnation, includmg relevant assumptions, in Chareer $7 of the PRA. 3896 NRR/SPSB 19.5 RAlol IW2/96 PRA-1TacSurser Action W Actices W 720 335 One isem ofconcern in the certification of advanced reactee designs is the impact of snoke, hot gases, and fire suppressrnts on safe shutdown equipenent (especially due to sensitive electromcs) and on operator actions. The issue is arrylified when these elements migrate inno other fue areas. Please address this issue in the innernal fire PRA Page: dI Total Records: 187

r AP600 Open Item Tracking System Database: Executive Sommary Date: 11/21/96 Selecties- [DSER Section] like 'I9 ** And [NRC Branch) like NRR/SPSB' Sorted by item # han DSER Section/ Title /Descrileian (W) NRC T pe Status Detail tast Mod Date ite p Eng Staans Stansa 12tter No. I tar Date No. Branch C__ 3 3897 NRR/SPSB 19.1 ItAIOR IM% Pita-1 fee.hree Action W Actson W ( f 720 336 Rurmng liquids in the AP600 turbine tesildag could fall en the floor at elevation 100 feet h is nm clear where they would go. Is it possible that the oil could creer the Auxiliary Building? Experience (the Vandellos turbine building fwe) has shown that hurning oil can spread away frorn the poirs oforiget is it possible that an innportam scenarw, which involves dennage to other l fue areas within the Auxiliary Building, was not analyzed twcause of the analpis groundrule prevewing trentenne of scenanos involving fare spread to nashiple rancs? Please explain and idewify the specific design features that prevent this frown -,..ing. l 3944 NRR.5PSB 19.5 RAlot In% Pita-ITwehrter Action W Action W i_ 720.337 Westingliouse claines that a comervative "boian&ng* assessenew of the wegact of fre-induced "hre shosts" was perforened. The staf( however, cannot conclude that Westeigimse's analysis is bounding j (based on the information provided in the subnuttal) because (a) the probability of a hot short (frown NUREGCR 2258)is based on judgynne,(b)it is assumed that the probabildy of muhiple hot short events is state <#4siewledge independent, and (c) the analpis does not refer to the specific AP600 PRA IAC malcis and logic &agrams to recognire any innportard features, anser operational requirennents,that are incorporated into the design to prevent fre-induced hot shorts froni causing spunous actuations which in turn i could have a significare impact on plant safety. Please explain the nicchamsm of fire-induced spurious actuations using the AP600 PRA i lac models, the location of the various IAC cabinets, the location l of power source interfaces and assurrgeions enade on cahic characteristics and routint, Also, please hst important design features, antor operational requirements, that prevent fire-induced has shorts froen causing spurious actuations. 3945 NRR/SPSB 19.5 ftAlot IM% Pita-ITre%cter Action W Action W L ? 720.338 Succeuful injection of core makeup taras (CMTs) requires trip of all reactor coolant punys (RCPs). Please address in your annipis the impact of an inadvertent RCP start (aner initial trip) and whether this can occur in the same scenano with other fee-induced failures of safety equipmem, such as spurious actuation of ADS valves, and or with fire-induced control roosn in& cations. Page 42 Total Records: 187

-. = - - _ - -.... r AP600 Open Item Tracking System Database: Executive Summary Date: II/21/96 Selection [DSER Section]like'I9 ** And [NRC Branch]like NRR/SPSB" Sorted by item # Items DSER section/ Title'Desenption (W) NRC No. Branch Question Type Status Detail tast Mod Date Resp Eng Staeus Statua t,eer No. / IJr Date 3946 NRR/SPSB 19.1 RA!Of 80'2/96 PRA.lfme/Bueta Action W Action W ( 720 339 Fire-inanced failure of contaironne isolation valws was not treated in the analysis. It was assurned that such failure has no effect on core damage frequenc,y (see itan it page 5715) because 4.e PRA core damage success entena are specified assummg failure of - -- -= isolation

• llowever, based on infonnation presented in Appendis A of the AP600 PRA,it aws nce appear that cornamunent nelation failure was assumed in,:.a..

success cntena for

[ sump recirculation. Furthennore,the frecency of a core damage scenario with, - isolation failure should be investigated to detennine its conenbution to offsite w gei Please explain. 3947 NRR/SPSB 19.1 RAIOI 10'2/96 PftA.ITre.Burta Action W Action W 720,340 The barrier failure probabilities used in the analysis (see Table l 37-3) assume certain inspection program for the baniers, which includes a sampimg scheme and timing. Please include this uformation in Chapter 57 (internal fres) of the AP600 PRA. 3948 NRR/SPSB 19.1 RAIOl 16'2/96 PRA-lTweBurter Action W Action W 720.341 The first parayaph of Section 57.2 irglies that probabilistic criteria allow screening of - with high fuelloadmg which do not contain PRA< redried epipmew, regardless of propagation potessial. Ilowever, the analysis does consider rooms where the only concern appears to be fue spread (e g, the lube oil room in the turbine building). Is the statement in Section 57.2 correct 7 Pleaseexplah 3949 NRR/SPSB 19.I RAIOl 10/2/96 PRA-IfweBurts Action W Action W 720.342 The basis for defining the fue scenenos in Table 57-4 is not always clear, given the groundrules esemblished in qualitative analyses Step 10. For example, what is the basis for distmguishing between scenanos I and 2 for Fire Area 1200 AF 017 Doth do not seen to involve spunous signals Does one involve propagation out t of the area 7 Scenanos involving propagation out of the fre area 3 should indicate explicitly which adjacent fue area is being treated (especially since the second bullet on page 57-4 states that ' ' a propagation to multiple areas is not treated). Please [ exP ah l 4 Page: 43 Total Records: 187

e-AP600 Open Itene Tracking System Database: Executive Summary Date: 11/21/96 Selection: [DSER Section] like *19.** And [NRC Branch] like NRR/SPSIF Sotted by item # Itsen DSER section/ Title / Description (W) NRC No. Breach Question Twe Status Detail Laat Mod Date Resp Eng Sutus Steaua gener No. / gJr Date 3930 NRR.SPSB 19.8 RAICI 10 @ 96 PRMTetheter A, tion W Action W g 720 343 Note 2 in Table 57-8 indicates that some components enodeled in the facused PRA are failed for some imtiators Does this refer to the damage listed in the 4th column of the table, er are there additional component losses not explicitly idrneined? Please explain. 3958 NRR/SPSB 19.1 RAIOl 10 @ 96 PRM Tscheter Action W Action W [ 720.344 Does the Remote Shutdown Workstation (RSW) panel have identical centrols and drsplays ofplant status information needed dtwing accidents as the Main Control Room (MCR) panels? If the answer is no, please list the major differences and explain how they afect safety system redundancy and relianihty, including operator actions. 3952 NRR/SPSB 19.8 RA!OR IN2/96 PRA-lTrehrter Action W Action W 720.345 Could a fue in the Main Control Room (MCR) afect the transferring ofcontrol to the Remote Shutdown Workstation (RSW) panel? Could i amtrol be inadvertently transferred back to the MCR7 If the answer to these questions is no, please eglain by referring to design features and characteristics (e g,6her optic switches and locanica of power sources to the light transmitters and receivm) and to emergency operating procedures and criteria for transfming conteol to the RSW. If the answer to any of the above two questions is yes, please model the failure to transfer control in the PRA. 3933 NRR/SPSB 19.1 RA!Of 30 @ 96 PRA ITseSurter Action W Action W \\ 720.346 The Main Control Roorn (MCR) evacuation scenario related to fre in the overhead snimic panel (scenario CR5) appears to be relevant for i all control room panels, notjust the overhead mimic panel. If all panels are included the contribution from CRS-like scenarios should he around a factor of 30 higher. Please explain why fres in other control roose pancis are not postulated to lead to MCR evacuation and plant shutdown via the Remote Shut &mi Workstation. Page: 44 Total Records: 187

r AP600 Open Item Tracking Systen Database: Executive Summary Date: 11/21/96 Selecties [DSER Section] like '19.** And [NRC Branch] likt NRR/SPSE Sorted by item f item DSER Sectuai/ Title /Deacnytion (W) NRC No. Brancti Question Type Status Detail Imst Med Date Resp Eng stanas Stasms W Na f gm pas, 3954 NRR/SPSB 19.1 RA!W 17196 PRA-Ifesikriar Action W Action W j 720.347 The fresquency of fwes in the AP600 Main Control Roeni(MCR) was assunwd to be a fador of 10 snialler than the fregnency of Twes in a convevesonal control races 1M was based on the observation that rnost of the cables in the AP600 MCR are low vokage as cumpered with conventional control rooni cables. Although it appears reasonable to postutate some reductiori in fue frapawy as compared with conventional control rooms,is there any data to supptut the reduction factor used? It is annaioned (page 57-26) that Westinghouse ceble heatup calculations have shown that ignition is very inyrobable bnause low-voltage cables do not produce enough energy to heat up the cables. Do, the above mentioned Westinghouse calculations, account for insulation agirg or the presence ordust? Ilow many of the I 2 MCR fsres in the NSAC/17 L database were mitiated by eledrient fanhs lendmg to ignition of the ensulation? Please provide a brealtdown of causes. Afu, for endi ema, please prodde: an event drwission, the basis for

n. ' ' ; that the fire was not severe and the supprmion tune.

Page: 45 Total Records: 187 m-

_~ .. + AP600 Open Item Tracking System Database: Executive Sosnatry Date: 11/21/96 7 Seleeden- [DSER Section) like 'I9 ** And [NRC Branch l ltke NIUUSPSB' Sorted by item # lease DSER 5acteenf TW. (W) NRC h Brune W Type sensus Deemet tase Med Dane Ramp Esig sessus semens gmar w f. IJr Dane 3955 NRR/SPSB 19.1 RAI48 in96 PRA-lTas1hseese Aceien W Action W 1, j 720.348 The analysis of scenanas CR4 and CR4A(which treat die spunaus i actisasion of bash divisions of the ADS Stage i valves ese to a fwe I in the Deecaned Caneral Panel) and Scenano CR4B (which treats the 5 spurious opening of the Stage 4 valves) does nas explain alue audissunns of spunaus actuation using PRA IAC nandris and SAR IAC i logic eayanus and does nas sense amusnps.ans snade. furthensmare, dus annipis does nas idneify inapostase fessures, and/or operational tapeirensenes, that are -- .-Minto aler design to t prevent fwe-induced Inot shorts frosn causing spunaus actuateans which in sura could have a significans ' igast an plant safety. [ m riesse provide this infannation. In your rep please inchade j aanwers to the followuig 9 sessions: [ Is Sceneno CR4B property labeled as a sensitivity case? Or should its resuhs he added inso the taeal CDF for the MCR7 r I Can a fire that has youn past the innpiese usage in the i panel affect all ADS vahes? If so, is there a technical i l basis for anatyring only a nsheet of fue efIects? The effective spunaies acoussian probaNisey for all three MCR scenanas (CR4, CR4A and CR4B)is 0 01. Osa the other i hand, for scenarios outside time MCR. a value ef 0 06 is used for a single spuncus actuassan of an ADS Stage 4 valve (leading to an nordumn 1.OCA) and a vakse of 0.0036 is used for IIne spuncus actuarian of bash ADS Stage 4 valves (leadog :o a large tiX'AK ls there a efference between I the MCR and ex MCR scenanas necessstseing the differese approaches so gnassify the hkelshood ofspuncus actuai.ans? l i 3956 NRR/SPSB 19.1 RAIOl IM96 PRA-ITur Tourier Aceien W Action W 720.349 I nic analg.s - emi uCR rwes win ne. anrea snish;,ie cabinees, at lean uneil caserol is transferred to the renuse t shutdown worlunation. what dess s ressures are leavided se ensure e thee fues do noe prepasase fresa ene cabinet'paart to annehert i L I L b I l Page 46 Total Records: I87 I i

r AP600 Open Item Tracking System Database: Executive Summary Date: 1I/21/96 Selecties: [DSER Section] like *19? And [NRC Branch] like NRR/SPSB* Sorted by item # Item DSER Sedian/ Title >Drecnytion (W) NRC = h Brenda Qaastian Type Staans Detail tast Mod Date Resp Eng Stemas Stamos teest h I IJr Date 3957 NRR/SPSB 19.1 ItAIOl 18296 PRA-ITwe9urter Action W Action W \\ 720.350 h is not clear which nondel was used to estirnate the neuMuppression probability The annipis text refers to EPRfs HCR nondel, but the reference supphed is for ASEP(see p 57-33, Ref. 574). a) Please explain how the norwuppression probahilny of 0 0034 (used in the analpis)was altamed. b) Aside froen questions ofits applicabiley to the analpis of i fire suppression activities, the ASEP nondel deals with t diagonais (and noswespanse), as does EPRfs HCR model. Some time is required to actually extinguish the fire. Anstpis of suppression time data in& cates a nican l suppression time clahout 8 nunutes. Does the AP600 l analpis address the turie required to extinguish the fire? Please explain. c) Westinglinuse's iseerpretation of the San &a cabinet fue tests appears to &ffer froen San &a's interpretation. la questions to the utildy regerang the South Texas fire risk i assenarnent, the San &a tearn stated that " San &a spanscred large scale enclosure tests have shown that cabinet fees generate such intense smrate that within 6-8 eninutes control c(the plant frown the coveral roern would be sirtually ingensible. These tests were conducted with control recen ventilatsen rates of up to ten room changes per hour? Please explain the basis fw selecting a 15 uninute tiene wuulow (before control recen evacuation is required) d Are there procedures dealing with control room evacuation? If so, what are the criteria ined for determerung when evacuation should' anne take place? 3958 NRR/SPSB 19.1 ItAlot 10'2,96 PRA-lTweBurter Action W Actiest W ( I 720.351 l A fue in the MCR migle canne spermus indications as well as apunous equipmers operaticut Such spunous in& cations could prompt incorrect operator actions ("mors ofcomnussion"). Please decuss the likelihood and potential consequences of such fue-indaced errors. In your discussion please list invertant design features and operational requirements which help pevers such ,,,,,s of- - t i Page: 47 Tolet Records: 187

e AP600 Open item Tracking Systein Database: Executive Susemary Date: 11/21/96 i Selectlen: [DSER Section] like '19.** And [NRC Branch] Itka NRR/SPStr Sorted by item 8 Item DSER Sectam/ Title.1)eempeian (W) NRC Na Brandi Quewian Type sensus Detail last Med Date Resp Eng Stasus ' Sensus I.myr Na / Lar Date 3939 NRR/SPSB 19.I RAIOf 10rI796 f1tM TweBurter Actian W Action W 720.352 l The Auxiliary Building contains the MCR as well as various IAC, honery and electrical equipmeve areas. Do any of the later areas . share a conune veveilation system anser air intake syneem with the control ronm? If the answer is yes, please explain whos barriers (including operator actions) prevent smok e, het pses and fire suppressants from reaching the MCR and how such barrices can be defeated i L Page: 48 Total Records: 187 m

AP600 Open Item Tracking System Database: Executive Summary Date: 10/15/96 Selecties: [DSER Sation] like *5 And [NRC Branch] like NRR/ITRIY Sorted by NRC Branch Itan DSER Sectson/ TitleDesenpainn (W) NRC = No. Branch Queshen Type seseus Detail Last Med Dese Stsaus Stasms Laser No. / Lar Duse SIS NRR,7 ERB ER.Ct 1&2591 Closed W NTD-NRC-95-4433 4/3.95 h e *> p ~ Westinghouse should add COL Action lien 2.3.1-1 to the SSAR. requinng thee time COL applicant provide one-specdic sinnmation. (Regional Cisnetology) lClased - Comtuned License meniincludalin SSAR Revision 2, sectiori 2.3.6.l. l Le 50N& Page 1 Total Records. I

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AP600 Open Iten Tracking System Database: Executive Sumniary Date: 10/15/96 ~ Selection: [DSER Section] like 7 ** Sorted by NRC Branch item DSER Sedianf Title /Denmption (W) NRC i No. Branch Queshen Type Staeus Detail Las Mod Date Semeus Stamas im No. I 12 Date 1839 NRR.? ERB 2.3 I-I D$ERM torts,91 Closed N NTD-NRC-9f 4433, 4195 l2.3.5-l N COL applicant should provide alw idewified ssee.apecifw reponal meteorolopcal infm- [OJOfL/M / l } Closed - Comhuwd Licerme item included in SSAR Revision 2 sectm 2 3 6.1. l W NTD-NRC-95-4433, 419) 1940 NRR!PERB 23.2-1 D5ERM IM s,9s Cimed l2.3.2-11he COL applicant should provide the idevenfwd sne-spenfw local..r_,MM infonnatsart /d.5 O/t/#( l l Closed - Combined Liceme item included in SSAR Revision 2 sectson 2.3 6.2. l 1841 NRR.TERB 233-1 DsERM a2095 Closed PrepuRf NTD NRC-95-4433 4'3f5 l23.3-1 The COL apphcart should provide tle ermite nwteorolopcal.._._.t program for staffreview. [dSo/V8 of l l Closed - Comhaned License itern includal in SSAR Revision 2 Section 2 3 6.3. l 1842 NRRTERD 23.5-1 DSERM s/2n95 Cloerd peepened NTD-NRC-95-4433 4.195 I l23.5-l & COL applicant should provide the site 4pecife long4erm diffusion estimates- @ S d/(/p q l l Closed - Combined ljcense item ircluded in SSAR Revision 2, section 2.3 6.5. l 518 NRR/IIRB 2.33 D5ERol 9/2ft91 Closed Resolved N'ID-NRC-95-4433 4195 inghouse should add COL Acten item 23.3-1 to the SS AR for COL apphcant to provide the ansite nutmolopcal necesuremews program for staff IClosed - Combined liceme item included in SSAR Revision 2 Section 23.6.3. l i l i Page: 11; TotalRecords.5d(.7jgh

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== e e = h u = e n s uR 1 m m a l i= a q e m yr e f sa ed a s m w mM is r b n= e l n t u a c i e r ia n m n a n s h e l m 1 u i f n R s l ip y m u e n e b O is e u r o n e n h t s i r a din u y r w = r i l e a A a e S b pf S p eh e u e e v t yt R s r e s r s o 6 n n t f f e m r m ~ e n ae e S s tsy ie y y c Re p 9 id t W m o o, n p 6 o a a m v o bb p c c n ( e a w e u 4 e i a ne e i n g 3n a n e s m C s t r c h ab t mm a da d ~ r 3 y O i m e u e e m S p g g e 1 m l E r T r s a a a r x R s lyd o e a u u u nt s y c S in t r r n o c l e R d o d a u I e e e e u n e = s, r U a t t d e f no d e e o p e e ah L. h n v a s m e n y h a i s s s tem c E a, ic s 1 h m h n t i f s i f e e h r a e g N s 3 e s e a e c E h e o s S e r - s u t e h 6 y a 7 y a u o d a isD m n eT e y m m e t o. D e m n t e s n u a' dl 5 a a n h n 9 d o 7 le n e t u 6 l t 3 a 6 f r 6 On a, e u e y D s n C- ,l n 9 h ru 5 d d 6 s id 9 o C 4 6 i C 4 6 i Ehh e a 9 a h 9 r ee n. e B 0 7 3 0 M 1 ~ s b d n 9 b b p m 9 0 e R t ae a n d e c 6 n m. A a o M e a a a n d j 3 1 d r r s a n 4 c e e b e M s o - dh m s r e a r 9 wh r e h f l e o e oW iz T E 1 h 1 E e h w 7 e r m mR S i t p-i t i o 3 pe a t a s e R O mA S t o R t s m. s s c t t r e h t i t o a uh m A a n s m l t t' e t U e n u s mS e i e S t St sh L u a u py i f N tu f N e m n e R uS d m c s n mC 9, D' 8 th i O in m a aa e a r r s m wd b da a o t e a t B = Wt e t s i r e id m yB 8 u t A-s n m =a-iwd r C m m eT S e mR hd wf 3 w a ev o n w t N e1 aa m a m a su n e d n ud e E e 3 h id ei d u T l i 1 d Oq e e my u m C e m C e o e e eh d m r v m3 m 1 P = npe a m at d u s. t D d s r r 3 d di ri r ob u / e P u dm i-s 3 yR Tar r W d e u X l r d f e pf f l d e c l l m d S R m e n u a s e, e b s h I O u s e u Rr e ns a a rE a u a o a n a n t o C o aa h gW ^ n a e i f f h Ee e h s n c h e a D h mi L L s u s s s e s s s s s e e o st s - h O h O a' T n 1 e e n b e 1 Wh in a n e p a s C C i h.8 i k mtil i .T Ha re m P. .to W e e ur ht, k h m e s-A' o - a A. A. J . W i W1 D a" c ] e ^ We e . We p t s n d ) ah T. e e d g r iv m 1 d e n h '- r c . u e m G. a u-i l e e m a .e . y ^ m a n s ta T a l m .T m 3 s r a r TS W" W C W i m t 7 a o s a e n d l 3 l s t se e C ) [ l [ i W LA, l ".Q 3 W [ r [ Ap R [ ^ r A. W mB [ c 1 e t R N I n[ o E s e t t O I I O I p o c C O O I o O t e O w E E E E E E E E R A R R R R R R 0 e T s s S 5 S S 5 S s O D D D D D D D 0 i t 6 c A e n 7 P el 9 / S a s ~ t c s e = d S = r R o Dh 3 3 3 1 3 3 3 l c E 1 1 2 3 4 3 4 S e S 3 3 3 3 3 3 3 C R 3 3 O a 1 1 1 1 1 3 3 t ( oT B q B B B B B B R R R R R R R h E E E - E E E E ^, c P P P P P P P / r R R R R R R R R n / / / / / / a R R R R R R R R B N N N N N N N N 4

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AP600 Open item Tracking System Database: Executive Sumacy Date: 11/W96 selecties [NRC Branch) hke NRR/PERR Sortal by DSER Section itsen DSER Secuanf Title,W (W) NRC Na M W Type Samme Detaal Imat Mad Dane r Simams States immer No I tar Dune 33 NRR/PERB 20 4-30 DSEA U Ws696 Closed Rassiend To a&hus Immue 111 Al.2. Wa==ga- =* should ..i for the ensee suppent casear (OSC)'m the AP600 deny h h*= 18.2 I.1.2 6 ddie i SS AR danske ese S-*== and W ef the OSC. This a-ad be e-A=*=d in huum (2)(urv) afSmanism 1,93 af to SSAR te dummenWuse rumml this imune for the AP600 damipt N- ' lemae 111A1.2 has bauen.r Jecally m&lrummed in the Rev. 7 ef Sectson i 9 4 of the SSAR, and inctended in Table 19 2 IJutun' Safety Imame med Omarse Sefury Immmes acce% to what wee agreed wide die NRC, The lama in ceased NRC an=== Updese pnmend in t=gn=d= S 1996 husr: SSAR Revision 7,(4.96) of Section I 9 3(2)(xxv)en page I 9-22 of the SSAR specifically mahamen samme 111 AI.2. Ennergency Response Fr.nti-tism. pnmens for a secommcal asyport emner (TSC) and + support causer (OSC)- and inchaded IIIA l.2 in Table t.9-2 (Shoes 20 of 33, page 1.9-143k "listang of Unrenalved Safety Immes and Genme I Sareeyimm R moived 354 NRR/PERB 20.4-31 DSEA O WMme h Rammlued 7_ _ should a& bens ihm :

• 7, of the COL appiscuss in the resolumes ofissue !!!A3.3.

I ~ Clemed. SSAR Table 1.9-2, thout 21. Revisen 7. h ust hmme It1A3.3 is uma a emmip imame nimme le is smemmed b d operatsamt The consnunicatiase myseern demipiis sabusand in the SSAR escasan 9 3 2. S '

-: 9.3 2.5 addreames offsier-inaurimens.

COL syplicuse requewneses reinsed to Issue ill A3 3 that are not meerfaces wnh the demip c?-- t - for AP600 are addrummed in the con 6med licumme appi cas-i process and are sus ;nchaded in the SSAR. NRC em=== Upenne prevedad in 5missereur 5.1996 leser SS AR Revision 5,(696) of Section 9 3 2.5 2 cui page 9 5-17 of the SSAR sh that "the sumergmacy r==pa=== facihty - ' --ion speari, incW dhe seimin summesamme radio ryunern, will be addressed by the Candiisend Ii===* mpplecenst. Ramalved t 1332 NRMERB 2049 DSERG . / t 67596 Clemed Actioni[ For Immse II.B.2, W" J _ shoesto eghculy discumm ihe ;- " ", between elecI&me and the sammee eerse used for accidmet analyses in 'hP-15 of she SSAR. Alma W J should provide she SSAR sections that escuss ilueldung and massee termes, and sinansid define alte ' lesses of s die CUL applicant. Klamed. Imme 11 B.2 has been -- t- "y addrummed sidie Rev. 7 of 0-4_-- t.9 4 of the SSAR. The inuma is cImmed 1604 NRR!FERB 20.7-46 DsER G _ / l { Wa t96 Omand " ' )#bSD-NRC-9M18 jFar C_..; trust 39-15. W" J uhensid idsmanfy ;.-m ;, _ dass for die AP600 damigt Actnem W -lhe i.;.C. . is the anterguicy rumpense data spesen (ERDS) propsum in a COL appencess reflect the role of die AP600 EROS in ideenfysig key piare perssneeses which could be used by a COL. apphcom ^and ' 1. WCAP-13359 will be revised to 1 shis preyent Clamed. WCAP-13339 Rev. I imanad Sayenneur I1, t996 . -- si i SIS NRR/PERB $243 D5EROI IW25MS Clamed Aceine N NTD-NRC-95-4431 W5 Westep should add COL Actson item 2.31 1 to the SSAR, reepswing shut the COL apphenne pnmde sawynn r- ,) ornamesamt (Reponal lClamed Cerebened I L---; esen ancluded si SSAR Revision 2, =are-2.3 6.1. l Page 13 Total Records 79 i ~ i

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,[ [ d 3 3 3 3 r 9 m 9 n a 1 9 9 v z e h e1 n 1 3 / D 4 m / 2 g r i t t u 4 4 1 o I e t p L 3 v a D r t e p 3 3 m 3 e 3 3 4 r 4 o 4 4 7 y = f 4 4 2 c = 0 s = 5 y 5 5 4 g = s I 9 ra 9 9 s y 8 C-d C-9 m 3 m C t oNR u [ R R C g e fs N a N N R m a k B N r o S e b 4 t nB D b r e e e T f e n T T T c s p r M N N E m $m e t N m e h s m t a O ,[ ' k t s a o n d d n i a n d o d a d y t s w s a e s e r n n v s l a a m e C u l v s b 6 R a a a l o s t m m a h e i e u s a t n l s c m d m 9 N S R A R R o R e c A e n a n ~ e / e I 4 m W c m / 4 s r e s 1 k a v m 1 e g iaA m t v a n eB s d s l i d d s d d l t a e e e u e e i e e d rD d a Wam s m e m m w e n e o v ) t l a s d e o a r m s a a l ( S l l a a s s D C C m 4 O C C a l e l l n u e d C lo-e m s rs p m y u 4 a t rk n f g e n el a o e= l o

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D m rU o d D S 9 s 9 9 p I. s n a S 2 0 i d 9 t d s s b d s e a e M t a in 6 t W-v e i e a a n n 2 d 6 u 2 n d s r e d d i m2 b wk . wi i a a t ti d 1 -. n 'r a u ? e / a. t o a d d r. s id; l / m m m-e s s l s a i A i t 3 n t c e 9. C ' e, ms c e s d e y a r y v r h r I s a oa a S L a u er t s C e ie s s a e e e u n m hl R s a B e e a s s inWom b n D B' 2 i d e i t c t c r L e tem l a, U e e e n O s i n u n as cs s c d d s e dTI 4d mR m s ma Rie = s n oi d p3 p d fsy P. 3 s vm e p. p e 5 e i e E e nw f se m n e d n o r)e31 u n i t P d e r v a3 ad n p o o s U d e $5 a c pe L e3 am 3 e n6 o LA d v S lu s_ 3 (1 td i d n S P i = y J u m l p O! 3 a p9 eAe C s r s o s d u f. l c e C! Ac e4iLl d e o .l %Da - f- . 'r . m O i h n e o 2 t W r h h s L e o e t ( aHf e m s s'- a n s i a 1 m I r g e e L d a7 m ahty d b s_ n s I e o mm o e l UeOehb pn o C i p To m m _l R e a i l s ed s s a e a a k h i t d ui e I n 0 mdi 4 I J0 h C C eieh h s s a R. i s n a c ) uv m f d e m a h 4_ eicd I. 6 m e s s a T n &b = d r c a P d 1 2 e t Rn A A e d d e e e S 'e d e s 1 s 5 e t e a r a m .'n mb Rm t e o 3 a e o s a r e n u s e 4 r. T S w l l l C Am he 'l mB I C 2 C l e p e C l W 1 } h lC Wo i e e n l 0 c l a S t a R I a C lh l 2 f Cc NS ll t R in [N M t o e i i o t M p o o e O: p R R R R R R y E E E E E E 0 s T s 5 S 5 5 S e D D D D D D 0 i t 6 c P el A e i 7 r S 9 sa e tceS m s d R - 1 r DW 3 3 S 6 e E 1 1 c 1 2 o S 4 2 t 4 3 3 3 3 3 R 0 2 2 2 2 2 2 a l to T B B B B B B R R R R R R h E E E E E E c n P 7s R R R R P ?. P P / a / R R / / r B R R R R R R N N N N N N 2 1 eg m a 2 E N 8 2 8 2 o 9 0 4 1 3 9 P te 99 5 1 5 3 1

j,MNG NS 6;idl3\\% AP600 Open Iteni Tracking System Datab;se: Prrject M:nagement Report Dat:: 11/21/96 Selectlee [NRC Branch) hke 'NRR/lDD'Ir Sorted by NRC Branch Decriptm hem DSER Section/ NRC Memo NRC No. Brandi Question Type Status Detail Last Mod Dase Stasus Stansa 1mer No. I Dane b' Ih 216 NRR/HHFB 13.1-1 D$ERot 618/96 Okmed Closed SighKLa>P 13 C OP 11-IL2I*TG d IWestinsho=ne should add COL Actioni hes i I 31 1 to k SSAR fa Se COL applicant to adeus h o

• sancture ef ee COL applicas.

l foL IT5m Cicaed - The COL mformaten item to include the _.,.._.; structure of the COL orgamzation was addai to the SSAR, Seection 13.1, Revision 3 Identified as closed in O!T database markup by Jim Bangarra, provided on 6/10% 217 NRR/51HFB 13.2-1 D5ERol 61296 Closed Closed NTD-NRC-95-4464 bhIIb, 54AA cnfL13 l Westinghouse should add COL Action hem 13 2 1 to the SSAR for the COL applicars to address pmannel tramag by the COL appheart. l Closed -lhe COL information nem to include the management structure of the COL organization u as added to the SSAR Section 13.2 (Revision 3) Identified as closed in OIT database majr up by Jun Bangarra, provided on 6/10% M A 'r'nscscy E-(4eq h EMMC# 725 NRR/HIIFB 13.5.l l DSER ot g 19 96 Closed Action W cuare ,g *. f l Westinghouse should add COL Action item 13 51-1 to the SSAR for the COL apphears to address ademnestrasive proce&res for the plant l (t/ Prod X2 DE/SZ4 Closed - A COLinformation seem was added to Chapter 13 5. Revision 3. of the SSAR to ad&ess administrative -Ch for the plant s 6/10.96 - N RC believes issue remains open pending resolution of the procedures section of Chapter 18. 226 NRR/HHFB 13.5 2-1 DSERol 919.96 Closed Actiosi W 0Qa(_/LA W ? N ?' N //3. l Westinghouse should add COL Action hem 13 5 21 to the SSAR for the COL applicant to address agerating and - _ :+ procedures for the plant. l S O.I y$ Closed - A COL information item was added to Section 13 5. Revision 3. of the SSAR to address the 1.e y.-.; of operating and maintainance Ivecedures for the plant. 6/10/96 - NRC believes issue remains open pendmg resolution of the procedures section of Chapter I8. I Page: 1 Total Records: 134 i

L o AP600 Open item Tracking System Database: Prcject Management Report Date: 11/21/96 Selection: [NRC Branch l ltke HRRA DIFB' Sorted by NRC Branch Decrigeson item DSER Section/ NRC Memo (W) NRC No. Branch h=i Type Staeus Detail Last Mod Date Stamms States EmarNo. / Dune 302 NRR/HlffB 18.211-1 D$EROI 7/2696 Cloaad ActuamW AcF"# f/ W' f _ should ishtify the starting pnires for each human factor erigmaerms (HR) activity (i.e., those espaces of the smalyass or emaist that see ayuts to the 1111 program, rather than the result of HFE analyses and evalushens). For example, if functions have baan alW to plass persassiel, net as part of the HFE analpis, the allocations should be idmised Per conferente call with NRC (J Bongwra, G Galletti, J CrHara, J Higgins) of 2/23.95: Action W - Send a draft of the associated documere and'or re6sion to the applicable SSAP. sectsons i I i Action W Per NRC letter of 3/22 and conference call with NRC (J Ikmgarra, O Galletti, J 011ars, J liiggins) of 2/2393: Action W-Revise SS AR section it 8 2 to include details of onitial assumptions erwl startmg poires for the llFE design process and to clarify iripuis to the HE design procras, any assumptions and the initial function allocations and control room resource selections (URD forms siput to the HFE process and basis for these assumptions) Dran of these revised SS AR sections will be sent to the NRC. Revision to MMIS Developmese Plan will be needed to ensure consistency. Resised AP600 human factors engineering proltram plan included as SSAR 18 2 in Revision 9,7/31/96. [E

• f MM 303 NRR,11HfTs 18 2.3.2-1 D5ER ot 7 26 %

Closed Resolved # a K iT/1/fd f/ Westinghouse should provide information regardeg the human systern interface (HSI) team composition WM ".2-_, should

• idenufy team members with procedures hadground
• idevenfy team memchers with safety system engineermg bodyound
• ideveify team memebers with RAMI background l
• provide the specifie qualiGcations of the team members Per conference call with NRC (J Bangarra, O Galletti, J 011 ara, J liiggins) of 2/23.95-Action N - Send clarification on the requirement to have a safety speem engmeer en the HFE design tearn Clarification on the qualification requirements of the safty sweem engmeer (Centdicate from the Board of Certified Safety Professionals in System safety???).

Resolved Per NRC letter of 3/2'96 Formal SSAR revision required for closure Revised AP600 human factors engmeering prograrn plan included as SSAR I8 2 in Revision 9,7/31/96 Per conference call with NRC (J Bangarra, O Galletti, J 011 era, J liiggins) of 2/23/95: Action N - Send clarificaria on the requirement to hast a safety system engmeer on the llFE design teasn Clanfication on the quahfication requirements ofCie safety system engmeer (Certificate from the Board of Certified Safety Professionals in Splem safcty???) Westinghouse has prepared a draft revision to SS AR section 18 4 that addresses the DSER open items, except for the clarification informahon needed from the NRC on the System Safety Engmeer. As soon as this information is provided, it will be added to the draA SS AR aection 18.4 and the draft section will be sere to the NRC. Action N - NRC to review I e 4 markup and provide feeenck [ Page: 2 Tolet Records: 134

o-p AP600 Open Item Tracking System Database: Prcject Management Report Date: 11/21/96 Selecties- [NRC Branch] like HRR/ID D'B' Sorted by NRC Branch Drumptica Itern DSER W NRC Mano (W) NRC No. M Quenhes Type Staeus Detail Imt Mod Date - Stabas 5tsaus Lamar No. / Dune 304 NRR/HHFB 112.3.2 2 DSEROI 7/ % 96 Clamed Resolved C}l/Blhkj) l Westeghouse should provide infonnahan regardmg the job deemp. teens and assigenents of HSI poemannel Per conference call with NRC (J fbngarra, G Galleei J OHare, J Higgins) of 2/23>95: Action W -- Names of assigned preserswl are nd needed. Send a draA of the associated exanent and'or redsien to the applicable $$AR asctuuss i Resolved Per NRC letter of 3'2/96 Formal SSAR revision required for cloure Per conference call with NRC (2 Ikegarra, O Galleni, J OHara, J Higgins) of 2/2395. Names of assigned personnel are not W Send a draA of revision to the applicable SSAR scoions. A revision et the MMIS Development Plan will be needed for. '- -)(pod S/31 pre S/l) { Westinghouw sent (via fat) a dean revision to SSAR 18 4 to t!w NRC filIFR Action N-NRC action is to review and provide fee &ack-t Revised AP600 human factors engmeenng program plan included as SSAR I 8 2 in Revision 9. 7/31 % h t r l i l l i r i l l t Page: 3 Total Records: 134 l . m - m

AP600 Open item Tracking System Databrse: Prtject Management Report Date: 11/21/96 Selection: [NRC Branch] like NRR/IDIFB' Sorted by NRC Branch Description Item DSER Section' NRC Memo (W) NRC No. Branch Quenham Type Status Detail Imt Mod Date Stanum Stamm LamarNo. I Dese 1305 NRR/HilFB 18 2.3.3-1 DSER ol 7%% Closed T nse..lvel co f $. (6ffff0 [ Westinghouse should provide infcumation regardma the HFE process and pre W ^f should provide WCAP 12601. WCAP-9817.OCS-OES 011. and any adational ecuments that dracribe the aspects of the HFE desip twooems idnenfied in shim criam audi as the "Dumir Reviews and Configuration Control Documents"idechried in Weninghouse's response to Q620 $ I. Meeting of 3995-Westinghouse will rnake available (plan in the Rocintle effice) to the NRC en cuangle of a speem that were through the process (draip process) auch as the one we paned around at the meeting ( AWARE Intermediate Desip Review Repnet) W AP600 MMIS Developerse Plan will also be rnade avadable aAct it is revised Action N: NRC uill resiew our desip process as desceihed in the SS AR. RAls and in WCAP 12601. 9817 and the MMIS Develogm v Plan and prende usfee & ack. Submteria Ic. and Id need to be addressed SS AR revision to IR S 2 is needed Needs to be w.._. with MMIS Developmese Plan. Meeting of 3193 Westinghouse will make available (place in the Rockville office)to the NRC en example of a system that went tlwaugh the process (desip process) such as the one we passed around at the rneetag ( AW ARE Intermediate Desip Review Report). W AP600 MMIS C...Lv._.; Plan will also be made available aAct it is revised Actim N NRC will review our desip process as drambed in the SSAR. RAls and in WCAP 1260I.9887 and the MMIS C...:.v._.; Plan and provide us feedback 4/IS93 - NRC Confermee call (J Hongarra. J mlara, J liiggins.S Kerch J Easter. K Kloes): NRC had reviewed WCAP 12601 and 9817 which was made available in the Rockville ofrece NRC questions as transmrtied by 4/10.95 fax were addreamed Action N: NRC action to =,. based on the 4/1895 discwusons NRC stated that ad&tional information will hkety be needed to eventually close open items I S.2 3.34 In the case of I8 2.3 31.the first four bullets under the mecria may require additional information, although the NRC would provide further W Solutaan may be to revise Q62014 and or Q620 l $ (map to respective procedure in WCAP 12601) to address these fwst four bullets and then to revise the MMIS Developmere Plan to be consistent Action N: NRC action to recaluate based on the 4!! 895 discussions. Following NRC feedbacUclanfication. Westinghouse will send a draft of document addressmg tlus open item. Revised AP600 human factors mg ng progr,a_m plan included as SSAR I2 2 in Revision 9. 7/31196 Page: 4 Tetal Records: I3d

AP600 Open item Tracking System Database: Priject Management Report Date: 11/21/96 Selection: [NRC Branch; Itke WRR/lDIFTr Sorted by NRC Branch i Description Item DSER Section/ NRC Memo (W) NRC No. Branch Question Type Staeus Detail Imt Mod Date Ttatus Status immer No. I Dune 1106 NRR!!!IlFB 122.33-2 D5ER4M v2m c3e ed g u as"s ca.'a al11tn Argner4P [I lWJ.Ja should povide mformation regardmg the llFE pacess management tools. Westinghouse should pevide WCAP-12601. WCAP-9817.OCS-GES41 I, and any ad&tronal documents that descnbe the tools and teelmiques to be usal by the team during the HFE design proceum as identdied in this ("k"** 1 Meeting of 3.995: Adion N: NRC will review our desip pacess as descv. bed in the SSAR. RAls and in WCAP12601.9817 and the MMIS Dc.d.,,. .- Plan and prodde us feedbad. Need to address the tradmg of desim reuew actinn stem chits and the uw of the human factors cheditist. Refer to NRC Iceter of 3/2296 Meetmg of 39.95: Action N NRC will renew our desip pocess as descnhed in the SSAR. RAls and in WCAP I 2601.9817 sad the MMIS Deselopment Plan and pmide us feedhad 4'l 8.95 - NRC Conference call (J llangarra. J O'Itara. J liegens.S Kmh. J Easter. K Klocs) NRC had renewed WCAP 12601 and 9817 wtuch was made availabic in the Rod 6tle ofrece NRC questens as trammitted by 4'I095 fan were adressed Action N: NRC action to re< valuate based on the 4'Is discussens NRC stated that additmnal mformatmn may be needed to eventually close open items I B.2.3.3e. NRC to provide further feedwk. In the case of I B 2 3 3 2. solution may be to rense Q62015 to prodde additional details on the tools and techmques (e g. review forms) that are used by the llFE design team to emure thev futt6tl their responsibilities Renw the MMIS Development Plan to be consistent. Action N NRC action to re<s atuate based an the 4 i R 9t discussions Follmnng NRC fectback/ clarification, Westmghouse will send a drd of dam addressing this open stem Revised AP600 human factors engineering pro. pam plan included a.s SSAR I R 2 mi Redsaan 9. 7/3 l!% ._ = :. = - - - - - t Page: 5 Total Records I34

W AP600 Open Item Tracking System Datch:.se: Przject Management Report Datn I1/21/96 Selecties: [NRC Branch) like NRR/lD Elr Sorted by NRC Branch Descrytion Itent DSER Sectient NRC Meino (W) NRC No. Ibandt Queshan Twe Status Detail Ima Mod Date Status Statua timer No. / Daar b f Ss A 1307 NRR!IIIIFB I82.3.3-3 D5ERol W2p6 Clamed Samm6eeul acw a os cilslu) [ W"f . should prowle information regarding the muegration of design activities W.- J sfiould provide WCAP-12601. WCAP-9817. OCS-OES411, and any additional domments that desenbe the intryation of the design activitwo of the HE demipt process sa idevained in this criterian Meding of 3.995: Action N NRC will review our design process as desenhed in the SSAR. RAls and in WCAP 12601. 9817 and the MMIS Developnent Plan and provide us feedback. Per NRC letter of 3 22 96. SS AR revision needed for closure Revised AP600 human fadees enginemng propam plan included as SSAR 18 2 in Rension 9,7/31/96. Meetmg of 3 995. Action N NPL uill review our design pacess as descnhed in the SS AR. RAls and M WCAP 12601,98I / and the MMIS Development Plan and prewide us feceack 4'lB 95 - NRC Conference call (J Hongarra J O'llara, J liiggun S Kerch, J Fmter K Klocs) NRC had reviewed WCAP 12601 and 9817 wtudi was [ made asmilable in the Rockvdle office NRC questions as transrrutted by 4/1095 fax were adre. sed Action N: NRC action to remluate based on the desmssions NRC stated that addstional information may be necdrd to eventually close open items I 8.2.3.3e In the case of I t 2 3 3-3. solution may be to revise the MMIS Devel<yment Plan by adding a section 4 5 titled "Intepetion ofIIFT and Other Plant Design Actinties" and describe exarryles of integation and how it is deme (e g, SSD sections 7,8. allocations; FDT A output and venfication of I & C needs; ERGS ERG I & C task analpis; ) Another ogeon would he to irulude this info in Q62015 revision and then later in the development plan for consistency. Action N NRC action to re-evaluate based on the 4/ I R 95 discussions Following NRC fecesck/clanfication, Westinghouse will send a auft of &cument addressing this open item by 6/23 95 l t Page: 6 Total Records-134

AP600 Open Item Tracking System Datdese: Prrject Management Report Date: 11/21/96 Selecties: [NRC Branch] like WRR/ID DTr Sorted by NRC Branch Desceiption item DSER Secticn/ NRC Memo (W) NRC No. Brandt Questime Type Status Detail Imt Mod Date Stansa steams tener No. / Dee NU b(1/1/16 ) 130s NRR/lfHFB 18233-4 D5ER ol 7/26 S6 Closed Simmeset"

w. 1 ner.x gl Westeghouse s%ould povide information regenhng the IIFE pogram nulemanes. W

-f -- - should povide WCAP.12601. WCAP.9817.06S4ES-08 I, and any ad&tional documents that descnhe the IIE prngram nulestones as identirmed in this critanost NtY E.J;V i dd Fif 30C Meeting of 3,9.95: Actson N. nil C will resiew our desip process as desvihed in the SSAR. RAls and in WCAP 1260l,9887 and the MMIS Dc.-4,..: Plan and pmvide us fee 4mk_. r Resolved ~ ~ ~ ' ~ i Per NRC lettee of 3 '22 96 Formal SSAR revisen needed for closure Redsed AP600 human fadors engmeenng pogram plan included as SS AR 18 2 in Re6sion 9,1/3196 Meetmg of 3 9 93 Action N NRC will reues our design process as descnivd in the SSAR. RAls and in WCAP12605,9817 and the MMIS Deselopment Plan and gworide us feedhmk 4'1895 - NRC Conference call (! Honga n. J trilara, J Ibggms.S Kerdt J Easter K Klocs)- NRC had reh WCAP 126n'.nd 9R 87 which was made availahde in the Rockville ofrece Nt:ynestions as transmined by 4<1095 fax were adresse s Act% N NRC action to re< valuate based on the awussions NRC stated that adetmnal information may be needed to eventually close open iam iS.2 3.3a in the caer of Ia 2.3 34 solution may be to revise the MMIS Development Plan by adding a subsectwn to sectinn 3 0 titled " Relative Schedule of HFE Pmynen Milestones * (use the sieriphried MMit Desigri blod diayam that uas presensed dunng March 9 meetmg ) and revise the Scheduled FOAKE Tasks and C.. ~ _..;. subsection to reflect the current FOAKE mhedule (use the high lesel har paph schedule ) L Action N. NRC action to re-evaluate based on the 4'1895 descussens. Following NRC feedhnck/clanfication. Westengliouse will send a draft ot' [ document addressing tius open item by 6/2391 i =. -. __ _. l I i i I Page: 7 Total Recorde: 134 m

AP600 Open hem Tracking System Database: Praject Management Report Data: 11/21/96 Selection: lNRC Branchilike WRRAUIFir Sorted by NRC Branch Descoytion liam DSER Section/ NRC Memo (W) NRC No. Brandi Questenn Twe Status Datait last Mod Dane Status Stamaa tasar No. / Dane 1309 NRMlHFB 18 2 3.3 $ DSERol 7/M96 Clamed Remot M M V Y # D & /5( 0$/f$ [l Westinghouse should provide IIFE dansmersation Wessinghouse should povide WCAP-12601, WCAP-9817.OCS4)E3411, and any addstional documents that desenhe the llFE docenmtation and associated pacudures as idmenfeed in this cnters<t Meeteg of 3 9,95-Action N: NRC will resiew our design process as descnbed in the SSAR. Rats and in WCAP12601,9217 and the MMIS Da-4._.; Plan and provide us Iceenck Closed NRC considers this open stem *resolser pn NRC tetter of 3 2296, but they do nce vecify any further actions that are needed such as a SS AR revision I heheve that no further action is requered Meeting of 3'995. Actmn N NRC wili review our design process as descnhed in the SSAR, RAls and in WCAP 12601,9817 and the MMIS l Development Plan and pmide us feedhad I 4:1895 - NRC Conference call () Ikegarra. J O Hara, J Ifigsms.S Kerch J Faner. K Kloes) NRC had reviewed WCAP 12601 and 9817 which was made available in the Rod sille office NRC questions as transmitted tw 4 'I0 95 fas were adressed Acthm N. NRC action to r. wa;uate based on the discussions NRC so ed that additionalinf.wmation may be needed to eventually close open seems 18 2.3 3e in the case of Ilit D-5. further clanfgation is neede.' from NRC Action N. NRC actian to re-evaluate based on the 4/It'95 discussions Following NRC fee &ack'clanfication. Westinghouse will send a dreA of document addressmg this cpen item by 6'2F95. Revised AP600 human factors engineenng program plan included as SSAR IE 2 in Revision 9. 7/3196. .. = _ _ - _ -. _ l l 1 i Page 8 Total Records: 134

AP600 Open Item Tracking System Database: Project Management Report Date: 11/21/96 Selecties- [NRC Branch) like NRR/lDIFB' Sorted by NRC Branch Descns*on finn DSER W NacMemo (W) NRC Na Ikaruh Queshen Twe sianus Detail im Mod Dese Staama !hanna im Na / Dame 1310 NRR/lHIFB 13.2.3.3 4 DSERol 7 % 96 Cloaad 8 -==k==J /3Cf* At Cid /No WhN 8/ Westinghouse should provide informahon regarding the conytiance of the HFE sulummeractor wit! 'tFE seguir==== W ' f shoesid provide WCAP.12601, WCAP-9817. OCS4ES4II, and any sabtional &runnents that dracrihe how the shoonernaar% = with INE regasunents is g []/ f.: )fJQc/[Hf Meeting of 3 9.95. Action N: NRC will review our design pocess as desenhed in the SSAR, RAls and in WCAP 12601,9817 and the MMIS Developrnent Plan and prende us feedback. Per NRC twetter of 3'2296 Iormal SSAR revsion is needed Revised AP600 human factors enmg logram plan includc<l as SSAR IB 2 in Revisi m 9,7/3I/96. Meeting of 3 9 95-Action N NRC wit! review cur design pacess as descnhed m the SSAR, RAls and in WCAP 12601,98 !.ind the MMIS Developmere Plan and provide us feedhad L 4'l8.95 - NRC Conference call (1 flongarra, J Ollara, J liiggms.S Kerch, J Easter, K Kloca) NRC had renewed WCAP 12601 and 9817 which was made available in the Rodnlle o&c. NFsC questions as transmetted by 4/1095 fax were adressed We staaed that HFE . "-. ;.u were given to subcontractors alwough (1) the fact that WCAP 12601 is given to all subcontradors a:wl all must follow its twoce&srea in consent and format Ex. AP3 I tections 2g, 5,6h and 7 are cumples of IIF considerations ; and (2)ifrough the fact that general design criieria are given to all subconeractors that are i eNetted by them - Et I A C General Design Cnteria, sc< tion 7. The tectmical document control procedsres govern the disenbution and release of AP600 l documents (AP 6 t,6 2 and 6 3) Pronde this answa in revision to Q620 I 5 as Jim suggested or a&l a subasction to section 4 0 of the MMIS Deveformere Plan Action W is to make the I & C Genna! Design Critena Dxument available in the Rockville office for their review and also proof that it went to applicable l suhcentractors. e 25/95 - Fat sent to J Bongarra and J 0rliara that provides a response to this open item. The IAC General Design Criteria docueners was placialin the 4: Rocknile office (b) A.Sterdis, attending an NRC meetmg in Rocknlle) Actim N. The NRC to renew the response and drtermme whether it is acceptable' provide feedback. [ Revised AP600 human factnes engineenng program plan included as SSAR l8.2 in Revision 9,7/31/96. This includes SSAR I2.2.3 5,ilFE in Subcontractor ENorts i-I 1 Page: 9 Total Records-13d

= _. e AP600 Open Item Tr:cking System Database: Prrject Management Report Date: 11/21196 Selecties. [NRC Branchj like NRR/lD D'B" Sorted by NRC Branch Desmptim item DSER Section/ NRC Memo (W) NRC No. Branch Quemason Type Status Detail Imt Mod Dese Status Sessus laear No. / Duse 131I NRR/HHFB IE 2.3 4-1 DsERot 9 t9% Clamed Action N # Westinghnume stumid povide information regardmg the HFE issues tracing eynaem avastability. W j sianuhl sulunit WCAPs-9365.12601, and d/ 9817, as well as any addnional dncuments that desmhe the tracking sprem and checitists as idessedied in this critanost pU.[M f2 /cfrQo.s7~ Meetingof 39.95: Westmghouse desmbed our drsip issues tracking sprem. Tracting of HFE related desip issues is not a separuse eseitiy but is part of the overall AP600 i desip process and desip issues tracking Processes for tracting desip issues, includes HFE issues, are (l.) the DCP process as deambed in WCAP 12608, AP3 2; (2 )the desip review process as desmhed in WCAP 12601. AP 3 5 and WCAP 9817(human factors cluicklist); (3 ) t'ne of SSDu. AP 31 ansd AP314 of WCAP 12601. Also a meners guide exists for SSDs. The Interface Requimnesses or the Human Factors Requimnents of the SSDu will be used to document and track IIFE related issues not curmely addressed by the desip and idereified prior to DCP or desip review. Feel closure of these issues is vmfied in the tahdation of the llSI versuses their functional requirements (This desenption also applies to open nems I B 2.14-2 thru 4-4 ) Adion W: --~ Per NRC letter of 3 '22 96 the NRC stated that they found our llE issues Tracking Sptem described in the draR o(I B 4 4 as acceptable, but they warned to know when ther cnutd visn us and vmfv its implementation At this point. the red team decided that our systrai(as describert in the draft of I B 4 4; had some poblems and might not pass an inspection from the NRC. Intemal nwetings are planned to discuss nioderscusions to the trackmg system Meetagof 39/95: Westinghouse desmhed our desip issues tracking speem Tracking of HFE relased desip issues is me a separate entatiy but is part of j the overall AP600 desip pacess and design issues tracting. Processes for tra ting desiphe inch % HE issues, are (I.) the DCP process as desmhed in WCAP 12601. AP3 2. (2 )the desip review process as desmhed in WCAP 12601, AP 3 5 and WCAP 9817(human factors checilist); (3 ) Use of SSDs - AP 3 I ansd AP314 of WCAP 12601. Also a wnters guide exists for SSDs The traerface Requirsemets or the Human Factors Requirements of the SSDs mill be used to document and track HFE related issues nne curternly addreened try the demip and identified prior to DCP or desip review. Final closure of these issues is verified in the vahdation of the llSI versuses their functional requirusneras. (11ais descriyeion abo applies to opm items I E 2 3 4-2 thru 4-4 ) Aho consider using the URD comphance dataSase as another niethod used to track desip issues. 4'l895 - NRC Conference call (J Bongarra,3 Orliara, J liiggms.S Kerch, J Easter, K Kloes) NRC had reviewed WCAP 12601 and 9817 which was made available in the Raciville office. NRC questions as transmated by 4/1095 fax were adressed. NRC sessed to be sure to include in the revismn to Q62015 a desmption of the cutoff poun for closure of design review adeon item chas (stupment of the product -if any -. - '

chits, then per NQA-l the customer must be informed )

Instead of resisson 2 to Q62015, Westinghouse will sent a drall of SSAR section I E 4 4 (lf fE issue Tracking) to the NRC lufFB Action N-NRC action is to review this draft and povide fee &act Revised AP600 human factors engmee ing pogram plan included as SSAR IB 2 in Revision 9,7/31/96. This inchades SSAR 18.2.4, Human Factors Engmemng Issues Tracking. t P Page: 10 Tolet Records: 134 i i l

m _ ___ -~ o AP600 Open Item Tracking System Database: Pr: ject Man:gement Report Date: 11/21/96 Selection: [NRC Brrnch] like 'NRR/IDIFB' Sorted by NRC Branch v Descngsson Item DSER Sah NRC Mems (M NIC No. Drardi Question Type Status Detail tast Mod Dsac Stanus Stanus I ma-No. I Dane 1312 NRR!HHFB 122.34-2 D5EROI W19% Clemed Adian N < pv.9 ss-L gg - hould provide infonnation regenhng the HFE issues trackang symem method W f - M ndunit WCAPa-9565,12601, and W-f p s 9237. as well as any additional documems that desenhe the method for handhng HfE issues as idereafind in this maarvan. eJ. f hftfitAy" g6* Action W: Per NRC letter of 3'2296, the NRC stated that they found our llFE issues Trmting System dencnbed un the draA of 18 4 4 na =-. - but they warned to know when they could visit us and venfy sts implemmtation At this poet, the red tearn decided that car system (as dracnbed in the draA of I 8 4 4) had some problems and might not pass an inspection from the NRC. Internal meetings are planned to discuss.. ' _ ' - ' to the tradung system. Meeting of 3995-Westinghouse descnhed our desip issues truling system Tracking of HFE related deaip issues is not a separate ene tiy but is part of the overall AP600 desip process and desip issues tracking Processes for tracking desip issues, including HFE innsen, are (I ) the DCP process as descnhed in WCAP I2601. AP3 2. (2 ) the design review pmcess as descnbed in WCAP 12601. AP 3.5 and WCAP 9817 (human fat 1 ors chedlist). (3 ) Use of SSDs. AP 3 I ansd AP3 I4 of WCAP 12601. Also a wnters guide exists for SSDs The linerface Requiremeses or the Human Factors Requiremeras of the SSDs will he used to document and track llFE related issues not narrently addressed by the deaip and idnenfied pior to DCP or design renew. Final closure of these issues is smfied in the tahdation of the 1151 versuses thew functional..' (This desenreion also aryhes to open items I t 13 4-2 thru 4-4 ) Alm cnider using the t'RD compliance database as another nwthod used to track design issus - t 4'l 295 - NRC Conference call (J Ibngarra, J 0 Itara. J liiggins.S Kerch J Faster, K Klocs): NRC had reviewed WCAP 12601 and 9217 which was made available in the Rockulle office NRC questions as tranmutted by 4/1095 few were adressed NRC sessad to be sure to include in the rmsion to Q62015 e desenpaiun of the cutoff point for closure of denen review actinn item ctuts (shipmens of the product - if any custanding chsts, then per NQA-I the customer must be enformed ) Instead of redsion 2 to Q62015. Westmghouse sent a dran of SSAR section I8 4 4 (HFE issues Trackmg)to the NRC HHFB. Action N-NRC action is to review this dran and provide fee &ack Revised AP600 human factors engmeenng program plan included as SS AR I2 2 in Revision 9. 7/31% This unchsdes SSAR I8 2 4. Iluman Factors I -Engineenng issues Traciting s 5 f I h t I C Page: 1I Total Records: 13d

AP600 Open Item Tracking System Database: Prcject Management Report Date: 11/21/96 Selection [NRC Branch l tike 'NRR/IIHFir Sotted by NRC Branch 1 Descrgtion item DtER SM NRC Menum (W) NRC No. Brancia Question Type Staeus Detail Imt Mod Date Status Stasus temar Na / Dane 1313 NRR'HHFB IS.2.3 4-3 D$EROI 9/1996 Cleasd Action N b#$ M M W9/41 g/ Westinghouse should provide mformation regenhns &e HFE issuem tracting speem h w - f - lwuld sulunit WCAPe-9565,12601, s and 9817, as well as any addnional documents that descrae the method for documenting HFE issues as idenedied in &is criternest g - h f a dtO cte J I Action w; Per NRC letter of 3/2296, the NRC stated that they found our flFE issues Tracking Speem demaibed in the dran of I t.4 4 as==tedde, but they wanted to know when they could visit us and vmfy as implementation At this point, the red team decided that our systern (as drambed at the draR of it 4 4) had some problenn and might not pass an empection from the NRC. Internal enectings are plarmed to discuss modifications to the tracking systent Meetes of 3995: Westinghouse desmhed our desip issues tracking system Trackir g of HFE relmaed desip issues is not a separase antaiy but is part of the overall AP600 desip process and desip issues tracking Processes for tracking desip issues, including HfE issues, are (l.)ihe DCP pmcess as desenhed in WCAP 12601 AP3 2; (2 )the desip review process as descritmlin WCAP 12601, AP 3.5 and WCAP 9817 (hisnan fa tors clieckItst); (3 ) Use of SSDs. AP 3 I ansd AP) 14 of WCAP 12601. Also a writers guide exists for SSDs. The Interface Requirements or the Human Fadas Requirements of the SSDs will he used to dacument and track I!FE related inmes rud cumntly addressed by the dreip and idesstdied prior to DCP or desip resiew. Final dosure of these mues is senficd in the salidation of the IISI versuses their ibactional recpsirements (This descnption also applies to open items 12 2 3 4-2 thru 4-4 l Also c.muder using the UPD cerryliance database as another method used to track desip issus 4:1 E.95 - NRC Conference call (J Ilongarra, J O'llara, J liiggins S Kmh, J Easter, K Klocs)' NRC had renewed WCAP 12601 and 9817 which was inade available an the Rockntle office NRC questums as transnutted by 4/10.95 fax were adressed NRC stased to be sure to include in the rension to Q62015 e descnption of the cutoff poord for closure of desip review action item chits (shermend of the product -if any oustanding chsts, then per NQA-1 the customer must be informed ) Instead of rension 2 to Q62015 Westinghouse sent a draft of SSAR section i E 4 4 (IIII Issues Tracking) to the NRC HHFB. Action N-NRC action is to renew this draft and gwoside feeenck. Revised AP600 human factors engineering progam plan included as SSAR IE 2 in Resision 9,7/31/96. This includes SSAR IS.2 4 Human Factors Engineering Issues Tracking Page: 12 Total Records: 13d

6 AP600 Open item Tracking System Databi.se: Prsject Management Report Date: 11/21/96 Selection: (NRC Branch] like NRRA D D'D' Sorted by NRC Branch 4 Descrytion item DSER Section/ NRC Memo (W) MC No-Branch Question Type Status Detail tast Mod Dat, status Stansa Imm No. / Dane 1314 NRR/HHFD 182.344 D5ERot S tem Clceed .M in SN I KEsaw.GA MA lfl1lfh .g/ Westinghouse should preside information regardmg responsebil:ty for the IIFE ismen tracitsng synema. W j . aliould ashenit WCAPa-9565, 12601, and 9817, as well as any addsteenal docurneses that describe the resposenbilities of persosueel urvolved in die tradurg and ruolutson c(HFE issues as ident fied m this criterun. - _. Resolved Pn NRC letter of 3/22'96. Closure requires formal revision to the SS AR. Revised AP600 lusman factors engmeermg program plan included as SS AR I 2 2 in Revision 9,7/3 I/96 This includes SS AR 18 2 4, Iturnan Factm Fagmemng issues Tradmg Meeting of 39 95. Westinghouse desenhed our desip essues tracking system Tracking of HFE related desip issues is not a separate eiwitry but is part of the overall AP600 desip pocess and deup issues tracimg Processes for tracking design issues, includsng HFE h are (I ) the DCP practum as desenhed in WCAP I2601, AP3 2 (2 )the desip renew pecess as descnhed in WCAP 12601, AP 3.5 and WCAP 9817(hurnen factors checitlist), (3 ) Lise of SSDs - AP 3 I ansd AP) I4 of WCAP 12601 Also a writers guide exies for SSDs The Interface Regsirternents or the llumen Fade Requirements of the SSDs %ill tw used so Josenent and track llFE related issues not currently adchessed by the design and idnwiico prior to DCP or desip review final closure of these iuucs is senfied m the vahdation of the list wvsuses their functional requirvenents. (This dencngtion also applies to open items I t 2 3 4-2 thru 4-4 ) Also consider usmg the L'R D comphance database as anotlier method raed to track design issues 4/l 895 - NRC Conference call (J lbngstra. MYllera, J liiggms.S Kerch. J Easter, K Kloes) NRC had reviewed WCAP 12601 and 9817 whid was made available in the Rockville office. NRC questions as transnutted by 4/10<95 fax were adressed. NRC asad to be sure to include in the rmsion to Q62015 a descnpaion of the cutoff point for closure of desip review action item (hits (shipment of the product -if any custaruhng cluts, then per NQA-1 the customer must he mformed ) Instead of resision 2 to Q620 I S, Wegenhouse nern a draft of SS AR section I 8 4 4 (IIFE lsmues Tracking) to the NRC 1I11111. Action N-NRC_ action _i_s to renew this_dr_ aft and proude lie &_ai_ 1313 NRR/IIHFB 18235-I DSE R ot 73 % Cgoned I U' f IMk_ WAoM cKAA/f/fD g7l Westmghouse should provide information regardmg the IIFE pogram elements and docunieventsort Wesdnghouse should descnhe the programmatic relationship between the llFE pogram and PR AllRA related actiuties, as well as the IIFE program eacurnentation for OER, IIRA, and TAE admtics Actuwt W: Reuse SSAR section 12 8.2 I (MMIS Desip Process) to include details of nutial assumptions and starting poets foi the llFE design process and to clanfv the initial fundian allocations and control ronm resource selc<tions (URD forms irtput to the HFE process and hesis for these assungtions) include lira OER, and test & evaluation resuhs as an input to the design process (refer to DSER eval section for this open item). Reference the llRA-ilFE Integration implementation Plan document in the SSAR section Draft of these revised SSAR sections will be acre to the NRC. MMIS Development Plan needs to be consistent Revised Cha:Wer 18 of the AP600 SSAR suberutted in Revision 9,7/31196 Page: 13 Total Records 134

a AP600 Open Item Tracking System Datab:se: Pr: ject Management Report Dat:: 11/21/96 Selection: [NRC Branch] hke NRR/lD[FTr Sorted by NRC Branch 4 Dewrysim item DSER SM NRC Merno (W) NRC No. Brandi Quesason Type status Detail Imt Mod Date Stasus status taear No. / Dune 1316 NRMillfil 18.3.311 DSEROt Ifv2V96 Clamed Resnived NTD-NRC-94845 l Westinghnuse should provide a carpenson to pedecesarv plants and systems Westmstumane should describe how sincy will apply the lowtressere reference plant concelg to the OER. and then apply it appstyriately in the performance of a review of cyerming eitperissice Per conference call with NRC (J liongarra. G Galletti. J 011 ara. J Ifiggms) of 2'23 95: i Action W - NRC says that rev I to R Al Q620 9 dnes nnt completely clanfy Westinghouw to review *llFE Insights For Advanced Reactors Based tiron Operating Expenemce' transmetted to Wesimatwusse en 2/13 95 Place rhis stem on 3'8 nacrmla. klectmgof 3995: Action W. Westmghouw to perform an OER that addresses open items t 8 3 31.I thru l-3,2-1 thru 2-3 In the OER report we wdl clanfy that OER d d not reflect the low-preuure plant es the pedecessor reference plant We udt descnhe the scope of the plam es:penerice reviewed The law pessure reference plant was uwd as the startmg point for AP600 ERG development. but is not the predeccant plant for the OE R. In generst. Wi-4 PWR expenence udt he renewed Also refer to klectmg Open item, dhase seem number 20]6 7 Resolved - Draft OER report provided hv NSD-NRC-96-4722 on 5/I4 96 Chapter I8 of the SSAR to be revised to reference this encummt Revised Chapter I8 of the AP600 SS AR suberuned m Revision 9. 7/31196 OER is referenced in SSAR I 8 3. Formal WCAP transminal will be enade followmg receipt of NRC comments Element 2. l Comments recieved from NRC en 8/13 To cime tius item. SSAR Chi 8 was submitted and we owe a rev to WCAP-14645. Closed wah WCAP subrnistal on 101796 rkn 10'25

=

z=-.= = _. - -=.. _ _. Page: 14 Total Records: 134 i

~ d' AP600 Open Iteni Tracking S; stem Database: Pr: ject Manage nent Report Date: 11/21/96 Selection: [NRC Branch] like NRR/lDIFB' Sorted by NRC Branch D wian item DSER SM NRC Memo (W) NRC No Branch Question Type Status Detail 12st Mod Date Status h tamar No. I Duse 1317 NRR/HHTB 18.3.3.1-2 DSERCI 10/2396 Closed . ". - & NTBNRC-96-4845 Act M g 'k Westinghouse should provide information regardmg ineastry IIFE issues Before prepanns the final SSAR. W ^ - diould armre that the OER addresses the human factors agats of all issues idedified in Amendit B of the PRM and addetaal llFFaelssed e[ersaing empmenm W (e R. NRC //h, bf:dMCAI Iblictins and Generic letters) identified in Chaper 20 of this report. Meeting of 3 995-ActHun W. Westinghouse to perform an OER that addresses open items IS 3 3 I-l thru l 3, 51 thru 2-3. _. ~ _ Resolsed -Ihan Operating E vpenence Review (OIR) report provided by NSD-NRC-96 4722 on $!!496 Chapter IB of the SSAR to be rensed to reference tlus donament Revised Chapter iB of the Af%00 SS AR submnted in Resision 9. 7/3I 96 OER is referenced in SSAR I3 3. Fortnal WCAP transmittal unit he made folloumg receipt of NRC comments Element 2. Commmes reciesed from NRC on t 13 1.3 (lose this item. SS AR Chi 8 was submitted and we c se a rev to WCAP 14645 , Closed with WCAP submittal on IO.17.96 rin 10'25 1318 NRR,IlllFB 18331-3 D$f Rol 1425 06 Closed NRC-96-4845 NYW 1 [b Westinghouse should describe how thev hate included related IISI technologies in the OE R. Meeting of 3 9 95. i Action W: Westmshouse to perform an OER that addresses open items 18.3.31-8 thru l 3,21 tisu 2-3. In the OER report, where there is no nuclear plant expmence for the llSI teshnology being applied to AP600, reference the reports that document research gerformed for operating expenence in other industries Reference to be done hv title, autlw. date (The s,...>..; to perform these reviews for areas where we are intending to apply new technologies is in revision I to RAI 620 9)_ Resolved - Dran OER report provided by NSD-NRC-96-4722 on 3/l4/96 Chapter It of the SSAR to be revised to reference this donsment. Revised Chapter i8 of the AP600 SSAR suhrrutted in Resision 9,7/31/96. OER is referenced in SSAR 18.3. Formal WCAP tr aststtal will he made folkvwing reced of NRC conwnents. Element 2. Comments recieved from NRC on S/13. To close this item, SSAR Chi 8 was submitted and we owe a rev to WCAP-I 4645. Closed with WCAP submittal on 10/17/96 rkn 10/25 Page: 15 Total Records: 134

e AP600 Open Item Tracking System Datcbase: PIoject Manatement Report Data: 11/21/96 Selection: [NRC Branch] like WRR/IIIIFIr Sorted by NRC Branch Descryson item DSER W NRC Memo (W) NRC Na Brandt Question Type Status Detail 12m Mod Date Staeus Staeus letar Na / Duse 1319 NRR/Illtfll 1B 3.3.5-4 D5ERol Ity21M6 Cloned Action N NTD NRC 96 4843 g 7, Westmghnuse should provide information regarding the resuhs of operssor meerviews Westanghouse should povide the cismen and resalts of the operuser g/3' /EUfd: d,8ir(/FT witernews to the staff and L.a es hms they address this criterwwt Aleding of 3 9 95. Action W: Westmghouse to prform an OER that ad& esses open items It 3 31-1 thru l-3,2-1 tlwu 2-3 I Resolved - Draft Of R report subnutted by NSD-NRC-96-4722 on 5/14 96. Chaper it of the SSAR to be revued to reference this docsunmt Revised Chapter 1I of the AP600 SSAR submitted in Revision 9,7/3 f.96 OER is referenced in SS AR IS.3. Formal WCAP tranonuttal will be made followieg receipt of NRC comments Flement 2 Comments reciesed froni NRC on t'll To close this item, SS AR Chi 8 mas suhrmned and we owe a rev to WCAP-l4645. Closed with WCAP subminal on 10:I7 96 ska 10.25 1320 NRR/IlliF11 18332-1 Dsf R ot to75 % Closed Resolved / NTUNRC-96-4845 l, Westmghoanse bid proside information rcgardmg the operatmg esent report (GER) issue analpas Westinghouse should describe how the OF R udt [ ~ h address rssues relateil to human performance and problems and sources of human error in addith Westinghouse should describe how the llTE design addresses the inues raised by the OFR. Alecteg of 3 9 95. i Action W. Wessinghouse to perform an OER that addresses open itens 12 3 31 1 thns 13,2-1 t}ru 2-3. g-i Resched - Draft Of R report suhrmned hv NSD-NRC 96-4722 on 3/I4 96 Chapter iE of the SS AR to be revised to reference this document ? Resised Chapter it of the AP600 SSAR suhnnited in Revision 9,7/3I 96 OE R is referenced in SSAR IS.3. Formal WCAP transmttal will be made ( followmg receipt of NRC comments 1 Elemere 2. Comments recieved froni NRC on S. II To close this nem, SSAR Chl 8 was submitted and we owe a re. to WCAP-14645. I Closed with WCAP submittal on 1017,96 rka 10/25 r Page: 16 Total Records: 13d

{ AP600 Open Item Tracking System Database: Prcject Management Report Data: II/21/96 Selecties: [NRC Branch] like NRR/lDIFir Sorted by NRC Branch Descriptimi s Item DSER Sectmn/ NRC Memo (W) NRC No. Firanch Quemuon Type Status Detail tmst Mod Date Status steams tmar No. / " Date 1321 NRR/IIHFB 183.32-2 D$ERCl 10/2996 Clamed Remotved NTIANRC-96-4845 g'V Westinghouse should prmide exumentation ofits analysis of ryernung expenence Weaungham hould provide an OER repoet thes %-a-ty eruments the results of the reviews and how the fmdmgs are (m will be) addressed by the AP600 Je sign Meeting of 3995: Action W: Westmghouse to perform an OER that addreues open items Ie 3 31-1 thru l-3. 2-1 thru 2 3. The OER repat needs to discuss the llSt OER relative to SPDS. AWARE.COMPRO Resolved. Draft OER repet suhnutted by NSD NRC-96-4722 on 5/I4 96 Chapter IR of the SSAR to be redsed to reference this docurnent Revised Chagter i e of the AP600 SSAR subnutted m Reusion 9. 7 3196 OF R is referenced in SS AR I t 3. Formal WCAP transrruttal will be ende following receipt of NRC corrsnems Elemens 2 Comrnents reueved from NRC on a 13 To close tius acm. SSAR Chi 8 was suhrmtted and we owe a rev to WCAP.I4645. Closed with WCAP suhmittal on 101796 rkn 10'25 =.. .-;v- - =. - = = _ _ _ _ _ _ _.. - - - 1322 NRRAlHFH IB332) DSER CI 14 M% Closed Actaan N/ NTD-NRC-96 4845 Mg Westinghouse should provide information regardmg the incorpws-teon ofissues into the tracting s) item. Wi-gu should describe how each p p s /,f/cp7 operating expenence issue determined to be appropnate for incorpwation into the design is entered into the systeret Meeteg of 3 995. Action W: Wessmghouse to perform an OF R that addresses open items it 3.31 1 thru l-3,21 thru 2-3. W ' f needs to prodde a deussion (at end of OER report) of how we coramue to a&lress OER (,... A.m.;). Informal day to day conunurucations msnmarizmg Genmc treters. Information Nouces, daily Site Sevice manager reports, etc formal process would require a renew and duponnien of those that are issued between design certification and plans order. Also, descnhe how thme Of R life issues rwt currentigddressed in the AP600 design are ensered into the trading system Drall OER report suhrnitted by NSD N RC-96-4722 on 5/I496. Chapter i2 of the SS AR to be revised to reference this document Revised Chapter 19 of the AP600 SSAR sulmutted in Revision 9. 7/31/96. OER is reference in SS AR I 8.3. Tracking syssem i %hed in SSAR 1324 Formal OER WCAP transnuttal will be made following receipt of NRC comments. Elemmt 2 Cornments recieved from NRC on 8/13 To close this item. SSAR Chi 8 was submitted and we owe a rev to WCAP-14645. Closed with WCAP submittal on 10/17,96 rkn 10/25 Page: 17 Total Records: 134

e AP600 Open item Tracking System Database: Project Management Report Date: 11/21/96 Selecties: [NRC Branch] like NRR/1D DTr Sorted by NRC Branch e Dmrigeion Item DSER Sectumf NRC Memo (W) NRC No. Brandi Queshan Type Status Detail Last Mod Date Staeus Stense f anw No. / Dane 1323 NRMfHFB l8 4 3 l-l D5ER G I414 % Clemed Resolved # NSD-NRC-94231 Westinghouse should povide information regarding the source mesmals for the revirananas analysis " ' " g. W ^f should ideery the y edustry standards, guidelines, or padices used to perform the funasonal raguirements analysis Meeting of 3 993: Actean N Westinghouse has askeJ that element tiere he reviewed at the corylete elemeva level NRC to revisit the aitma for element 3 (15 opm items. II 4 D_'Ti"P".* Ie_ sedy,,o,,fjssues based on ou discussion. Refer to new meeting open item whidi is dahase Item Number 2064 I Meetmg of 3/9.95. Action N - Westinghouse has asked that elemme three he reviewed at the complete element level. NRC to rensit the criteria fa elemevd 3 (15 open items. I R 4. ) and retropose a focused set ofissues based on our discussion Refer to new meeting open item whidi is dabase hem Number 2064 Action W Docunient (sent bs the NRC en 5'l3 95)that refocuses the element 3 open items uas received on 5/22. Westinghna : will provide a drnA response to this docurnent Draft WCAP 14644 submitted tw NSD-NRC 96-4722 on 5/1496 Chapter i B of the SSAR to be revised to reference this document. Revised Chapter I e of the AP600 SSAR suhmitted in Rewsion 9. 7I3 t S6 WCAP-l4644 is referenced in SSAR 18 4. Functional Requirements Analysis and Allocation f armal WCAP teansmsttal will be made following receipt of NRC comments Element 3 Comments Recieved from NRC on 811 To close this item. SS AR Chi 8 was suhmined and we owe a rev to WCAP-14644. Closed - In reference to letter NSTANRC-96-483I dated 9 (k1oher 1996 t h r Page: I8 Total Records 1 34

a AP600 Open Item Tracking System Det.; base: Pr: ject Management Report Date: 11/21/96 Selection: [NRC Branch] like WRR/IDIFB' Sorted by NRC Branch e Desmgemn Itcen DSER Sectant NRC Memo (W) NRC No. Branch Oe Type Staeus Detail tmi Mod Dese Staeus Stasma I.amar No. I Dase 1324 NRMIHFB IB 4 3.2-1 D$ERot tort &96 Closed .Amenan-w NSD-NRC.9W31 Ae r rJ Westenghouse shculd provide information regartlang the functsonal analysis methods W^ j slaould dsambe the procesa for h W= /y) analysis m..,1^.a. and accuracy MA gg. M. 4 2 f.)(_>P-/yf yy Mating of 3.9 95: o 4 J W, O' UO W l'Y L I# 7 Action N - Westinghouse has asked that element tiree be reviewed at the complete elemas level NRC to revisit the critaria for elevnere 3 (15 open itsens. 18 4...) and retropose a famed set ofissues based on our discussion. Refer to new enceting open itern which is dabase hamn Number 2064. g,w ~ ~ - ~ Meeting of 3 995 Action N Weemshouse has asked that element three he reviewed as the corigdete elenisse level. NRC to rnisit the enteria for elemmt 3 (15 open items; I R 4 ) and re-propose a focused set ofissues based on our discussiort Refer to new enerting open iteen whkh is dabase item Number 2064 Action W. Dncument (scre in the NRC on 51595)that refames the element 3 open stems was received on 5/22. Westinghare will provide a draft response to this exument DrnA WCAP-14644 submmed in NSD-NRC 96-4722 on 5!!4 96 Chapter 18 of the SSAR to be redsed to reference this docuenent Redsed Chapter 18 of the AP600 SSAR submined in Revision 9. 7/31/96 WCAP-I4644 is referenced in SSAR 18 4. Functsonal Requiremmts Analysis and A!!ocation. Fermal WCAP trammettal will he made followmg receipt of NRC comments Element 3 Comrnents Recieved from NRC on tel) To close thes stem. SSAR Chl t was submmed and we owe a rev to WCAP 14644 Closed la reference to letter NSD-NRC.96-.tt3I dated 9 0ctober 1996

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4 AP600 Open item Trccking System Database: Prtject Management Report Date: 11/21/96 Seleciles: [NRC Branch] hke NRR/lDIFIr Sorted by NRC Branch a Description item DSER Satsm/ NRC Memo (W) NRC No. M h-T3pe Status Detail ime Mod Date stanis 9tanus .sw No.I Dese 1325 NRRsNHFB 1843.2-2 DsElt ot sort 496 Classal - ta. Je-NSD-NRC-96-4331 h er N Westinghouse hid provide a detailed desenytmen of enodified functions. Westesghnuse ahnuld espond die angsrison h k plaat and g3 the Al%00 to include an analysis of plant safety fundtions and pmcesses Meetingof 3995: J / M, s' M y Action N - Wessinghouse has asked that element three he reviewed at the complete element level NRC to revisit the criteria for clanent 3 (15 open iurns. M , t-II # d ""d "_T'"P***

• I"i 'I'""'5 M "" *"' discussion Refer to new g open item which is dahame item Number 2064.

.e Meeting of 3 995 Action N - % estenghouse has asked that element three he reviewed at the conglete element level. NRC to rnish the criteria fcw elemeen 3 (15 open seems. I e 4, ) and re-propose a focused set ofissues based on nur demasseort Refer to new meetmg open item Ah is dahase Itan Numher 2064 7 Action W: Docuenent (sent hs the NRC em 5 I S 95) that refeses she element 3 open items was rueived em $/22. Westinghou e will pro *ide a draA response to this document j DraA WCAP-14644 suhnutted by NSD'NRC-%-4722 on 5'l496 Chapter i3 of the SSAR to he revised to reference this documere Revried Chapter 13 of the AP600 SSAR sulmuned in Revision 9. 7/3196 WCAP 14644 is referenmlin SSAR It 4. Functional Requiremeras Analwis and Allocation. Fermal WCAP transmettal will be made following receipt of NRC ciwnments Element 3 Comments Recmed from NRC nn 2:11 To close this stern. SS AR Ch! 8 was submined and we owe a rev to WCAP-14644 Closed - In reference to letter NSD-NRC-96-421I dated 9 (Moher 1996 i l I Page: 20 Total Records-134

+ AP600 Open Iteni Tracking Systen Database: Praject Management Report Dat2: 11/21/96 Selection: [NRC Branch] hke NRR/lDIFB* Sorted by NRC Branch Descrytion Item DSER Sectionf NRC Memo (W) NRC No. Ikanch W Twe Status Detain ime Mod Date Statua Staeus tener No. / Dune 1326 NRAHHFB is 4,3.2 3 DSER4M tryt4w closed M NSD NRC 96-483I Aer& g Westinghouse should identify and desenhe the basis for the modified functuwe and pmceanes Mating of 3 9.95. g Action N Westmghouw has asked that element three he reviewed at the conylete elemme level NRC to revisit the craccia for element 3 (I 5 open items; je/ 18 4..) and repopose a focuwd set ofissua hered on our discussiori gf pt* ~ Refer to new meeting open item which is dahase Item Number 2064. f Meeting of 39 95-Action N - Westeghouse has aded that element three he ruwwed at the complete element level NRC tc remit the criteria for elemeis 3 (15 gen itens; I R 4.) and re-propow a focuwd set ofissues based on our discussion Refer to new meetmg open item atuch is dahase Item Number 2064 Action W Document (sent hs the NRC on 5 IS 95) that refauws the element 3 open items was received on 5/22. Westir. ghon =e will gronde a draft respome to this documme Draft WCAP.I4644 suhmened in NSD-NRC 96-4722 on 5'l4 96 Chapter IR of the SSAR to he revised to reference this docummt Rensed Chapter iR of the AP600 SS AR submitted in Revision 9. 7/3196 WCAP.I4644 is referetwed in SSAR I8 4. Functional Requremmts Analysis ami Allocation Formal WCAP trammettal mill he made followmg receipt of NRC comments Ilement 3 Conunmts Recieved f w. RC on R. I 1. To time thes item. SS AR Chl t was submdted and we owe a rev to WCAP-14644 Closed,In reference to Iceter NSD.NRC.96,-4231 dated 9 (Mober 1996- -. _. _..

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AP600 Open Itesa Tracking System Detaltse: Praject Management Report Date: II/21/96 selecelee- [NRC Branch] like NRR/lDIHr Sorted by NRC Branch Description item DSER Sectanar NRC Mano (W) NRC No. thench Wm Type Status Detail last Mod Date Status Status laamr No. I Duse 1327 NRR!!!HM 18.4.3.2-4 DSERCI lovicM Closed AsheurW NSD NRC-904831 A47"AJ q' W" J _ shnold ponde infmnation regening the method-ological concerns wnh plaw pecuse 4, W j should addrums methodological concerns to provide assurance that there are no genene poblans with the analysis method Specifically (a) the RCS mass invensory MTA i should be cornpleted,(b) the topical report refwenced on page 4 should be includal (c) the basic goal for hidi mese invencry should be addrumed,(d) {

1. lAy /

omission of the "ultsmate cooling" injedian supply should he cylained and justified, and (e) the function oflisted valves should be presidnt t \\ Per conference call mth NRC (J Hongarra, O Galletti, J O'lIarm, J Higgins) of 20395: Action W - Send the remed RCS Mass Inventory F'ITA and send the RCS Pressure Centrol FBTA. Afceting of 3 995. f Adeon N - Westmghouse has aded that element three be reviewed at the complete element level NRC to revisse the criteria for element 3 (15 open stans. IS 4. ) and re-propose a focused set of issues ba_ sed on our discussion Refer to new meetmg open item which is dabane item Number 2064 i kleeting of 3 9 95 Action N - Westmghouse has aded that clanent three he reviewed et the complete elemew level. NRC to revisit the maaria for clanent 3 (15 open st IS 4. ) and re propose a focused set ofissues based on our discussion Refer to new meeting open itan which is dahase item Number 2064 Action W. Document (sent by the NRC on 5'1545) that refocuses the elenwnt 3 open items was received on 5/22 Westinghouse mil provide a dr requese to thes document t Draft WCAP-14644 suhmined hv NSD-NRC-96-4722 on 5'I4 96 Charter IR of the S$AR to be revised to refernice this docei Revised Chapter iB of the AP600 SSAR solmuned in Revision 9. 7/3196 WCAP-14644 in referencalin SSAR 18 4, Functional Requiremf and Allocation Formal WCAP transminal will be maJe follouing receipt of NRC comments Element 3. Comrnents Recieved from NRC on R'l 3 To close this item, SS AR Chi R was suhnuned and we owe a rev to WCAP.14644 Closed. In reference to letter NSD-NRC-96-4811 dated 9 (Atober 1996 i i Page: 22 Total Records-134

AP600 Open Item Tracking S.s stem D:t;bIse: Prrject Management Report Date: II/21/96 i Selecties: [NRC Branchl like NRR/lDIHF Sorted by NRC Branch + I Descrignien hem DSER Section/ NRC Memo (W) NRC No lhundi Question Type Status Detail Imr Mod Date Staeus stasus tomer No. / Dese 132s NRR/HHFB 18.4 3.2-5 D$ER ot twl496 Closed ,AsasserW NSD-NRC-9483I 4FJ gj Westinatiouse should povide detailed descripions for all modd'ied plant processes Per conference call with NRC (J Ikegarra, G Galletti. J 01f are, J Higgins) of 2/2313: g Action N - NRC to review the material presented on 2/293 by Terry Schuti(AP600 fueW.d assaisted grocemes, comparison with curreve 6gMy Westinghouse PWRs) and provide feedback (new status) g Afecting of 3 995 r Action N - Wecinghouw has aded that element three he reviewed at the complete element level NRC to revisit the criteria for elemere 3 (I S open items; 18 4 ) and re-propow a focused set of inues based on our discuuion Refer to new mestag open item ufuch is dabase Iteni Narrher 2064 Action W Afecting e( 3 9 93 Action N ~ Westmghouse has aded that element three he reveemed at the carrylete element level NRC to reviss the creeria for element 3 (15 open items; I B 4. ) and re-propow a iku ed set ofi ucs hawd on our discussion Refer to new meeting open item utiich is dabase hem Ni Act2064 L Action W Donwnent Isent in the NRC on 3'IS 95)that refocuses the element 3 open items was received on $/22 Westmghouse wdl prende a draft response to this dawnent Drall WCAP 14644 subnutted hv NSD-NRC 96-4722 on 314 96 Chapter I R of the SS AR to be redsed to reference this damment Rensed Chapter It of the AP600 SSAR submined in Resiuon 9. 711<96. WCAP t 4644 is referenced si SSAR It 4. Functional Requirements Analnis and Allocation Formal WCAP transnunal will he made following receipt of NRC comments Element 3 Comments Reciesed froen NRC on R 11 To close this itent SS AR Chi s was submrrted and we owe a rev to WC AP l 4644 L 0'"" NSU-NRC-96-4818 dated 9 Woher 1996 f Ct*'#d

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Page: 23 Total Records: 134 1

+ AP600 Open Item Tracking System Database: Prcject Man:gement Report Datn 11/21/96 Selecties: (NRC Branchj hke NRRM DD'B' Sorted by NRC Branch Description Item DSER Sectson/ NRC Memo (W) NRC Na Brandi Queauon Type Status Detail Imt Mod Date Staans Stamas Imar Na / Dee 1329 NRR/IIHFB l84324 D5ERol Itk14N C1cand Aanser4r" NSD NRC 96 4831 D Wessinghouse shnuld provide a m....:.. ..: for updsesng the fusutsonal analysis as part of the flautson analysis mnhedr4agy Per conference ca!I wah NRC () flongarra, G Galletti, J 01tara, J Ifiggms) of 2/23 95: Action W - Send a draft of the associated &xumers and'or redsinn to the apphcable SSAR sections Yg, f h gdN !Llecting of 3995 Ac1 ion N - Wesemphouse has asked that element three he resieued at the conglete element level NRC to revisit the criteria for clemens 3 (15 open itms. I t 4. ) and re propose a focused set ofissues based on our discussaan Refer to new meeting open item which is dahase Item Number 2064 i kleetmg of 39 95. Action N - Westmghouse has asked that element three he resiewed at the complete element lesel NRC to revisit the criteria for elemere 3 (15 open itenu, II 4, ) and re-propose a focused set ofissues based on our discussion Refer to new meeting oprei stem which is dabase Item Number 2064 Actmn W Ihumn t (sent tw the NRC on 3/IS 95) that refonases the element 3 open items was received on 5 22. Westmshouse mil pronde a dran response to thes &c ment Dran WCAP-I4644 suhnutted In NSD-NRC-96-4722 on 5/14 96 Chapter IR of the SSAR to be remed to reference this docummt. Revised Chapter 1R of the AP600 SSAR subnutted m Reunon 9,73196 WCAP-I 4644 is referenced in SSAR Ie 4. Functional Requiremeras Analnis and Altocation Formal WCAP transmntal will he made following receipt of NRC commmts l ? ficment 3 Comments Reciesed from NRC on a 13 To close this stem. SS AR Chlt uas sulmutted and we owe a rev to WCAP.I4644 Closed. In seference to letter NSD-NRC_96-4231 dated 9 Omh 1996. - _ -

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o AP600 Open Item Tracking Systene Databue: Pnject Management Report Datn 11/21/96 Selecties: (NRC Branch] like NRR/IUIFir Sorted by NRC Branch Desaiggion Itens DSER Section/ NRC Memo (W) NRC No. Bramh Qaentsen Type Status Detail Iant Mod Date Stasus 5tsema tassar No. I Dane 1330 NRR/HHFB 184.32-7 D$ERot 1414 % Closed M NSD-NRC-9M83I ACT kl gj W"-Ca should provide informatmn regardmg the function requirements vmfication Westi hnume should vanfy West all of the g-m for achieving safe operarmn are identifeed and all of the ;+.....:. of each process are identified y Meetingof 3'995. I / g h Action N Westmghouse has asked that element thee he reviewed at the complete element level NRC to tevisit the critain for element 3 (15 open items. p I 83 ) and retropase,a focuwd set ofissues based on our discussion Refer to new meetmg open item which is Ah It m Number 2064. Ir Action W Meeting of 3 995 Action N - Westmgbome has asked that element sluce he redewed at the complete element levet NRC to revisit the criteria for eternent 3 (15 open stenu. Ie 4..) and re-propose a focused set ofissues based on our discussma Refer to new meeting open stem which is dahase Item Number 2064 Action W Donemens (sene hv the NRC.m 515 95) that refocuses the element 3 open items was received on 5 '22 West +.s will provide a drmR response to this hwnens Draft WCAP-I4644 suhmined hs NSD NRC-96-4722 on 3rl496 Chapter Ie of the SSAR to he revised to reference this docuenent Revised Chapter 12 of the AP600 SSAR submined in Revision 9,7/31196 WCAP I4644 is referenced in SSAR I8 4. Functional Requirements Analpas and Allocatmn Formal WCAP transminal will he made followmg receipt of NRC comments Ele nent 3 Comenents Recieved from NRC on 8/13 To cloie this item SSAR Chi 8 was submined and we owe a rev to WCAP 14644 Closed In reference to letter NSD-NRC-964231 dated 9 Odober 1996 i Page: 25 Total Records: 134

v AP600 Open Item Tracking System Database: Project Man:gement Report Date: 11/21/96 Selecties: [NRC Branch l like NRRMHIFB~ Sorted by NRC Branch Desaignion Item DSER Sectionf NRC Memo NRC No. Branch Questson Type Status Detail Last Mod Dee Staean Steaua ,teenr No. I Date f NSD-NRC-94831 1331 NRR/lHIFB 1843.3-1 D5ERot 10/1496 Cleand Ramelved y Westinghmsse should provide informasson regardmg the basis for initial function allocationa.W J abould emocribe ene b=mia foe time mitial 7 allocations, as well as the pmceu that will ad&ess the level of automation (e g, fully autornatic, Es!!y manual, or. with manual bedup) Tw each unchanged function wth unchanged allocatioet Per conference call with NRC (J Dongarra, G Galletti, J UHara, J liiggms) o(2/2395: Action W - Send a draft of the associated document and or revision to the applicable SSAR sections. Place on 3.1 agends to discuss further with NRC. Meetmg of 3 995-Actmn N - Westmghamse has asked that element three he reviewed at the complete element level NRC to revisit the aiteria fiw elev. ere 3 (I 5 open items, .I_I f ;).*"d'?t'opme a pxused set ofissues based on out disussio_nRefer to new meetjng open item which is dahane item Number 2064 l Meetmg of 3 9 95 Action N - Westinghouse has asked that element three be reviewed at the complete element level NRC to revisit the criteria for element 3 (t 5 open stems, it 4 ) and re-propme a focused set ofissues based on our discussion Refer to new meetmg open item which in h Itan Nurnber 2064 Action W: Document (sent by the NRC on 5'15 95)that refocuses the elemere 3 open items was received on 5/22. Westinghouse will provide a draA response to this &xument i Draft WCAP 14644 submitted hv NSD-NRC-96-4722 on 3/I4 96 Chapter It of the SSAR to be revised to reference this docunrrut Revised Chapta It of the AP600 SSAR submstied in Revision 9,71196 WCAP-I4644 is referenced in SSAR It.4, Functional Requirements Analp l and Allocatmn Formal WCAP trammsttal mdi he made following receipt of NRC commmts Element 3 Commmes Reciesed from NRC on R 11 To close this stem, SS AR Chi 8 was sulmutted and we cwe a rev to WCAP-14644 .l Closed l _ ___ ___ - ; _ In reference to letter NSD-NRC 96-4831 dated 9 Octoba 1996 I { Page: 26 Total Records-134

4 AP600 Open item Tracking System D;t hase: Prrject Management Report Det:: 11/21/96 Selection [NRC Branchj hke NRR/lDD'B Sorted by NRC Branch Descryion tiern DSER Section/ NRC Memo (W) NRC No. Ikund Quemann Type Status Detail Imt Mod Date Status Stadun tener No. / Duse 1332 NRR/IIIIFB 13.4.3.3-2 DSERot torim Closed Resolved 'NSD NRC 96-4338 M Wewanghnuse should desmhe how the program will develop the rationale and level of autornetson for each unchanged fundson or process with enodsfied allocation Per confereme call with NRC (J Ibngarra, G Galleni. J O'llara, J Iliggins) of 2/2345 L Action W - Send a draft of the associated dinument and'or revision to the applicable SSAR acctions Place on 31 agenda no escuss further with NRC. l Meeting of 3 995: Action N - Weeinghouse has aded that element three he reviewed at the enmplete element level NRC to revisit the critma for element 3 (15 cwn items; I8 4..) and re-propose a focused set ofissues based on our descussion. Refer to new meeting open stem which is dabne item Number 2004 Meetmg of 3 9 95 Action N - Westinghouse has aded that element three he reviewed at the complete element level. NRC to revisit the criteria for elemere 3 (15 open items, it 4. ) and te propose a imused set of assues based on our discussion Refer to new meetmg open item whide is dahase item Number 2064 Action W: Ikwument (sent hv the NRC on 515 95) that refoonses the elemens 3 open items was received ori 5/22. Wessingbouse will preside a draft re5mnse to thn document (kaft WCAP-14644 submitted hv NSf1NRC-96-4722 on 5'l4 96 Chapter I8 of the SS AR to be revised to reference this &wument. Revised Chagect iR of the AP600 SSAR submrtted in Resision 9. 7/3196 WCAP-14644 is referenced in SSAR I8 4. Functional Requirements and Allocation Formal WCAP transmittal will he made following receipt of NRC comments Element 3 i Comments Reciesed from NRC on Scl 4 To close this item. SSAR Chl t was submined and we owe a rev to WCAP-14644 Closed - In reference,to letter NSD NRC-96-4R31 dated 9 October 1996 ..._= -_ -. .__. _ - _. = I Page: 27 Total Records 134

AP600 Open item Tracking Systern Database: Prsject Management Report Date: 11/21/96 Selecties: [NRC Branch] hke NRR/1D ETr Sorted by NRC Branch a Description Itan DSER W NRC Memo (%) NRC No. Branch Questson Type Status Detail Imt Mod Date Status Stahu tenner No. / Dese 1333 NRR/HilFB I8433-3 DSERol lei m Clomal Resolved [NSD-NRC-96 4831 (Westinghnuw should pmvide mformation regarding the function allocasson for nunfied pran==s W should demaihe the process tima ws!I addren the rationale, allocation, and level of automation for enodieed plant processes Per conference ca!I with NRC (1 Bangarra, G Galletti, J O'llara, J liiggins) of 2r23,95-Action W - Send a draA of the associated document andW revision to the applicalle SS AR sections Place on 31 agenda to dimuss fisther with NRC. Meetmgof 3 995: Action N - Wesmghouw has asked that element ttree he reviewed at the cunplete element level NRC to revisit the criteria for element 3 (15 gen items, I t 4. ) and re-propose a focuwd set _of issues based on our discussion Refer to new meetmg open item which is dahase item Number 2064 Meetmg of.19 95 Action N - Wenmghouw has asked that element three he reviewed at the corrplete element level NRC to revisit the criteria for element 3 (I S open stems, Ia 4 ) and re propow a fkused set of essues based on our discussion Refer to new meeting open item which is dahase item Number 2064 Action W: Document (sent hv the NRC on 5/1595) that refocuses the element 3 open stems was received on 5/22. Westmghouse will provide a draft reworse to this document Draft WCAP-14644 submined in NSD-NRC-96-4722 on 5/I4 96 Chagver i8 of the SSAR to be redsed to reference this document.. Rensed Chapter ie of the AP600 SS AR submined in Redsiasi 9,7/31.96 WCAP 14644 is referenced in SSAR I8 4. Functional Requirements Analvsis and Allocation Formal WCAP transmittal will be made followmg rece pt of NRC commmes Element 3. Comments Recieved from NRC on 811 To close this stem SSAR Chie mas subnuned and we owe a rev to WCAP-14644 Closed _.... ___ _ _-In reference to Ictter NSD-NRC 96-4R31 dated 9 (k1<dwr 1996, _ _ _ _ _ Page: 28 Total Records: 134

AP600 Open Item Tracking System Database: Przject Management Report Date: 11/21/96 Selection: [NRC Branchl like WRR/IDIFB' Sorted by NRC Branch e Descngnion item DSER Sedm/ NRC Memo (W) NRC No Ihanch Question Type Status Detail last Mod Date Staeus Simass base No / Dane 1314 NRR!HHfil II 4 3.3-4 D$ERot toclaw Closed Ranolved ASD NRC 96-4831 y Westinghouse should swovide the furxtum allocatmn resuks. Westinghouse should desmhe the analyare that wdl cumnmehet the yeennemel can property perform tasks aHocated to them while mamtaming operator situation awareness, wortload, and vigilance. Mecing of 39 95: Actum N - Westinghnuw has asked that element three he reviewed at the complete element level NRC to revisit the critma for elemmt 3 (15 open items, i I8 4_J and reporose a focused set of essues based on our disansion Refer to new meetmg open riem which is debase item Number 2064 Action W Meeting of 39 95- .k1 ion N Westmghouw has asked that element three he renewed at the complete elemmt level NRC to rensit the mteria for elemere 3 (13 open items. It 4 ) and retropose a fuuwd set of usues based on our discussmn Refer to new meetssg open stem which is dabase item Number 2064 Actum W' lbsmere (sens hs the NRC.4a ? 15 99 that ter.ases the element 3 open stems was received on $ r22 Westingh.x will provide a dran response to this dxument Drall WCAP.I4644 suhrruned hs NSD NRC 96-4722 on S/14 96 Chapter i 8 of the SSAR to be revened to reference this docurners Resised Cha er IE of the AP600 SS AR suhrmned in Revision 9. 7e 3I $6 WCAP-I4644 is referenced in SSAR I8 4. Functumat Requirements Analvsis and Allocatmn Formal WCAP trammenal udt he made followmg ecceipt of NRC comments Element 3 Comments Recieved from NRC on R l1 To close this item. SSAR Chi 8 was submitted and we owe a rev to WCAP 14644 6 Closed _In reference to letter NSD _NRC 96-48li dated 9 (k1ober 1996 i _.. ~ _... _ -. _ _ _.... i Page: 29 Total Records: 13d i

6 AP600 Open item Tracking System Datatcse: Pnject Management Report Date: 11/21/96 Selectlee [NRC Branch] Itke WRR/lHIFD' Sorted by NRC Branch Desairtim hem DSER W NRC Memo (W) NRC No. Branch Queenan Tye Status Detail last klad Date Staeus Sedus Lasser No. / Dune I335 NRR/HHFB Ie 4 3.3-5 DSERot to H96 Cloend Resolved NSD-NRC 96-423I l g Wemmghouse should provide inf<wmation regardag the une of the OER for enod6ed proorns functsan altaanw=L W ^ f - damid describe the une of the OER in the identification and evahsation of function allocations for those modded procemmes that have beam h4sd as s -. bened en operating experience and how past problems will he addressed Meeting of 3995 Action N - Westinghouse Ass nacd that element three he reviewed at the compicie element level. NRC to revisit the criteria for clanent 3 (15 open items. I e 4. ) ard refcopow a focuwd set of issues based on our esassseon_ Refer to new meetmg open item which is dahnse hem Numher 2064 Meetmg of 4 9 95: Action N Wesmghouse has aded that element three he resiewed at the complete element level NRC to resisat the critens for elemere 3 (IS opni stems. IR 4 ) and re-propmc a fkuwd act of swucs based on our discuuson Refn to new mening open arm wiuch is dahase Item h..mher 2064 Action W: Document (sent bs the N R C m 515 95) that refinsws the element 3 open items was received on 5/22. Westmghouse will gvovide a enA response toilus ensment DraA WCAP 14644 submined by NSD-NRC-96-4722 on 5'l496 Chapter Ie of the SSAR to be revised to reference ilus docuenens Reviwd Charts !E of the AP600 SSAR submitted in Revnion 9. 71196 WCAP-l4444 is re(crenced in SSAR Ie 4. Fundsonal Requiremeses Analpis and Allocation. The OER is referenced in SSAR I2 3 Formal WCAP trammittal wtII he made fotlowing receipt of NRC comments Element 3 Comments Reciesed from NRC on t'l 1 To close this itens SS AR Chi 2 was submitted and we owe a rev to WCAP-14644 Closed -In reference to letter NSD-NRC-96-4231 dated 9 October '996 -=--=.=::- - i Page: 30 Total Records-l34 l i i

AP600 Open item Tracking System Database: Prsject Management Report Date: 11/21/96 Selecties: [NRC Branch] like NRRADIFIr Sorted by NRC Branch Dramptian item DSER Sectiant NRC Mema (%) NRC Na Branch Questeen Type Status Dnail Im Mod Date stamme stasma tmar No. / Dese 1336 NRR/HiiFB 1843.34 D5Dtot talm Clamed Resolved # NSD NRC-96-4338 g Westmghouse uhnuld prodde information regardmg the use of the OER for uruhanged pmomms Amaction asocussant Waarungnouse dandd esembe bow unchanged functenns with unchanged fundinn allocations that have been idmtified as,,_ * * - beamd on opermanag cuperasance will be metransmat Meetmg of 3990 Adion N - Westinghnuse has asa rd that element tlwee he reviewed at the cosglete element level NRC to revisit the entma for elemese 3 (15 open herns; iE 4..) and repopose a fnossed set of assues based on nur discussion Refer to new meetag open hem which is h Item Numhee 2064. Meetmgof 3 993 Action N - Westmghnuse has asked that element t}rce he redewed at the complete elemne level NRC to revisit the cracria for claneva 3 (I $ open items; I t 4.I and repopose a focused set of euucs based on our discussion Refer to new meetag open stem which is dahase item Nusaher 2064 Action W: Document (sent bs the N RC on 513 95)that refocuses the element 1 open stems was ecceived on 5'22. Westeghouse wsil provide a draft response to this drument i i Drall WCAP 14644 subnut:ed hv NSDM 'WM-4722 on

• 14 96 Chapter It of the SSAR to. c revi=ed to reference this asumeve.

t Revised Chapter IE of the AP600 SS AR sutensned in Redsion 9,7/3l>96 WCAP-l4644 is referenced in SSAR l8 4, Functional Requirements Anals.is f and Allocation l'ormal WCAP trammatal uill he made fotlowing receipt of NRC comments Elemere 3 Comments Recieved from NRC cn 811 To close this item SSAR Chi 8 was submated and we owe a rev to WCAP-14644 b la Closed. _In reference to letter NSD-NRC 96-4811 dated 9 (ktober 1996 [

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___a I i i l f L i f Pase: 31 Total Records: 134

AP600 Open Item Tracking System Database: Pmject Management Report Date: 11/21/96 Selecties: [NRC Branch] like NRR/lDIFir Sorted by NRC Branch a Desmptim item DSER W NRC Memo (W) NRC No. Branch Questsen Type Status Detail Ime Mod Date Status Stamm tener No. I Date 1337 NRR!HHFB I343.37 DSFR4)l 10ilW Closed Resolved NSD-NRC-9W31 p} Westinghouse shnuld gwovide information regereng the effect ofnew control functson allocatsanat W^j dsessid dancnbe lesw Amctson mIW-will be reviewed to es atuate the effect of new control functee allocatiom on unchanged control ibnc. ion allocabans Meeting e f 3 993. Action N Westinghnuw has ask ed that element three he reviewed at the complete elemets level. NRC to revisit the cntecia for elenunt 3 (l $ epen items. I B 4..) and retropose a (mused set ofissues based on our discussion; Refer to new resertirq open item which is dahane Item Numhec 2064 ~ _.__ Afecting of 3 995 Action N - Westinghause has ad ed that element three be reviewed at the complete element level NRC to revisit the criteria for elemein 3 (15 open nems. 18 4. ) and re-propow a facuwd set of euucs based on cut dricussion Refer to new meeting open item whidi is dahase Itern Number 2064 Action W Document (wne hs the NRC on 5 I 3 95)that refact.ses the element 3 open nems was receiwd on $/22 Westmghouw will provide a draft response to this dwument Dran WCAP.146 8 submined in NSD-NRC-96-4722 on 514 96 Chapter IR of the SSAR to be revised to reference this daunwve Revised Charta 12 of the Al%00 SSAR suhmined in Revision 9.7131/96 WCAP.I4644 is referenced in SSAR IB 4. Functional Requirements Anahss and Allocation Formal WCAP transminal will he made following receipt of NRC comments Element 3. Comments Recieved from NRC on 8't). To(Iow this stem. SS AR Chi 8 was sulwnstted and we owe a rev to WCAP.I4644 Closed. In refer -9 =. =.,ence to lene._r NSD-NRC7.6 4R3 8 dated 9 R1obe.r.1996.

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__7 = Page: 32 Total Records 134

t ? i AP600 Open Item Tracking System Datchase: PrEject Management Report Date: 11/21/96 Selecties: [NRC Branch] like NRR/lD DTr Sotted by NRC Branch f ( Wi"8 Iteni DSER Sectionf NRC Memo (W) NRC No. Brasich Questam Type Status Detail las Mod Date Stasus Stanas Immar No. I Dame 1333 NRR/HHFB 18.5.3 1 DSI:r41 telm Clemed Adian N NSD-NRC-94831 4[ Westespuvuse should provide information regarding the scope of tank analysis. Westindiouse sh. 'd identify die aramenald foe denaams amcal er le@ua taas, how the PRA will he tred to identify the tads, and the PRA levels to be included (e g,levto I and 2) Conference catt with NRC 3 21/95 (J flangarra, G Calletti T Kenym J 01tara, J ll;ggins ASterdis, J Faster. E R A S Kerch): Westinghouse erlained that there are no cnticat higimsk taas that have been ideveified in the AP600 PRA A smaitivity study was done where al! operator actions in the PR A cutsets were set to I (ie, operator actions fail or no operator actions occur) The reauks still prodaced acceptable core damage frequencies (Ref RAlQ720 til) Actson W: Applicable settinn(s) of chagwer of the SSAR will be revised to state this We will define threshold aiteria for " Rid Important Tads". Thss criteria will he consistent u sth the D R AP niteria The_informatinn ade es6cg this open item will b_e included in the AP600 flRA-flFE,In_tcgration tv ylementatae Plan. ~ i l Conference call with NRC 3 21/95 (J Hongarra, G Galletti, f Kemon J Ollara, J liiggins, ASterdis, J Easeer E Roth, S Kerdi)- The NRC aded us what we meant by "deletmg all manual actions". We e9 amed that we encant that there were no operator actiores (ie, that a!! eperator [ t adonns in the PR A cutsets were set to 11 The mformation addresamg tfus open stem will he encluded in the AP600 IIRA-IIFE Integration Inglemeinstion Plan 4'1995 - Fax of dran respanae to IR 7 3 2 and IR 5 31 %as sent to J Ilongarra, G Galletti, J (Fliera, A J llinguna If acceptable,this response will be encorporated into the IIR A-llFE Integyation implementation Plan Action W: NRC resiewed response and presided recenck sin fax of 8'22/95. Westinghouse needs to addresa uforther tad analpis will be performed on representative mamtenance. test, inspection and surveillance tads (NRC response sent 9/5/95) New draR of the Ted Analpis plan is in red team re6cw (4896) Resised Chapter it of the AP600 SSAR submitted in Revi6nn 9,7/31/96 This includes SSAR 18 5 Task Analpis, and SSAR 18 I t,ilumen Fadars Venfication and Vahdation f hem uill be closed when WCAP-1465 I is resised to reflect NRC c, .4 Element 4 Item will be closed when WCAP l 4651 is revised to reflect NRC commeras Closed. In reference to letter NSD-NRC 96-48)I dated 9 October 1996. 1 l Page: 33 Total Records: 13d

AP600 Open Item Tracking System Database: Prrject Management Report Date: 11/21196 Selectica: [NRC Branch) like WRR/lDIFIT Sorted by NRC Ihunch Desmgnion Item DSER W NRC Memo (W) NRC No, Bra d ^* Type Simtus Detail tw Mod Date Status Status tener No / Date 1339 NRR/HilfB 18.53-2 D$ERol 161436 Closed Action N/ NSD-NRC 94831 f4 Westinghouse should g= ovide informata= regarding the critical task evaluanxus Westeghouse should ideenfy all aiticellemnan actumn as hwas thew response to Q720133, and descnhe how task analysis will he used in the evaluation of the critical taas hi operuhonal aespaances Conference call with NRC 3/2113 (J Ikmgarn, O Galletti. T Kenyon, J Crliara, J liiggms. ASterdis, J Faster. E Roth. S Kerch) Action W; Weemghouse eglained that there are no meicat highesk tasks that have heniiderdified bithe AP600 PRA A sensitivity study was done where all operator adions in the PR A cutwts were set to I (se, operator acti<ms fail or no operator adions occur). The results shll produced acceptable cwe damage frequencies (Ref RAlQ720133) Applicable section(s) of chapter of the SSAR wdl he revised to state this We will derme threshold cntma fa ~ Rid important Tasks. Thn entena will he consistent with the D-R AP cntma the Risk Irryortant Tasks and our plan to deal with them will be identified in the AP600 llRA-lif E Integration lnytementatson Plan .The information addressing thn open stem wdl he included in the AP600 IIR A.lif E Integration Inylemeatation Plant Action W Conference call with NRC 3 21/9L (I Ibngarra, G Galleni. T Kenyon, J 011 ara, J liiggma, ASterdis, J Easter. E Rceh, S Kmb) Actuut W: Westinghouw explamed that there are no mhcal highesk tasks that have been identified in the AP600 PRA A anoitivity study was done where all operator adeons m the PR A cutsets were set to I (se me:or actions fail or no operstor actions ocnar) The resulta still prdvat acceptable core damage frequencies (Ref RAlQ720 l33) Applicable wct on(s) of chage -,7 A-SSAR will he revised to state this We will define threshold cntma for "Resk Important Tasks. This mima witt tw consisters w % the D-%AP mteria The Risl6 trrportant Tasks and our plan to deal with thern wdl he ideveified in the AP600 IIR A-IIF E Inteeration impicmentation Plan Westinghouse unt (via a fas) e draA of the llR A1tfE Integyation luglementation Plan and a draA of the Tad Analpis Desenption to the NRC HlifH on 5/2495. The NRC resiewed the informati<m and gwovided feedback via fas of 8/22 95 Westmghouse needs to resolve the issue of cntical human adions and nsk important tasks (NRC response sent 9 595) Reuwd Chapter ie of the AP600 SSAR submined in Revision 9,7s3196 This em hades SSAR I2 5. Task Analysis, and SSAR IE II,iluman factors Vmfecation and Validation Item will be closed when WCAP.I 465 I is reviwd to refied NRC commmes Flemmt 4 Item will he cimed when WCAP.I 4651 n reuwd to reflect NRC comrnents [ Closed _la reference to letter NSD-N RC _96-4R11 dated 9 0ctober 1996 =._ Page: 34 Total Records 134 i

o. AP600 Open item Tracking System Database: Pr2 ject Management Report Dat:: 11/21/96 Selecties: [NRC Branch] Itke NRRM DIFTY Sorted by NRC Branch a Desmrtum Itens DSER Sectumf NRC Memo (W) NRC No. Iksrech Osentum Type Status Detad Ims Afod Date Staeus Sessus immer No. I Dare 1340 NRR/HHFB 18.533 D$EROI am.% Resolved .Randrust-g{y )Y Wesamshnuse should provide an6wmatum regardmg the task analysis methods Westmghouse should W inw tame facears, werkload, tank myport requirements wortplan factors, stasmg. and communication will he aekessed in the taa analysis. W - f should also deambeinw the onpiitive J or p task analpes and "traditimial* methods will be inteErsted to analy7e crew tasks what detsien maaria will be tamed tojudge whethee taas need the N J \\0g tg cogmeive ta.sk anaines, and the total set of task analpis data that will resuh from the cuyletion of att task analpas snethods j 06 G V d I Conference call with NRC 3/21/95: p g plp., J (J Ibngarra. G Galletti, T Kenyces. J 01Isra. J liiggms. ASterdes. J Easter. E Roth. S Kmh) Action W: Westinghouse's response to include the descnption of Operational Sequeue Analpes (OSAs). De OSAs will focus on time available versus time estimates We udt relv en the IIFE VAV fro realistic estimate of workload We will evaluate Iww best to incorpurate this information. ie revise appikaMe intums of chartcr I t,of the SSAR,w mte a damn,e,nt,tha_t is, refevewed in the SSAR. 1 Conference call with NRC 3 '2145 (J ibngarra. G Galicite. T Kemon. J ollara. J iriggins, Asterdia. J Easser. E Roth. S Kerch) Actmn W. Westeghouse's respame to mchwie the d -wryteon of Operatennat Sequence Analpes (OS As) and woriload analwis De OS s, mitt focus en time available versus time estunales We mall esatuate how best to encorpor ate tlus information. se., resise appikable sectiores of chageer 18 of the SSAR or unte a document that is referenced in the SS AR i Westinghouse sens (via a fau) e draA of a Task Analysis Desmpten document to the NRC lilIFB on 5/24,95. De NRC reviewed the Anment and prowled feedhad via fas of a 22 95. corniders = sue resolmf Fmal closure will require a revision to SSAR section 18 8.2 I and and ITAAC. (NRC response sait 9 595) Revised Chapter I t of the Al%00 SSAR submitted in Revision 9. 7/3196 hisincludes SSAR I* 5. Tank Analysis --=_r - - = - _.. - =__ k I Page: 35 Tolal Records: 134 i

a, AP600 Open Item Tracking Systera Database: Prrject Management Report Date: 11/21/96 i l Selection: [NRC Branch] like NRRe1DFIT Sorted by NRC Branch e Desayeien tiern DSER Section/ NRC Mano (W) NRC No. Brana Queueson Type Status Detail las Mod Date Staeus Status tamerNo./ Dese 134l NRR/lillFB 18.5.3-4 DSERoi s'n 96 Ramolved -Sammind Ac7 yd M Westinghouse should prowde information regarding the task analpis job dreigrt W- -f - should iA=*dy alw relevara job deaipi factors (ens as the number of crew member Alls), and indicate how they will be addressed in the task analysis g Conference call with NRC 3/2195. [f1)[ (J Dongarra. G Galletti, T Kenyort J 011 ara J liiggins, Aster &s, J Faster. E Roth, S Knch) e Action W: Westinghouse will write a COI. Action Item (Information tiern) that states that the ident:6;ation of

• job design factori*, such as crew member skills, es a COL applicant responsitalery This information is used to develop an operstor training progrant Weninghouse will clearly state the assumptions used in thegational Segsence Analyses.

_. _. - - _ ~ Conference call with NRC 3 2195 (J liongarra, G Galletti. T Kenyon, J 011 ara. J liiggum, ASacrdis, J Easter, E Roth, S Kerch) Action W: Westmghouse well unte a Col, Adian Itern (Information item) that states that the identification of" job desipi factors", such as crew member skslls, is a COI. apphcant responsitulies This information is used to dn elop an opnator training program Wen.,,R will clearly stah *he assumptiors used m the Operatsonal Sequence Analnes Westinghouse sens (via a fax) e dran of a 1 ask Analpis Descriptuwi exument to the NRC fillFD on 5/24.95. The NRC reviewed the document and provided fee &ack via fax of 8 2295.comsders issue resolved Final closure will requwe a revision to SSAR section It 8 2.1 and an ITAAC. (NRC respome sene 9,5.95) Resised Chapter Ie of the AP600 SSAR subnutted in Revision 9. 7 3196 This includes SS AR It.5. Task Analysis. 1142 NRR'llilFil it535 DsFR ot a t* Resolsed .Susabed Ac.r W g Westmghouse should provide enformation regard ng the task analpis methodology source masenais. W " j should identify sourst &msmeras to serve as the basis for detamining the types of mformation previously identified in Cninion 3 (Refer to open item 18 5.3 3) g Conference call with NRC 3/2195 p q0 (J llongarra. G Galletti T Kenyon. J 01tua. I liiggins. ASacrdis, J Easter, E Roth, S Kerch) }l Action W: A clear statement of the dumwnts that were considered is needed in chapter i t of the SSAR. I Conference call with NRC 3/21195 (J llongarra G Galletti. T Kentert J O'llara. J liiggms, AStenhs, J Easter, E Roth, S Kerch) Action W: A clear statemens of the docurnents that were considered as needed m chapter it of the SSAR. Rev. 4 to SSAR. Weninghouse sene (via a fax) a dran of a Task Analpis Desaircion Axument to the NRC III!FB on 5/2495. The NRC reviewed the d=umere and provided feedback sin fax of 8 22/95. Imal closure will require a revision to SSAR section 18 8.2 I and an appropriate ITAAC. (NRC response sens 9/595) Revised Chapter I$ of the AP600 SSAR subnutted in Revision 9,7/31% lhis includes SSAR Ia 5, Task Analpaa Page: 36 Total Records-134

AP600 Open Item Tracking System Database: Prcject Management Report Data: 11/21/96 Selection [NRC Branch] like NRR/IDIFTr Sorted by NRC Branch a Descrignet item DSER Section/ NRC Memo (%) NRC No Branch Questnus Type Stasua Detail IAct Mod Date Staeus Stamas Lauer No. I Dese 1343 NRR/IIHFB 1863-1 D5EJL ol 3396 Cleasd M A,- r-M Westinghnenne should provide information regarding the number and quale 6 cations ofpsentousel W ^ j should prende M-t Mosmeson on how the llFE desipi and impicmentation process wdl address the nurnher and ph6catiosa of personnel required enring the nell range of plant con &tions and tads, includmg operational tads, plant enaintenance, and plare surveillance and newsng Conference call with NRC 3/21195: (J Ibngarra G Galletti. T Kenyon. J O'llara. J liiggins, A Sterdis. J Fasser, E Roth. S Kersh) Action W: Westeghouse to revise the applicable chapter i E SSAR sections to reflect the statemeres and process described in the cleaure padt Stase that staffmg levels outside of the operations staff, such as maintenance, is the responsiht.ty of the COL applicase (COL Informatson lean needed) The same appranch will be appl.ed to all the stafTang open dems Westinghouse is to clearly identify to the NRC where in the draft revision each apan item is addiessed This will be &me hv utilising this database, ic, in the database for each open item provide the map of the open item to the parragraph(s)in the dr_an reps.on whn,e,the open,itan i,s adorened,,- __ __ Act.an w Conferencecall with NRC 3 28 95' (I ILngarra, G Gattetti. T Kenyon, J O'llara. J ll ggina, Asieres, J Easter. E Roth. S L n) Action W-West.nghouse to revise the appl cahic thapta 12 SSAR sen.ons (Reviseon 4 to SS AR) to reflect the sensameses and procean demmhed in the closure pedi State that staffmg lesels outside of the operations staff, such as mamienance, as the responssMlay of the COL applicant (COL Informasson item needed) The same approa h will be applied to all the staffmg open nems Westinghouse is to clearly idersify to the NRC where in the draA resishm cash open stem es addressed Action W. A &an revision to SS AR settim i R 7 (Staffmg) needs to he sent to NRC, a&hessing all element 5 open items The NRC actim will then be to amew and prmide feedhmit 4896 A &an of I 2 7 has Gnnhed red team renew comrnents base been encorporsted or resolved The drnA is now in word processing Resolved Per a descusshe wnh the NRC on 5 22. staffmg will he addressed as a COI. responsibilet.. Closure will depend upon the revised subnnual of Chapter I t. Revened Chagwer IE 6 of the AP600 SSAR submitted in Resision 9,7/3 8'96 This includes ccmhined license applicant responsibilny for stasang item wsli he closed when suggwwting WCAP on staffrng is trammetted Licment 5 Weth SS AR C n 1 E submittal and WCAP 14694 this is closed Page: 37 Total Records: 134 W

=. _ _ e AP600 Open item Tracking System D; tab se: Prrject Management Report Date: 11/21/96 Selectles: [NRC Branchj like NRR/lIHFB' Sorted by NRC Branch Dracngeion term DSER Sectso'V NRC Memo y) NRC No. Ikunch h-i Twe Status Detait last Mod Date Staeus Seasus tener No. I Dune 1344 NRR/HHFB 186.32 DsFaol ar2L96 Closed -AmssenrW Arr 0 g Westinghouse should provute information regardmg the staNing level analysis Westinglunsar shmend disuses hme the s mfFmig demien somsts the a regsiremmes of 10 CFR 50 54(m). and desenhe the analyses cendected to detemune whether these.,. - were approprinne for the AP600. ^ W,W

should also descnhe the process that will be insed to validate staffing rapsirenumas agaiist the task analysms and assinst die physical demispi of the AP600 operations and control centers, as well as how the avadabilay of plant information from individual operator workstassons will be used in the analysis of staffing levels Westinghouw should also escuss the availshildy of operators -

".. eeher engoing act;vetise, and liow that relates to j staffing In addition, Westmghouw should provide more informatumi on the required interadion between opermaars for &apioses, planneg,and onntrol activdees, and interaction between personnel for administrative, cornmuncations, and reporting activnica. Final!y. W-___ ; : should escuss how the actions required in 10 CFR 50 47(and NURFG4634)and staffing requisemmts in Sestions I) 1.2 and l). I 3 of NUREG4800 and 10 CFR 50 54 will be taken into account in the staffing level decisions made for the AP600 f Confaence call with NRC 3'21/95 (J Ibagarra, G Galletti, T Kemon. J O'Ilara, J liiggms, ASteres, J Easter E Roth S Kerch) Actuws W; Westmghouw to renw the applicable chapter 18 SS AR ses1 ions to reflest the statements and process drucnhed in the closure path State that i staffung levels outside of the operations stas, such as mairmenance, is the responsibilets of the COL applicare (COL Ird.. . Itern needed) The same l appreadi will be appteed to all the staffing open items Westinghouse is to clearly identify to the NRC whm in the dran revision each open nem is l addressed This will he done in ut I.iing N datahaw, se, in the database for each npen stem provide the map of the open itern *. the parragraph(s)in the drall revesson where_the open seem is addressed l i Conference call with NRC 3/2 8 95: (lIbngarra, G Galletti, T Kenyon. J 01tara, J liiggins. ASteres. J Easter. E Roth. S Kerch) Action % : l Westinghouse to reviw the applicable chapter I t SSAR sections to reflect the staten ents and process desenhed in the closure pak State that snaffing levels outside of the operations staK. such as maintenance. is the responsshditv of the COL applicant (COL Infonnmanon item needed) The same apii mill be applied to all the stafTmg open items Westmghouw is to clearly identify to the NRC uhere in the draA reviseen each open itern is addressed Act.on W_ A drall resision to SS AR sedeon I t 7 (Staffing) needs to he sent to NRC.1

all elemne 5 open items. The NRC action wdl then he to review and provide feceed 4 '896 A draft of I t 7 has finnhed red team renew, comments hase been mcorpwated or resolved. The draA is now in werd processing Resolved Per a dacuuien with the NRC on 5'22, staffmg udt he addressed as a COL resporisihday Closure will depend upon the revised suhmittal of Chapter I*

i Revised Chapter iR 6 of the AP600 SSAR submitted in Revision 9,7/31'96 Thrs includes combmed license applicant respomiheldy for staffing item mill he closed when supportmg WCAP on staffmg is transmitted Eleman 5. l Wah SSAR Ch I R submittal and WCAP-14694 this is closed t Page: 38 Total Records-13d L i

r I w AP600 Open item Tracking S. stein Database: Prsject Management Report Dat2: 11/21/96 Selecties- [NRC Branch) like NRR/lD Efr Sorted by NRC Branch Descryteon luin DSER Sectaanf NRC Memo (W) NRC No. Branch Questaan Type Staeus Deta 1 tme Mod Date Stasus Stasus tesaar No / Daae 1345 NRR/IIHnt 18 6.3-3 DsFRot t'2M6 Clamed .AmeneurW scnJ 4 #>j Westinsimune should provide inf smation regarding the staring analpis iteration Westinghouse sinnesad escribe si aume enest the iemrative assure of the staEing level aantpis Innehtmn, Westinghouse shnuto discuss how the task analysis will be mndified if a desernunsanon is made that the sta9ing level is anadequate or if meetmg the stalr.ng level requirement adds sulntarsial spenstaed automatic control of ampsipnene, agiven that it is : sos clear ihsa the task analpas is crew member 4.ased Conference call with NRC 3 2145 (J Bangarra, O Galletti. T Kenyon, J Ollara, J IInggins, ASecrdis, J Fasacr. E Roth,5 Kercti) Acuinn W. Westinghouse to redse the applicable chapter I 8 SS AR ses1 sons to reflect the staternevits and process described in tiv closure patfL j Conference caff with NRC 12195. (J Ikegarra, G Galiciti. T Kenvan, J 01tara J Ifigsms. ASterdis, J Eamer. E Roth, S Kertti) Adson W: Westeghouse to redse the applicable 6harter 18 SSAR ses1 eons to reflect the statements and procesa deemhed in the closure path Actenn W. A draft revision to SS AR sedian I 8 7 (StaEmg) needs to he sene to NRC, adeessing all element 5 open items The NRC adim wdl then he to [ review and prodde fee &ack 4 2 96' A draft of I2 7 has finnhed red team res new,commmes have been mcorporsted or resels 4 Tk draA is now in word processmg Reselsed Per a discussion unh the NRC on 5 22. staring will he addressed as a C01, regponsibility, Closure will depend upon the revised subnunal ol Chapter it. Redsed Chapter IR 6 of the AP600 SSAR submitted in Revision 9,7'lle96 This includes etwnhined licessee applicans responsebshev fiw sta6mg Itern will he closed utien supporting WCAP on stafTmg is eransmitted Element 5. i gSMgit suMnal and WCArg6 thisjs closed i I i ) i l l t i Page 39 Total Records: 134 I t

~ - AP600 Open Iten Tracking Systeni Database: Pseject Managesnent Report Date: 11/21/96 Selectica [NRC Branch) Itke NRR/IDIFTT Sorted by NRC Branch a Desmrtson Item DSER S*M NRC Meme (w) NRC N. arena n -- Tne Status Detail. Im und pate Status Stamm laear No / Date 1346 NRR/IlffFB I$&34 D5ER41 t'2196 Closed W f5G r-N g Westinghouse should provide infonnation regerang the conipliance of stafeg with the 11E PRM eleinsses W_._ J slumsid provide NW inforniatiori, particularly for those elements of Critenon 4.

• Basis for Stasmg,* of this sedian, thee an. tus speci6cally addranand for operstma personnel, and for all the elements of Cntman 4.
• Basis for Stafing," of this secitan as they relate to ann.operussons persorairl.

Conference call with NRC 3/2193: (J Bongarra, G Galletti, T Kenvon. J Ullara, J f figsms, ASterdis, J Faster, E Rath S Kerch) Ad'"" W; W""8h"5' '* '"i5'. thy _appiecage dagwer I t SSAR sedions to reflect the statements and process descnhed in the closure path Action W Conference call with NRC 12195 (l Ilongurn, G Galletti. T Kenyort J O'Itara, J lliggms. A Ster &s. J Easner, E Roth, S Kerth) Action W; Westinghouse to res use the apphcahic chapter 18 SSAR sedians to reflect the statements and pronss desmhed in the closure petit Adann W. A draft reuseon la SS 1R sedeon I 2 7 (Stating) needs to be sent to NRC, addressing all element 5 open stems The NRC adian will elim be to review and proside feedback 4 8 96 A draft of * *' 7 has finnhed red tearn review,comrnents base been erworparated nr resolsed The draft is now in word messing I Resolved Per a dis. ussion meth the NRC on 3/22 stafing udt he addressed as a COI responnebddy. Closure will depend upon ti.e redsed subrnittal of Chapter It Rnised Chapter i B 6 of the AP600 SSAR suhmdted en Resision 9,7'3I 96 Thss asludes combmed th appiscant responsebeldv for staffing Item will be closed when supporting WCAP on stalling is transmitted Element S. Wah SSAR Ch It suhmdtal and WCAP.14694 thes is closed _.a 7 _ _. _ _ -. - _ l 1 t Page: 40 Total Records: 134

AP600 Open Item Tracking System Database: Project Management Report Date: 11/21/96 Selecties [NRC Branch] lih NRR/lD U B' Sorted by NRC Branch Descrigwien item DSER Section/ NRC Memo (W) NRC No. Branch h-Type Status Detail las Mod Date Stamm Stasus bear Na / Date 1347 NRR/HHFB 18 6.3-5 D5EROI 87386 Closed Mass >W g' wesunghouse shouw povide inrannation regarang the mafreg nwthodology source mM W mafiouse Amild idmenfy the in&mry mandm&, guidelines, and practices on utich the stahg inylementatim plan is based Conference call with NRC 3/2895. (J Hongarra, G Gar!ctri. T Kenyon, J O'llara, J Higgins, ASterdis, J Eamer, E Roth, S Kerth) A tion W: Westinghouse to revise the applicable chapter 12 SSAR sections to reflect the statenwnes and process descnbed in the closure patit Based on the &scussions with the NRC on stahg and the informeteon to be provided te address each stafang open stem, this item will be covaed We need to meure that the stahg COL Adian itempfies the COL pplicant responuhidy and mates the stafteng assungssons that were made in desigri certifkstaart Conference call math NRC 3/2 8 95. (J Dongarra, G Galletti, T Kenyon, J O'llara, J liiggins, A.Sterdes, J Eamer E Roth, S Kerth) Action W. Westinghouse to reuse the apphcable chapter IS SSAR sections to reflect the statements and process described in the closure path Based on the docussions with the NRC on stahg and the mformation to be pros ided to address each stahs open item, this iteen will be cove-d. We need to ensure that the stahg 001. Ad on item identifks the COL apphcant regensib hty and states the stafing assunytions that were snade m desigri certification Action W: A draft reuuan to SS AR sedim 18 7 (Stahg) needs to be sent to NRC, addressing all elemese $ open itens The NRC action will thm he to review and proside feedhad 41% A draft of I t 7 has finished red team renew; comments have been incorporated or resolved. 'he draft is now in word processing Resolsed Per a discussion udh the NRC on 5 '22, stahg mill he addressed as a Col.responsihiirry Closure will depend upon the redsed suberuttal of Chapter it Revised Chapace 12 6 of the AP600 SSAR suhrnatted in Revision 9. 7/31 '96 This includes combined license app?icant responsabilny for staffung item will be closed when supportmg WCAP on stahg is transnutted Element 5 With SSAR Ch I e subnuttal and WCAP-I 4694 this is closed a y-

m 2 Page: 4I Total Records 134

AP600 Open Itein Tracking System Database: Przject Management Report Date: 1I/21/96 Sdection [NRC Branch] like NRR/lDIFIr Sorted by NRC Branch Description tiem DSER Sectnesi/ NRC Memo (w) NRC No. Brandi Questaan Type Status Detail Last Mod Dese sisans Sesmas 1.amar No. I Dune 134: NRMfHFB 12.7.3-1 DsER O tor:496 Closed --assm6eed-FSD-NRC-96-4831 (A CT LCl. /(p lWessingfumase ahnuld povide informatxin regneding the hunnan reliabildy analysis (HRAyHFE inspuhan, ' ' pint l 1 {lM> 'geP"#.MI Resolved f 3/31/95. Phone conversation between Westinghouse and J Nagarra' hm stated that generally speaking the resolutaca pashs for all element 6 open innes are acceptable Action W. To develop and submit a draA of the llRA-l!FE Innegation Iglementassen Plan by May 31. The appropnase ention of the [ [$ SSAR nll also be revised (Revision 4),referencmg this N'...c.ation plan (,% The draA If RAllIFE Integation Implementation Plan was sent (via fax) to the NRC llHFB ori 5/2495. All elemme 6 (HRA) open itams are addressed by this dansment The NRC revicued the drument and prodded fee &ack da fat of 97295 NRC considers this issue resolval (see NRC respnme sent 10/395) Revised SSAR I E 7. Inteystion of Iluman Reliabildy Analnis with Iturnan Factors Enginecesng sulunitted in Revision 9. 7/11 % Item will he cleard when redsed WCAP-14651 is submened Elemens 6. Redsed SSAR It 7. Integation of Bluman Rehability Analais with Iluman Factors Engmeenng submitted on Revision 9. 7/3196 Item msli be closed when revised WCAP-14651 is submitted Closed - la reference to letter NSD-NRC 96-4831 dated 9 (ktober 1996 - - = -

== - . _. := _.= = z - - - - _ - - - - - -

== l b Page: 42 Total Records: 134

4 AP600 Open Item Tracking System Database: Przject Management Report Date: 11/21/96 Selecties [NRC Branch] like NRR/IIIIFB' Sotted by NRC Branch Denmption item DSER Saten/ NRC Memo M NRC No. Branch W-Type Staeus Detail l_ast Mod Dane sessus Steens Imar No. / Dee 1349 NRR/HHFS 18.7.3 2 D5ER4)I t&l496 Closed AsessurN NSD-NRC 96-4831 MT-u) W " w should provide infonnation regereng the process used for i&seafying cynical immune meh W+ hW dammbe Itte proomms dent py will idewify meical human actions fm the level I and 1svel 2 PRA including teth intemal and external evassa, followstg the carrylation of senmitavdy analyses M Action N ~ 3/31/95 - Phone comersation between Westinghouse and J Bongarrn Jirn stated that generally speaking the resolusson pashs for all elmieva 6 opm item are accriemble Action W. To desetop and sutwnit a draA of the if RA-flFE traepetion Irrglemereation Plan try May 31. The appropriate secnon of the SSAR will also he remed (R Fv 4). referencing this implementation plan 4/1995 Fax of dran respame to I8 7 3 2 and iR.5 3-1 was sera to J Bangarra, G Galleni. J Ullara, A J liiggins if aneptable, this response ws:1 he incorporated una the llR A-life Integation implementation Plan NRC reviewed this dran and prouded feceatk via fai of 9/2895. Westinghouse and NRC still need to resolve the innse of critical human adions and risk unportant tasks The NRC tillFilto coordinate a conference call wah the NRC Rask Analpis(PR A) people and W- '-f - to encuss. (See NRC respome sent 10195) 4 '896-A resised dran of the llR A lif E Integation Inglementation Plan shouki he ready for red team review by 4/12% Resolved Dran WCAP.1465I,Intepation ofIluman Relishihty Analpis with ituman Factors Em Design Inglemernation Plan, was sulunetted to the NRC as an attachment to NSD-NRC-96 4722 on 5/1496 Appropriate reference to the documese will be made in Chapter 18 of the SSAR. Revised SSAR 18 7, Integation ofIluman Rehabihtv Analvsis with Iluman Factors Engineenng submrtled in Revision 9. 7/31/96 liern will be closed when remed WCAP-14651 is submitted Element 6 Revesed SS AR IE 7, Intepation of Iluman Rehabihty Analpis unh Blumen Factors Fngineering suhnutted on Revision 9. 7/31/96 Item will be closed l when revised WCAP-14658 is suhrnated t Closed In reference to Ictter NSD ---. _... - _ __NRC-96_4til dated 9 ( Atober 1996 .__m t i t l l t i i I Page: 43 Total Records: I3d [ i i b

e AP600 Open item Tracking System Database: Pnject Management Report Date: 11/21/96 Selection- [NRC Branch] like NRR/IDIFIr Sorted by NRC Branch Desenption Iteni DSER Sectsant NRC Mano (W) NRC g Brundi Questaan Tne Status Detail I.ma Mad Date Stama Staans Im No. I Dese 350 NRR/HHFB 18.7.3 3 DSER G 141496 Clemed NSD-NRC-964831

c. c_T' tA.)

g lWestinginouse should descnhe the process they will ue to address lhe tad analyers for cynicallaunan actions. l Resnived E 3/31/95 - Phone conversation between Westirighouse and J finngana Jun stated that generally speaking the reschnian pashs far all elanent 6 epen items f g,i f are acceptable Action W: To devely and suhnut a dran of the llR A IIFE Integration Impleninsation Plan by May 31. W apprepnase acction of the f SSAR wdl also be revised referennng this irrylementatim plan. N dran IIR AllFE Inteerstian Inglemanatian Plan was see (vis fax) to the NRC lillFB on 5/2495. All elenient 6 (IIRA) open itens are a&henned by dus d<xvment & NRC revicued the dxvment and provided fe hck via the faz o(9'28.95, NRC considers this issue resolvat r Action W (per NRC)- see NRC respome sent 10/395 Revised SS AR II 7, Integration of llaman Rehabildv Anahsis wah fluman Fadors Fnemeenna submnted in Revision 9,7/31/96. lean will be closed mtwn revised WCAP. I s65 8 is sutemtted i Element 6. Revised SSAR 13 7,lategration of llaman Reinabildy Anahsis with fluman fattors Engswenng sulmutted on Revision 9,7/31/96. Item will be closed when revised WCAP-1465 8 is submined l Closed -In reference to later NSD-NRC.96_423 8 dated 9 atoher 1996_ _. - _. _ _. _ _ _ _ . - - -. _. ~ -. - - _.. _. t l i Page: 44 Total Records: 134 i

o AP600 Open Item Tracking System Database: Prsject Management Report Date: 11/21/96 Selection [NRC Branch] like NRRA D D'B' Sorted by NRC Branch Decription lean DSER W NRC Merno (W) NRC No. Brandt h a-Type Status Detail last Mod Date Staeus 9 sses im No. / Dane 1351 NRR!HHFB 13.7.34 D5ERol I&lM6 Clamed -SaaESUS$-* NSD-NRC 964831 act-ti> jg weatsnepiouse should penvide information regardma the detailed exanunatum of aitical actio W ' f - sinamed describe the preams that will(a) provide addstional information on the innpact ofitFE function allocatiore pt to be performed on alie ifRA,(b) provide deeniled evaknations of aitical actions to reduce or etuninate sourtes of error, and (c) clanfy the possible encensisteng twtween the operssor role asuniptions in the life draiyi and the 11RA R a ed 3/31/95 - Phone conversation tutween Westmghouse and J Ihmgarra, Jwn stated that geacrally speaking the resolutaan paths for all elemmt 6 open items are acceptable Action W: To develop and suhmes a draA of the llR A-IIFE Inteystion :.Sc..= ion Plan by May 31. The apprepnase sation of the SSAR will also be revued, referencing this implerr.cntation plan The draft itRAliFE Integation Impleur.mtation Plan was sers (vis fau) to the NRC ItilFB on 5/2495. All element 6 (llRA) open items are addremed bv slus document The NRC seriewed the dxument and provided Ice &ack via the fat of 9/2895 NRC considers this inante resolved Action W (per NRC) see NRC reymw wn: 10195 Closed Revised SSAR I2 7,intepat.on of ituman Retinhality Analwis with Iluman Factors Fagpneerug sularuand in Revision 9. 7/31/96. Item mil he closed when revised WCAP-1465I es subnuned Element 6. Revised SS AR I2 7, insepation of fluman Rehabilstv Analwes usth fluman faaots F nameermg sulumned on Revision 9. 7/31196 Item mit be closed when revised WCAP 1465I is submitted Closed. In refaence to tener NSD,-NRC-96-42)I dated 9 &1oher 1996 . - -.. -. = = - = ~ = - = 2.

_ _ _ _ _ _ _ _ - - =. =

Page 45 Total Records: 134

-. =. - o AP600 Open Item Tracking System Database: Priject Msagement Report Date: 11/21/96 Sduties: [NRC Branchj like 'NRR/IDIFB Sorted by NRC Branch Desmgwim Itan DSER Sh NRC Memo (W) NRC No. Brandi Questum Type status Detail im Mod Date Stana Stadass I macNo./ Dese A4W = h" NSD-NRC-96-4531 AmilEN T 1352 NRR/HHFB 18 7.3-5 D$ER ol IM4N Cleasd ? P l, WestagPunase should provide utformation regardmg the use of PRMIRA swigins. W ^ f - ; a=4 provide examuples of how the HRATRA @

• ere used to improve desigri and tenet risk to human actions and errors and deambe the procean winervery than edFart will -- as part c(die HFE desiyL_

Actwn W 3f31/95 - Phone conversation hetween Westinghnuse and J Ihmgarra Jan stated that generally speak.ing the resolutaan pasha for all elemmed 6 open items gp$ are acceptable, however, the closure pain to thes one dws ret answer the question Jan saed that we need to provide spacine exangdes Also, he said to refer 1 to the specif.c PRM meeria, R Al Q720117 and the Es aluation section of the DSER for this open item for fus1hre guidance (Ee. ofinfluerax on the MMI l design?) Action W: To develop and suhm. a draA of the llR A-IIFE treepetion implementatumi Plan try May 31. The appropnase sedian of the SSAR will also be revised, referencing this implementatLm plan The drmA flR A IIFE Breepatum implementation Plan was sent (via fau) to the NRC lillFD on 5/24.95. All eternas 6 (IIRA) open itens are addressed by this document The NRC reviewed the ensment and prodded feedback. Westeighouse needs to address the questsons raiand in the NRC fax of 9/2895 (see NRC response sent 10/195) Resolved Dran WCAP-t 4651. Interation of fluman Retiablity Analpis with fluman Fa tors Engmemng Deseen implenwreatson PM was suhnnm to the NRC as an metactwnent to NSD-NRC 96-4722 on 5'l496 Appopriate reference to the documers will be made in Chagner 18 of the $$AR. Revised SSAR Ia 7. Intepation ofIluman ReliaNie Analpis wah Ilumen Factors Engineenne suhrrused in Revimien 9,7/3I/96. Itan wdl be closed when revised WCAP 14651 es submined Elemne 6. Revised SSAR 18 7,Interation ofIluman ReliaNhty Analpis with Iluman Factors Ingmemng suhnutted on Revision 9. 7/3I/96 Itern will he closed when reviwd WCAP-14651 is suhmened Closed la reference to ldter NSD-NRC-96-4231 dated 9 0ctober 1996 t t I 1 l I Page: 46 Total Records: 134 L i

1 AP600 Open Iteen Tracking System Database: Prsject Managesnent Report Dat:: 11/21/96 Sebcstem: [NRC Branchl Itke NRR/lO DTY Sorted by NRC Branch Itan DSER Sectaan/ NRC Memo (w) NRC No. Brandi 9-Type Status Detail bat Mod Duse Stasma h e asa c No. I Dane 1353 NRR/HilFB 187.34 D$ERol ItWM96 Cloemd .Sanabine-NSD-NRC,964g31 A C,L-N jy Westinghouse should prowde a forenation regardmg the llRA validation Wessanghouer should esembe the pmomms for N of HRA -P and possible revision of the llRA if necessary I Roolved " ~ ~~ 3/31/95 - Phone convmation between Westingbouse and J Bangarra: Jan stated that generally speaking the resolutson punha for all elesness 6 open stans are acceptable Adam W: To develop and sutet a enft of the IIRA-IIFE lisegration Inglementati e Plan try May 31. The apprnynaee season of the SSAR will also be rnised (Rewsion 4). refnencing this iniplementation plan L i The draft flR A1IFE Integration implementet.on rian uas sent (via fas) to the NRC 1811111 on 5/24 95 All elesnese 6 (llRA) open items are addressed by this dawnent The NRC reviewed the document and pavided feedha k via fas of 9 2295, NRC considers the immur resolved Action W (per NRC)- see NRC respawise sent IO 3 95 Rnised SSAR Ie 7. Integration of fluman Rehabhtv Analph with fluman Fadors I ngincenng submitted am Revision 9. 7/3I 94 Itern will he closed when rnised WCAP 1465 I is suhnuned i Elanent 6 I Revised SSAR IE 7. Integranson ofIfuman Rehahshty Analpas with Bluman Fadors Fngineering submitted on Revision 9. 7/3 8 /96 Item wit! be closed when revhed WCAP-14651 is submined Closed. In refnence to letter NSD-NRC 96-4til dated 9 Rtober 1996 [ t 1354 NRR.1111FB 188I31 DSF R ot y;5 % Closed Action W ! Westinghouse should proEUematErc~garding the ilSI desip process guidance ' Westinghouse Jiould descnhe how evaluatsan results wd1 he y communwated to designers. incorporated into design guidance, and refleded m 6nal & sip documerna ion 1he process by which implemersatim gu. dance / d g will be developed mu<t also he desenhed 9,#&[p<C V 19 ped Afectingof 3'1095 [ l Adion N NRC wdi rnicw our desip puacess as described in the SSAR R Als and in WCAP 1260I, and WCAP 98 87 and provide us feedmi The ge'g >, NRC will review the SSD procedures of WCAP I 2601 to determine af they cover issues like *providing guidance to llSI %. for adsbessmg / utilizing J y desiere inputs such as the FitTA resuhs' Nde that the procedures will be at a higher inel. not speci6cally referring to the FHTA or other speci6c IIFE g analyses er reports The staff udl also review the Alarm Sptern lksip Guedelmes and the Intmrn Report on Tectmical Pnnciples for Computer liased Displan of Data (both on,61c in R,ath ville off.cc) informal feedak from NRC was that the display encuanese does provide the ismended gu_idan kleeting of 3/10/95: NRC re7dourieTs p process as desmhed in the SS AR. RAfs and in WCAP 12601, and WCAP 9857 and provided feedm[nY a letter dated 7/2$/95 Action W: Review and address NRC feedimi issues Revised SSAR Chapter I

• suhmitted an Revision 9. 7/38 /96 1his includes SS AR I E 8, ilumen Systein Interface Design and SSAR I E 2. Ilumen Fadars fngsan=g Progrm Managanent.

t Page: 47 Total Records-134

o AP600 Open Itent Tracking Systen: Database: Prsject Management Report Date: 11/21/96 i selecties. [NRC Branch l like WRR/lDIFB' Sortal by NRC Branch Denmptaon lien DSER Sectnant NRC Mane (W) NRC No. M W -- Type Stasm Detail last Mod Date h h W No I h 1355 NRRMHFB I8 8 B.3-2 DSF M I M6% Cloaad Adian W/ d waninsbaume should provide inrannat.on retareng se ta=kclared HSI requirenuses. W ' f - M dumbe se ymcom by 6 pumWe

in maross and di.plar are eliminated form se rmal desian m me== by whidi faen ofcoveroh and displays are amnially dermed as-t aam lie drunbed.

I hg,6 Medmg of 3/1045 k Same as the

• Action N* note in the open item demnption field for ease itens number i 351 Meetingof 3/1095: NRC renewed our desop pacess as desenhed in the SSAR, R Als and in WCAP 12601, and WCAP 9817 and podded feediack da a letter dated 7/2545..

Action W: Redew and address NRC feedhui assues Revised SSAR napter la sulwmned in Remson 9. 7,3196 This includes SS AR I 2 8. Slumen Systan Irmarfaa Desip and SSAR 18 2. Iluman Fadors Engstrenne Program Managemers = 1356 NRR,1IIIFB B E E I 3-3 Dif R OB 7 N 06 Closed Banatsee-py

1. i Westinghouse should prodde informaEegarding IISI(haradenstics Westmglwune should descree lww patentaal proNema associased with lugh i

markload will he odere.Ged earl in the desip praeus, and how the concerns noted in the evaluatson above will be addressed. W- <-f - siwn Id also j 3 desmbe how the desip of workstations (mssde and outside the MCR) ensure support of optimal operator g i. = under a range ofcondations to .1 'l Meeting of 3rl095. Same as the "Adeon N note en the open item drunpaion field for dhase item number 1354 j ~ Meetingof 3'1095-NRCreviewed our design process as deunhed in the SSAR. R Als and in WCAP I 2608, and WCAP 9817 and provided feceed The NRC reviewed the SSD procedwes of WCAP 12601 mith resped to covenng issues hke "providmg guidance to IISI designers for addressing / utiliinng desip inputs such as the FD f A results Note that the procedures will be at a higher level, not specifically referring so the FBTA or other spenfic IIFE analpes or reports The staff she redewed the Alarm Svstem Desip Guedefines and the Interien Report est Tedanical Principles for Corguter Dased i Dnplan of Data (twdh on file in Rod nfle ofFece) Feceack from NRC was that the display docunnent does provide the inwended guidance 6495. Fax of a eesponse to this open dem was sent to I tkmgarra NRC revicued the response and provided feeenci indicating that the respomac{ neceptable See NRC letter dated 7/2595. SSAR revision required for closure. Revised SSAR Chapter it sulwmned in Revision 9,7/31/96. This ir.cludes SSAR 18 8, llaman Sperm Interface Desip and SSAR lt 2. Ilumen Fadorsi E"t***BE*Fn uanagmein l l i Page 48 Totel Records 13d t 6

C AP600 Open Item Tracking System Database: Project Management Report Date: 11/21/96 Selecties: [NRC Branch] like NRR/IDIFB' Sorted by NRC Branch Descrigeson Itern DSER Sectionf NRC Memo (W) NRC l No. Ikandi Queenson Type 5tsaus Detail 1ast Mod Date Stasus sessas tmar No. I Dee 1357 NRMillFB 18.3.l.3-4 DSEROI F26/% Cleasd Action W [ gi Westinghouse should provide unfarnutiort regarding deasy featwe selectsen. W - f should describe die precusa used to evaluase desigst ahermatives identified in the staffs evaluatinrt af kleeteg of 3/10.95: h )h Actinn W: Westinghouse to review the les el ofdetail for desip cevtification relative to the MMI key features. Specifically need to maktas whether ce not the " mission statements' or pupnwis) are unrth certdying If mission statemeres are not certified then the key features arent certified even frorn a conceptual lewt Will need to clearly idersify those trussums that we are cwermg We will indicase thcae key fessures that we do wt want certaried and their mission statemeras Scheeste will need to he quick forcause it will impact NRC scope of review. 5/11 Phoncon with J Ilongarra -I told Jim that we manted the 1151 desip resiewed at the 1, ...:.-ion plan level (as they how Ame) and thes there were no detip features that we wanted rencued at a more drtailed er complete level _ Meetmg of 3/1095 NRC revicued our desir process as described in the SSAR, RAls and m WCAP 12601, and WCAP 99 I 7 and preided feveeck via letter of 7'2595 Action W. Rmew and makess NRC feedhad issues Revised SSAR Chapter iR suhrmited m No +unn 9,7 31196 This includes SSAR 1R 1, llaman S. em Interface Desip and SS ut i8 2,ilumen Factors -Emem_em_ ng P_rogr_am_M_.anagemen_t___ ,r 1355 NR R,11HFil 18 8 f.3-5 DSERoi s'21 % Resolved L.:.J -A cT-W Westinghouse should provide information regardk the detailed guidelines for IISI desiers Wesemghouse shoesid provide the requested hanenok and guidelines as samples of the results of the process I o Meeting ef 3'10 95-f Same as the

• Action N note m the open riem desceiggion field for dhase item number i154 i

NRC reviewed the guidelme 4M and found them accegtable See NRC letter dated 7/2595. ITAAC required for clorure. Resised SSAR Chapter i3 subimited in Revision 9,7/3196 This includes SSAR lR R, ilumen Sym Interface Desip and SSAR 15 2,11uman Factors Engineering Program Management Element 7. SSAR Rev 9 Ch 18 and WCAP.I43% Rev i submritats. ITA5. rep to close. _. = _ I 1 Page: 49 Total Records-134

_ =.. . ~ o AP600 Open Item Tracking System Database: Prsiect Management Report Date: 11/21/96 Selection- [NRC Branchj like WRR/IDIFB' Sorted by NRC Branch Duription hem DSER Sectusif NRC Memo N NIC No. Branch Question Type Status Detail las Mod Daae 9taans h immar No. / Dane 1339 NRR/HilFB l88.1.3-6 D3ERot s/2195 Resolved DeuubadAc7 @

1. estinghouse simuld gwodde informatsat regenhng the detailed HSI design analpis W ^

should decrihe in more deemil the analymus sh by which desip imues not cowred by available guidssur are identified and resolved in partscular. Waushghause shnuld describe the means by which evaluaiton results are translated into desip guidance (see Criterien I,"IISI Design Process Guidance,* in this sectiert d Meetmg of 3fl095.

• / GIN Same as the "Actist N" note in the open item descnpaion field for ease item number 1134.

NRC renewed the quidelme documents and found them acceptable See NRC letter dated 7/23/95. ITAAC required for cleaure. Revised SSAR Chapter 18 submmed in Redsson 9. 7/31196 This includes SSAR I E R. Ilumen System leerface Desip and SSAR IS 2. Human Facton Engineenng Program Management Element 7. SSAR Rev 9 Ch it and WCAP.14396 Rev i submittals fTAAC req'd to close. _ -. _. - - - - - - -- - =- : z .___:-_.___=-: - 1360 NRR/IllIFB 18813-7 D3ER G 8 2m Resolved pp pf Westmghouse shE55 ps 'n informIa son r[garding the HSI evaluation Westingfww.e should describe the rationale for the HSin, desip elemems, and procedures selected fW es aluatmn. and for the points in the design process at which the evaluations u, to occur Westmghouse sh.ntd also describe the process for identifung and resolvmg conikts in guidance, as well as the ratmnale for desip decisions that cordisct with guidsaux. f Meeting of 3'10 93: Same as the " Action N note m the open item descript.on field for ease stem number I 354. NRC reucued the quidelme documents and found them acceptable See NRC letter dated 7/2595. ITAAC reqiured fee closure. Revised SSAR Chapter it suhnuned m Resismn 9. 7:3196 Uns irmludes SSAR IE R. Iluman System Interface Design and SSAR I2 2, Human Factors Fngmeenng Program Management Element 7. SSAR Rev 9 Ch IR and WCAP-14196 Rev i submettals ITAAC required to close. Pase: 50 Total Records-13d

AF600 Open Iteen Tracking Systemi Database: Project Managesment Report Date: 11/2I/96 Selecties. [NRC Branch] hke NRRADIFir Sorted by NRC Branch Descrytian leesa DSER 5ectment NRC Meine (W) NRC Na Iksna W Type Status Detail I.ast Med Dane 5tsaus samans tenerNa / Dune IMI NRR/HHFB 18 8 l.3-8 D5EROI t'n96 Resolved $muG55d g7 Q

1. 7 www.e should demise Iw. en Hsl d isn win he doc =i emed w medanime ihm u descr* how er anal H5I & mist wm be W.

=ceep-wins the ham siven in sie erherm Meetmg of 3'I093: Sarne as the

• Action N' note in the open hem description field for ease item number 1354.

NRC reviewed he quedelme dncuments and found them acceptable See NRC letice dated 7/2595. ITAAC required far closure. Revised SSAR Chapter It sufmutted in Ression 9,7/3196 This includes SSAR 18 3, Human System Inserface Design and SSAR lt.2. Hunan Factors Enginemng Propam Manntwnent. Element 7 SSAR Rev 9 Cli 18 and WCAP-14396 Rev i suhmattats ITAAC req'd to close -_===:-~=-.-_-. - :____=__.__ L P i Page: 51 Total Records: 134

AP600 Open item Tracking System Database: Project Management Report Date: 11/21/96 Selection [NRC Branch) hke NRR/IDIFB' Sorted by NRC Branch a Desenpason item DSER Section/ NRC Memo (W) NRC No. Brandt Question Type Status Detail last Mod Date Status Stanas limar No. I Dane 1362 NRR/HHFB 188231 DSERol M5/96 Closed .Antumw4f h LT-N WM J _._; should desenhe how the safety parameter esplay eymem (SPDS) deaiyi will be i / - " to nesse all partammen HSI emies menria. Westmghouse should provide assurance that the SPDS design will meet all of time patasere criteria as part o(ene HSL W '." should &ambe how e.h the SPDS wi!! privide a rapid and concise display ofcritical plant variables to cnneral room operators W should deambe how the SPDS J implementation will he convement to control room persamel. Westmghouse should desmhe how the SPDS functson will contmucumfy duplay plant safety mformatum. Westinghouse should descnhe how the SPDS will adiieve a lugh degree of rehahility. W ' J -s should desenhe liow the SPDS will be suitably isolated froni eledrical or eleoronic irmerference with safety syinems. Westinghouse should describe how human factori precyles will be mcerrorated ireo the SPDS Westeghouw should descnbe how the SPDS will display sufficwra information to deternme plare safety status wah respect to safety functions Wesimghouw should desenhe how proce&sres and operstor tranung, addressing actions both with and without the SPDS. will be implemented Per 2:16/93 conference call between Jun llongnerA JcJm O'llars & Kercit Easter. Roth. Mumaw: Action N - Send us any further shortcommgs frown a review of our rev. I resporne to R At 620 43 compared egneut the DSER issue I t 8 23 critena (311 meetmg in Morvocntic) Action W - After recen emg the deficicnes test from NRC. respond to it Meetmg of 3.3 93 Actions W Westeghouse to a&ess the comments gwonded by the NRC maff during 3 'S enectag Refer to meetag notevenremes foe the details in general one werd answers oes or no) as found in RAI 620 4R were insufficient. Each of the 10 CFR 50 34 saguirements (I a - Ie. 2 - 9) and the aehteonal mformation that was needed was dncussed Westmgbouse tojustify difference between our critical safety limction parametm on the SPDS and thoac specified by Nt' REG 1142 and the genenc letter Need to address the cntical safety functsons listed ori page 3 of NUREG 0737. Refer to meeting notes / minutes for further detail _ _ _ _ _ Meetmg of 3/893 Act on W - Westinghouse to address the comments provided bv the NRC staff during 3/8 nieeting, Refer to neretsng noses / minutes for the details In general. one word answers (yes or no) as found in RAI 620 4R were imufficient Each orthe 10 CFR 50 34 resquirements (la - le 2 - 9) and the adddional mformation that was needed was discussed Wesemghouse tojustify afference between our critical safety function parameters on the SPDS and those specified by Nt ' REG I 342 and the generic letter. Need to address the critical safets mctims listed on page B of NUREG 0737. Refer to sacetmg notes'mmutes for further detail Westinghouse mill fax to the NRC fillFB a response to th 6 open itern. This respnnse will be sent as a draft RAI revision 2 to Q620 48. He NRC action will be to review the resp <mse and provide fee &ack. Dr formal b..~.; ; ion to close this item will be a reviseen to SSAR section it 9 2 2 6 ce the formal revisien 2 to RAI Q620 48, both of which would incorporate NRC feedback as resuk ofreviewmg the draft RAI revision 6/7/93: Fax of document providing responses to the 9 enteria identified in the open item was sent to J Bongarra NRC revwwed this documens and provided feedback via fax of 9/21/93 Six of the nine SPDS cntens are coreidered resolved i Action W. To respond to remaining quest ons in fax of 9/2 8 /93. (see NRC response letter sent 9/23.95) Revised SSAR Chapter I R suhmitted in Revision 9. 7/3196 his includes SSAR 18 8. Human System Interface Desigro I i Page: 52 Total Records: 134 i l l t I

o AP600 Open Iteni Tracking Systent Datstese: Prsject Management Report Date: 11/21/96 Selection: [NRC Branch] like NRR/IDIHF Sorted by NRC Branch a Description hem DSER SM NRC Memo NRC No. Brandt Queenson Tne Status Detail tant Mod Date m Stama tamarNo I Der 1363 NRR/HHFB I29.3-1 DSERot F26% Closed f_i - - E'- g Ac r-M Mf Westanghouse simuld cianfy the scge of the proceeste 1.A,.-. pogram. Per 2/16/95 conference call twtween Jim Bangarra, Jolm 011 ara A Kerdi, Easter Roth, Murnsw: Action W - Semt the revised wrneup to applicable sedm of SSAR chaleer I 8 Westmghouse sent a draft remion of SSAR sedmn iE 9 R to the NRC 1% sedian will reference 13 5 3 which will state that the a aN,,m of procedures is a cornhmed license amlicare respnmihitrty. The rensed 13 $ 1 mill he sere as part of the formal revision 3 to the SSAR. NRC to renewed draft of It 9 R.see NRC fat of 2 2096 ACTION W: to respond to concems of the fat; *as discussed in cmference call of 3 '21/96 g losed - Procedure deselopmeve is addrew.Iin reused SSAR Chapters t 3 and Ia submitted in Rev 9. 7< 3196. C

---=.--=_-=,.:

=m-__- 1364 NR R/lillFil 18 9.3-2 DSER OI s t1% Closed M NSD-NRC 96-4794 ASTM 4{ Westinghome should prende the tedescal bases for pacedure deve!opnent Wester ghouse should deambe how (or whether) enethoda, in addetaan to LP ERG companson, will be used for procedure deselopment Per 2/I645 conference call between Jun flongarra John Orliara a Ee~h, Easter. Roth, Mumsw-Action N - Jun ihmgarra willireerface with NRC Rt syste m bra.ich who asse t-d 6: 2/2/95 meeting in Redville (AP600 ERG preentation) and decide what the NRC status rs,ie Ct.OSED or gise us feedbact on what our action needs to be. Fee &ack given to W -" " _ in 2/23 conference catt was that (the material peserned at 2/2 eneetmg (hasis of E RG desclopment) was accegnable an_d the action-W is to deliver the ERGS and docummis by May Action W I'ee&ad grten to Westmghouse in 2/21 conference call was that the matenal gesented at 2'2 meeting (basis of ERG developmere) was accepta action.W is to deliver the ERGS and documents by May 31,1995 Status update ponded by phone (D Jackson I/2 I) Action W is to complete anal tical basis for AE-l. AES-12. AE-2, and sugporting &cumentation for shutdown ERG 3 Review attower, tm power / shutdown ERGS and background for at-power and low power ERGS and the draA of SSAR section i 8 9 I sent on See NRC fat of 2/2096. ACTION W. to respond to concems of the fat, was discussed in conference call of 3/21196. Closed - In Response to letter NSD-NRC-96-4794 Page: 53 Total Records 134

AP600 Open Item Tracking System Detalese: Project Management Report Date: 11/21/96 Seleolon: [NRC Branch] like NRR/IDIFF Sorted by NRC Branch e e Dargeien item DSER W NRC Mems (W) NRC No. Ikunch Questien Type Status Detail im Mod Deee Status Statua JJaar No. I Dune 1363 NRR/HHFB 1893-3 DsERol 9/196 Resolved Action W/NSD-NRC-96-4803 4f Westinghouse should povide informauen regarding the writer's guide. Westinghouse shensid descree leew er wrieer% guide will addrama the auque fessures of a paper-and cmryuterensed presentation ofprocclures Per 2/1655 conference call between Jirn Bongarra. John 01ters & Kerch, Easter. Roth, Mumsw: Action W - NRC agreed to resolution path *in principle" and we need to send revision to SSAR section Action W Per 2/1695 conference call between Jun Bongarra. John 011 ara & Kerch, Eastre. Roth, Mumsw: Acticut W - NRC ayeed to resolution path "in pruiciple* and we nent to send revisaca to SSAR sedian Westinghnuse sent (da fas er fedeq to the NRC a draA rension to SSAR I8.9 8 on t'l SS$ wluch will provide the response to this open item Action N NRC to resiew draft of IR 9 R see NRC fas of 2 20 % ACTION W. to respond to concems of the fat, uas desnessed in conference call of 3 21196 Element t Wah submittal of SSAR Rev 9 ch IR and WCAP.I4690,the MMIS portion of this item is cicaed Need to determese what is required to close ERG partien ofitem Resolsed - Per DCPNRC0589, this item unit he closed wah sulwnrttal of th atymer ERG's t Page: 5d Total Recordr 13d

+ AP600 Open Item Tracking System Database: Pryject Management Report Date: 11/21/96 Selecties- [NRC Branch] like NRR/10 ff'B' Sotted by NRC Brunch Damgeien lean DSERSe h NRC Memo (W) NRC No. Ihanch Queseson Type Stanis Detail tast Mod Date Stasma saneam Lamar No. / Duse 1366 NRJUHilFB 13 9.3-4 D5EROI W196 Remotved Action W NSD-NRC-96-4805 b Westanghouse should provide information regarding the carenes of procedsrea w J slumid dancribe and provide a renamiale for the eduences,if any, between the paper. and computer 4ased presentations of the items in this memon (or in NUREG0999). Per 2'16.95 confnence call between Jun Bangarra. John 011are A Kerch, Ensser, Rceh, Mumaw: Action W - N RC agreed to resolution path "in principle" and we need to send rnision to SSAR section Action W Per 2/1695 conference call between Jim Ikegarra, John O'llara & Kerch. Easter Roth. Mumsw: Action W - NRC apeed to resolution posh *in pnnciple" and we need to send resision to SSAR scoion Westmedmuse sent (sia fat or fedes) to the NRC a &all revision to SSAR I e 9 8 on 2 I E95 which provided the response to this open item Action N NRC to renew draft of IR 9 R, see NRC fas of 2 20 96 ACTION W: to respond to cmcerns of the fat, was discussed m conference call of 3 21/96 Elemere a With sulmuttal of SSAR Res 9 cii I t and WCAP.I 4690, the MMIS portion of this item is closed. Need to determane what is requerd to close ERG portion of this item Resolved - Per DCP.NRC0589, this item wdl he closed with submittal of th seemer ERG's. 1367 NRR/IIHFB 18935 DsER.Ot s e 2m Closed -Artsuur?t* NSD-NRC-96-4794 _ Mfd f y Westinghouse should provide information regardmg the s)wytom-based emergency operating proceesres (EOPs). Wessinghouse should subme the AP600-specific E RGs so that the staff can senfs that the Fors will he surgeom-based k fek[ Per 2/1695 conference call between Jim Ikegarta. John Oliern & Kerch. Eamer, Roth, Mumaw: f sO* 8 1 Action W - NRC agreed to resolution path "in pnneiple" and we need to send the ERGS and background documents to NRC. s O [ Y ). f g Action W 0 Per 2/1995 conference call between Jun ihmgarra John 011 ara A Kerch Easter Roth, Mumsw: Action W - NRC agreed to resolution path *in preciple" and we need to send the ERGS and background documnas to NRC. T1rese will be sere via a phased approach with phase ! ERGS to be sent Si3 L 95. Stasus update provided by phone (D Jackson 8/21). Action W is to ccenplete analytical basis for AE-l, AES-1.2. AE-2, and mapporting documneasion for shutdown ERO. Action N - Review at-power,Imv power / shutdown ERGS and background for stymer and low power ERGS. Closed In Response to letter NSD-NRC-96-4794 Page: 55 Tolel Records. 134

o~! t AP600 Open item Tracking System Database: Prr. ject Management Report Date: 11/21/96 Selecties: lNRC Branch] hke NRR/IDIFIr Sorted by NRC Branch i thumption k lism DsER Saceant NRC M.,. (W) NRC No. Ikonch 'h

• Twr Staeus Detail Ime Mod Done Stense Sammes

,Imer No. / Duse 136s NRR,HHFB ls 9.34 D5ERol 9.%6 Resolved Action W [ NSD.NRC-96-4805 P( w"-r shnued provide inrannat== resarens e vav pmonsure. Weemsp=nme should claney the.- ". erthe EOF Vav to me M-Mis s evaluatxe issues The VaV process for hardecry precedwes should also be demmhed e Per 2r1695 conference call hermeen hm Ilongarra. John 01 tars & Kerch Eamer. Roth Mumsw: e p Ac um W - NRC agreed to resolutenn path "en prmnple" and we need to send revision to SS AR section Action W Per 2r16-95 conference call hetween Jim flongarra, John 01tara & Kerch, Easter, RotA Mumaw: Action W - NRC speed to eveolutson pedi in pnnciple-l and me need so send resnian to SSAR section [ Westingpiouse sens (sia fas tw fedn) to the NRC a dran ression to SSAR I 8 9 R on a I 2 95 which provided the response to this open item NRC to resieu draft of IR 9 R,see NRC fas of 2 20 % ACTION W to respond to conscens of the fat. mas discussed un conference call of 3 21/96 i Element 8 Wsth suhmrital of SSAR Res-9 th It and Wr'AP.I 4690, the MMIS partoon of this inein is closed Need to decernune when is mguired to close ERG portion . - - - -- -.-Resolsed - Per DCP NRC05R9, this stem will he closed wnh suhnnetal of th astower ERGS [ s l i L i i i i s 4 ? Page: 56 Total Records: 134 i

AP600 Open item Tracking System Database: Praject Management Report Date: 11/21/96 Selecties: {NRC Brunch) like NRR/lDD'Ir Sorted by NRC Branch Denmptim item DSER Sectica/ NRC Memo (W) NRC No. Brandi Qmeson Type Status Detail Im Mod Dese Staeus Status basar No. / Dune 1369 NRR/IIHFB 18 9.3,7 D5EROI 9496 Ramolved . Action W NSD-NRC-9400$ C W- ' j --- shmid provide information regardag the coniputee-based procedures W^ J should describe glie process try which Imanan enginecrms inues associated with cmputer4msed procedures will be resolved (e g, concept testing, and other analysus). (p Pee 2'l6.95 conference call between Arn Ilongarra, Mui O11ars & Keech, Easter Roth, Mumsw: Action W - NRC agreed to resolution path "m principle" and we need to send resision to SSAR section. Action W Pa 2/1693 coninence caft between hm ihmgarra, John 011 ara & Keeds Easta, Roth, Mumsw: Action W -- NRC agreed to res 'ution path m principle" and me need to send rension to SSAR sestion Westeghouw sent tsia fas a fedes)to the NRC a draR reviuon to SSAR I 2 9 8 on til 895 mhidi provided the respanne to this open item NRC to resieu draR of It 9 R, see NRC fas of 2 20 96 ACTION W~ to reW to concems of the fas; w as discuued in conference call of 3 '2I/96 Elemere t With subm ttal of SSAR Res 9 6n IE and WC AP.I4690, the MMIS portion of this ite i es cic ed Need to determme what is requerd to dose ERG porteen. Resolved - Per DCP.NRC0589, this item will he closed with subnurtal of th at p=a ERGS. - - - -. _ - -. = =.. _ --_m--. Page: 57 Total Records: I34 = - - -

o AP600 Open item Tracking System Database: Project Management Report Date: 11/21/96 Selection: [NRC Branch llike NRRA DIFIr Sorted by NRC Branch Descryuan item DSER Section/ NRC Memo (W) NRC No. Brandi W Type Staans Detail Imt Mod Date Staans Staeus immer No. I Duse 1370 NRAHlfFB 18933 DSEROI Stw Resolved Action W NSD-NRC-W805 gb Westsnghouse ahnuld gwr, vide informstson regarthng W --

---

s. W - _

_ shansId descree the adunuumative precedures that will muure that hardcopy procedures remain cwrent and consistent with the,, ;4esed pmceearts Per 2/1695 conference call between Jun ihmgarra, John Gilera A Kerch, Easter, Roth. Mumsw-Action W - NRC agreed to resolutwn path "in principle" and we need to send rnision to SSAR wtion. Per 2/16/95 conference call hetween Jun Ibntarra, John Gilars A Kerch, Easter, RcA Mumaw: Action W - NRC agreed to resolution path "in principle" and we need to send revesum to SS AR section Westmghouse sent (sia fas or fedes) to the NRC a draft revision to SSAR 18 9 R en 2 'IR 95 which provided the response to this open item NRC to review dran of IR 9 R.see NRC fas of 2 20 96 ACTION W: to respond to concerns of the fas, was discussed on crmference call of 3 21196 Element 8 Wuh sutw ittal(JSSAR Res 9 th Ie and WCAP.I4690.the MMis portuwe of this item is ciceed. Need to deterwune what is required to(kme ERG portum Resolwd - Per DCP NRC0589, this item will,be closed with suhrnitial of th atpower ERGS. _ _ _ _ = r.--- R Page 58 Total Records-134 i

AP600 Open item Tracking System Database: Project Management Report Date: 11/21/96 Selection: [NRC Branch) like 'NRR/1H UTr Sorted by NRC Branch Descryim item DSER Sectionf NRC Memo (W) NRC No. M Qu'esson Tne Status Detail im Mad Dese Staeus Statua Jmar No. / Dane 1371 NRR/HIIHI 139.39 DsER G 9496 Resolved Action W NSD-NRC 96 4805 Westinghouse should provide informatam regenhng prar==b== use. W-f w should describei h for - % and une c( herdonpy )h procedures, as backups either in the cxmtrol room ar as locations outside the cetrol roont W@ew should also demaibe how earuptson of ongome activity by automatically accened procedures will be manamired h Per 2/16/95 conference call twtween Jim Ibngarra, John O'llara & Kerch Easter. Roth, Mumsw: A4 tion W - N RC agreed to resolution path "in principle" and we need to send revision to SSAR sectiert Per 2'l695 cumference call hetween Jim IWgana. John O'Itars & Kerch Fasta. Roth Mumaw: Action W - NRC apeed to risolution path *in princyle" and we need to send revivon to SS AR mtion Westinghouse sent bia las or fedet)to the NRC e dran rension to SSAR IS 9 8 on R 18.95 whwh provided the response toilus open item NRC to renew draR of IR 9 R ; see NRC 1es of 2/20 96 \\C1 ION W: to respond to concems of the fat, uas discussed in conference call of 3'2I/96 Element R Wsth sulwnsttal of SSAR Rev 9 ch it and WCAP.I 4690, the Mklis partum of this stem is closed. Need to determane what is required to dow ERG portson Resols ed - Per DCP NRC_0589, t_ius ste.m.uill be closed mith submittal of th atpwer ERGS. Page: 59 Total Records: 134

AP600 Open Item Tracking Systeni Database: Prcject Management Report Date: 11/21/96 Selecties: [NRC Branch) like NRR/Ill!FIY Sorted by NRC Branch Denmption tiern DSER Satm' NRC Memo (W) NRC No. Ihandi Queshen Type Status Detail tant Mod Date 9tanus Staans tamar No. I Date 1372 NRR/HHFB 18 9.3-10 DsERCI 83M6 Clamed M y pg Westinghouse should provide infoemstion regar&ng the source snatmal for proce&me i.- - Westag$nouse hhe desebe the sauces or eupmence drawn upon in developing guidance for the design of the cerryuter4esed proce&rvet Conference call with NRC 3/2195: (J Bongarra. G Galletti. T Kenven. J 011 ara. J Ifiggins. Aster &s J Faster. E Roth. S Kerth) Action W: Westinghouse to tense the apphcable chapter i E SSAR sectenns to reflect the staternents and process described in the closure petit The NRC's intera of this open item is lumted to the_computetuation ofprocedures Conference call with NRC 3'2 I 95- (J Dongarra. G Galletti. T Kenyon. J Ollars. J IliRams. A.Sterdis, J Eaear, E RaA S Keech) Action W: Westingbnuse to reshe the awhcable chapter IR SSAR sections to reflect the statements and swocess desmhed in the closure path. The NRC's unent of this open stem is hrmted to the computernation of procedures Westinghnuse sent (sia fai or fedes) to the NRC e dran reusi.e s.i SSAR 18 9 8 on a 1895 which prended the response to this open item NRC to reviem draft of IS 9 8. see NRC fax of 2'20 96 ACTION W: to respond to concems of the far mas discussed in conference call of 3'2 I/96 Elemera S With sulmuttal of SSAR Res 9 ch it and WCAP-14690, this item is clomt t Page: 60 Total Records: 134

d AP600 Open item Tracking System Database: Project Management Report Date: I1/21/96 Selection: [NRC Branch] like NRR/lDIFir Sotted by NRC Branch Description leern DSER Section/ NRC Memo (W) NRC No. Branch Question Type Status Detail last Mod Date Staean Stesa Lamar No.1 Date 1373 NRR/IIIIFB 18.10 3-I DsERol 7/W96 Clemed Resolved / M$ Weatingt suw should pwide informanan resanhng the traming poram mi= ion. W-J should servide adw wannmen ram the vence= ihat will adeess the rationale twhind the sciect.cn of the idernired pudiens for developmg trama=ig propens, as well na Mm ^. on the atur related areas identified in this enterica Per 2/1695 conferevice call twtween Am Bongarra, Mwi 011 ara & Kerch, Easter, Roth, Mumaw: Action W - NRC agreed to resolution path "en preciple' and we need to 1. issue d=urnem, 2. prepare for March NRC meeting by list of COL applicant responsibility, and 3 reviw SSAR section Meeting of 3's 95 Action W: DraA Col. Action tiern Training popam developrwne is the responsihihty of the COI. applicana. Creation of this COL itern will clone all 15 DSER dems(1810 LI thru 3 I5)that it ad& esses Consider eussing words in chapter I) SS AR and DSER. Action item should he in chapter 13 and cross referenced from thapter I8 Two new MFETING Open items wete created, both Action W refer to emme item number 206I and 2062. DraA SSAR reTes~ son f$ section t R 9 9 se ' to UN'RC IIIIFR ClmureIull occur when formal revision 4 is dehvered. Action N NRC to resicu markup section and pmide feedback Closed. The traming pregam development is addreued in revised SS AR Chapters 13 and i B aubnutted iri Rev. 9. 7/3196. Action W see NRC responw sent il 2I 95 1374 NRR/IllIFB 1810.32 DSE R OI 7N Closed Resolved / gq Westmghcme should dcEnhe ttameng reqlu N ' Westinghouse should desmbe how the AP600 training pregram developmers wdl ensurr consistenes ] ~ ~~ =sth the regulators documents cited in this mtenon Per 2/I6S5 conference catt between Jun Bongarra, John (Tilara & Ken-h. Easter, Roth, Mumsw-Action W - NRC agreed to resolutaen path "in pnneiple" and we need to I issue document & SSAR resision, 2 prepare for March NRC rrwetmg by I se ofCOL applicant responsihihty, and 3 reuw SSAR section Liectmg of 31t 95 Action W; Draft COL Adian item Trauung pogram development is the responsibihty of the COL apphcare. Creation of this COL stem will clone all 15 DSER stems (1810 3-1 thru bl5)that se addresses Consider custmg words m chapter 13 SSAR and DSER. Action item should be in chageer 13 and cross referenced from chapter 18 Two new MFETING Open Items were created, both Action W, refer to eene item number 2061 and 2062__ _ _ Dran SSAR rension for section iR 9 9 sent to the NRC IIllFB Closure wds occur whevi formal revision 4 is delivered Action N NRC to renew markup section and povide fee &ack Action W - nee NRC response sent iI12195 Closed. The tramingprogram deselopment is addressed in revised SSAR Chapters I3 and iE aulamned in Rev. 9. 7/3 I/96. 1 Page: 61 Total Recordr 13d

e AP600 Open Item Tracking System Database: Project Management Report Date: 11/21/96 Selecties [NRC Branch] hke NRR/IDIFB' Sorted by NRC Branch Description item DSER Sata / NRC Memo (W) NRC No Branch Quesexus Type Status Detail last Mod Date Status Stanus 1, ear No. I Dune 1375 NRR/HHFB 18103-3 D5ERol 7/26 % Closed Resolved pk Westinghou. e should describe the SAT training approach Westinghouse should provide heal inf:smstson on ame S AT appreadt dist it is uses, s particularly with regard to the evalualmn elemmes of the SAT process Additionally, Westanghouse should provide suForenshan on how cogputiw task analysis wdl supplemme the mformation obtained using a tradnional SAT appondt Per 2/16/95 conference call hetween Jim Bangarra. John 011 ara & Keith Fader. Roth, Mumsw: Action W ~ NRC agreed to resolution path "rn pinciple* and we need to 1. issue document A SSAR rension, 2. prepare for March NRC mertang by hat of COL applicant responsibiletv, and 3 revise SSAR sectmn Meetingef 3/291 Action W. Draft Col. Action Item Training Foeram development is the responsehshty of the COL apphcant Creation of this COL it m will close all 15 DSE R items (It 10 3-1 tluu 3-15) that it addresses Consider existing words in chapter 13 SSAR and DSER. Action item should he s' i.hagner 13 and noss referenced from chapter I* Iwo new MF ETING Opm items were createdy Action W. refer to ease itan menher 2061 and 2062 Draft KSAR reusion for sectmn it 9 9 scow to the NRC tillfit Closure will occur when formal revision 4 is delivered Action N NRC to reuew markup section and povide feedback l t Actmas W - see NRC response sent 11:2195 Closed. The traming popam developenent is addressed in revised SS AR Chapeers i 3 and 18 subevutted in Rev. 9,7/31/96 1376 NRR1tilFB 18103-4 DSER ot 726 % Closed Resolved / yk Westinghouse should discuss organizational roles related to training Westmghouse should specifica!!y derme the roles of all argeruzations in developmg and unplementmg the AP600 traming pograms. Per 2'1695 conference call between Jun Ilongarra. John O*Itara & Kerch, Easter. RM.It Mumaw-Action W - NRC agreed to resolution path "in pinciple* and we need to I. issue docummt & SS AR revision, 2. prepare for March NRC meetmg by hst of COL apphcant responsibihts. and 3 resise SSAR sestum Meetingof 3't.95: Action W: Drall COL Action trem Trammg popam development is the responsibdity of the COL applicant. Creation of this COL item mil close all 15 DSER items (It to 3-1 thru 315)that it addresses Consider existing words in chapter 13 SS AR and DSER. Action item sinould he in chapter 13 and cross referenced from cha[ter lR_Two new MIiETING Open hems were created, both Action W, refer to Anne itan number 2061 and 2062. Draft SSAR revision for sectmn i2 9 9 sent to the NRC lillFB Closure wdl occur when formal rension 4 in delivered Action N NRC to review rnariup section and povide fee &ack Action W - see NRC response sent II/2I/95 Closed - The trmingprogram develornu w is addressed in rensed SSAR Chapters 13 and 18 submsund in Rev. 9.7/31/96. Page: 62 Total Records i34

se AP600 Open Item Tracking System Database: Project Management Report Date: 11/21/96 Selection- [NRC Branch] lake NRR/lilIFir Sorted by NRC Branch Descrquian item DSER Sectionf NRC Memo (W) NRC Na Branch W Type Stana Detail im Mod Date Steene Se m im Na / Date 1377 NRR!HHfB 18.10.3-5 DsF. Rot 7/ mss Clamed Resolved it % Westinghouse should discuss the qualdicatinua of training personnel W ' "- should provide addamanal. ._Z . en 9w. . of organizations and persneuwt to be involved in the ".a,-..: and comk1 of treW Per 2/1645 conference call hetween Jun Bangarra, John (yllara & Kerch, Easter, Roth. Mumaw: Action W - NRC apeed to resolution path "in principle" and we need to I, issue document & SSAR revision, 2 prepare fw Mardi NRC nuting by list of COL apphcant respnnsibildy, and 3 reuse SSAR sectum Meetmg of 3 2 95: Action W: DraA COL Action tiem Traimng propam dnelogvnent is the responsib hty of the COL applicase Creation of this COL itan will close all 15 DSEP dems (la 10 31 thru 3 15) that it addrnnes Consider custeg words in chegwer 11 SSAR and DSER. A1 ion item should be in diagen 13 and cross referenced from chalter IR Two new MT ETING Open items were created hoth Action W, refer to ease dem number 206l and 2062. 'I55 SSTiiiesmnn for wsinon i2 9 9 sent to t!'w hRC 1881ii5 AImure mil oc6Anhen formal rension 4 is delivered Action N NRC to resnew markup section and proude feedhai Action W see NRC response sent iI 2I 99

• • [* I Tarn nehyjaknsed_m reused SSAR Chapters 13 It suhnused in Rev. 9.7/31%

t r Page: 63 Tv.al Records: 13d

se AP600 Open Iteni Tracking Systene Database: Pr ject Managensent Report Date: 11/21/96 Selecites: INRC Branch] like NRR/IDIFir Sorted by NRC Branch Descrvtion l Item DSER Section/ NRC Memo (W) NRC No Branch Omahan Type Status Detail Imt Mod Dune Stamm Se m lenar Net / Dane 1373 NRJt/HHFB 15.1034 D$EROI F2696 Clamad Remofwad / d Wests shause should descnhe the trunmg scope. W ' f _ _ should provide a&htional Mormshon on how $w AP60G ensang preyent will addreas sie scvve of training This information should include casesones of personnel (e g senior reactor opersaar) to be trained, as well na spacinc plass % (normal, upset, and emergencv) operational activie.es (e g. operations, masnienance, teneing, and survallanceA and HSI cxweginnenes (e g. MCR, emergency opernasons facility. remnte shutdown panel, local control stations) Per 2tI6/95 conference call between Jwn llengarra, klm 011 ara & Kerth, Easter. Roth Mumsw: Action W - NRC agreed to resolutinn path *en pnnciple* and we need to l issue document & SSAR revision, 2. prepare for Mardi NRC meetsngIrv proving list of Col. applicant reywisihitety (1378,1381,133 3.13 4?), and 3 revise SSAR section I Meeteng of 3 3 DS: Action W: Dran Col. Actenn item Training program development is the responsebelsey of the COL applicant. Creasson of this COL seem will close all 15 DSER stems (Ie 10 3-1 thru 3-1s)that et addresses Considrr existing words in chapter 13 SSAR and DSER. Action item should be ai chapter 13 and cross referenced from dialwer !8 Tmo new MF ETING Open Itans were created, both Adion W; refer to Amme item number 2061 and 2062. l DraA SSAR revesson for sedson it 9 9 sent to the NRC lllif'll Closure will acrur when formal revision 4 is delived Action N NRC to re iew mariup section and proside ferend Action W - see NRC respome sent IIllt 95 Closed - The traeninggogram desclopmmt is addressed in rnised SSAR Chaptm I and I E suhnutted in Rev. 9,7'3 I96 t i t i I Page: 64 Total Records: 134 I l

,e AP600 Open item Tracking System Database: Project Management Report Date: 11/21196 Selecties: [NRC Branch) like NRR/lD IFB' Sorted by NRC Branch Descrytion Item DSER W NRC Memo (W) NRC No. Hranch Question Type Status Detail Im Mod Date sessus Status I; mar No. I Date Resolved [ 1379 NRMlHFB I B 10.3-7 DSERot 7/26 % Clemed 4 Westeghouse should desenhe how flumen Factas Engmeenng Proyarn Review Madri(HFE PRM) elemens are incorporuand W the naams pleasung objectives Westinghouse should descnhe how training issues mit be identifed from the seven elsenenes fw use in deriving lannung objedives, namely. Operating Expmence Review. Function Analpis and Allocation Task Analysis,ilumen Reliabildy Amenamnd. HSt Damian, Plant Pr~=A-ve, and Vmfication and Valwintion Per 2/1615 conference call between Jun Dongarra, John (Yllara & Kerch, Faster, Roth, Mumsw: Action W - NRC agreed to resolution path *en principle" and we need to I issue documere & SSAR revision, 2 prepare for Me h NRC meetingby proving list of Col. applicant respnnsiblity (l 378.1381,1333. I 384?), and 3. revise SSAR sectson. kfecting of 3 8 95 Action W Dran Col. Action hem Traming program developmere is the respormNisty of the COL applicant Creation of this COL item ml! close all I S DSER items ilt 10 LI thru 3-15)that et addresses Consider custing words at chapter 13 SSAR and DSER. Action item should be in chageer 13 and cross referenced from charter I R Tuo new MEETING Opm items were created. both Action W; refer to ease item numbre 2061 and 2062 . _. _ _. _ _ _.Dran SS AR reusion for sectum IR 9 9 sent to the NRC IlllF H Clouste will occur when formal revision 4 is delivered Actum N NRC to reucu mmkup scoion J prmide fee &ack Adeon W - see NRC response sere 1I 2195 Closed. The traming program desch._e is mairessed in revised SSAR Chareers 13 and 18 sulmutted in Rev. 9,7/3196__ _ _...- - - - = - :--._=------__. _ _ _ _ .z_. I Page: 65 Total Records: 134

se AP600 Open Item Tracking System Database: Project Management Report Dat2: 11/21/96 Selection: INRC Branch] like WRR/lIIIFTr Sorted by NRC Branch Description lievn DSER Section/ NRC klemo (W) NRC No. Branch Questson Type, Stahse Detail Imt klod Date Status Steaua tittar No 1 Date 1380 NRRAllIFB 18103-3 D5ERil 7/2696 Closed R ealved p% Westmghouse should deurthe how infortnataan froen other sources is incorporuted into the trasnaig learvung aaj reives. W -j should dancribe how the trierung development pmcess will allow a detemunation to be inade of whether leanung ohjectives will be dueived imm the final safety analysis report, system description manuals and operstmg procedures, faciley liceme and hcerne amenwbnents, licanace evens reports, and ether damneras idmetted by the staff as being important to traming Per 2/1695 conference call twtween Jim 11nngarva, John Ollara & Kerch. Easter. Roth. Alumaw: Action W - NRC agreed to resolution path "m pnnciple" and me need to I issue docurnent & SS AR revisiove, 2. prepare for klarth NRC nweting by proving list of Col, apphcant revnnsibiliev (137R, IlR1. I 383 IIR4?), and 3 resise SSAR sectious kleeting of 3 3 95-Action W Draft C01, Action Itern. Trmining program rbelopment is the responsihihty of the COL applicant. Creation of this COL item mil close all 15 DSER stems (I* 10 3-1 thru 315) that it addresses Cornider esistmg words in chareer 13 SSAR armt DSER. Action item should be in chapter 13 and cross referenced from chapter i8 Ywe new kl,EETING,Open items were created, both Action W, refer to emme item number 206I and 2062 .... _... _ Draft SSAR reusion far section I R 9 9 sent to the NRC ll!!! H Closure will occur when farmal revision 4 is delivered. Action N NRC to res tw markup sedeon and proude fec&ack Acton W - see NRC sesponse sent Ili2195 Closed _De ers.neg program desclopment is addressed in resised SS AR Gasers 13 and 18 submitted in Rev. 9,7/3I/96 i i I Page: 66 Total Records: 13d L

_-.~ AP600 Open item Tracking System Datatoe: Prcject Management Report Date: 11/21/96 Selecties [NRC Dranch] like NRRA DIFir Sorted by NRC Branch e Descriptwn item DSER SM NRC Memo (W) NRC No. Dramh Questaat Type Status Detail Onst Med Date Status Status I.aear No. I Date 1331 NRR/lillFB 18.10.3-9 D$EJtoi yesw closed Resolved [ f6 Westmshouse should desenhe details for traming presentatmn techruques Westmghouse should d-cribe how learnes objectsves will be conveyed to the trainee, and how the other itens of this cencrion are addressed Per 2/16/95 cmiference call between hm 11ongarra, John 011 ara & Kerch Easter, Rosit Mumsw-Action W - NRC agreed to re=olution path *in pnnciple" and we need to I issue documere & SSAR revisiori, 1. pepare for March NRC rneetmg by proving list of COL applicant responsihihty (I 378,133I, i18),1384h, and 3. revise SSAR section Meeting ef 3 '8 95 Action W: Draft COI. Action item Tramma popam development is the revonsihhty of the COL applicant. Creation of this COL item will clone all 15 DSER stems (I210 3-1 tiu u 3-15) that d adeesses Consider existmg wwds m chapter 13 SSAR and DSER. Action item should be in chapter 13 and cross referenced from chagter it Two new MELTING t pen items were created twe Action W?efer to ease item number 2061 and 2062 } ~ Draft SSAR resisson Int testhus i R 9 9 sent to t5 NE fillFR Closure udt occur uhen formal revision 4 is delivered Action N NRC to review mariup settson and preside fecAlt Action W - see NRC respamse sent iI 2195 Closed - The traming propam developrnent is addressed in revised SSAR Chagters I 3 and it submstted in Rev. 9,7/31/96 1382 NRR/IlllFD 1810310 DSER -OI 7N% (M Resolved / Westmghouw should desaihe eraimng reEr7es Westmghouse should discuss how the various facihties and resources needed to satisfy traming desig requirements will be identified Per 2'1695 conference call hetueen hm Hongarra, John O'llara & Kercli, Easter, Roth, Mumsw: Action W ~ NRC speed to resolution path "m pnnciple" and we need to I assue dosvment & SSAR revision, 2. prepare for March NRC meetingby promg list of COI. appl. cant responsihditv (1172, I 3RI, I 383. I 384?), and 3 revise SSAR sectinet Meetmgof 3/295: Action W: Draft COL Actmn item Traimng propam devehyment is the responsib lity of the COL applicant Creation of tius COL stem will close all 15 DSER items (1810 3-1 thru 315)that it addresses Consider existmg words in chapter 13 SSAR and DSER. Action item should be in chapter 13 and cross referenced from chapter 18 Two new MEETING Open Items were created, Imth Action W; refer to dbase item number 2M I and 2062 ~ Draft SSAR revision for sestion it 9 9 sess to the NRC lillFB Closure wdl occur when formal revision 4 is delivered Action N NRC to review markup section and provide fee &ack. Action W. see NRC respnnse sent iI/21/95 Closed - The trainingpry development is addressed in revised SSAR Chapters I3 and iB subnutted in Rev. 9,7/31196, Page: 67 Total Records: 134

a AP600 Open Item Tracking System Datab:se: Praject Management Report Date: 11/21/96 Selecties: [NRC Branch] like NRR/IH ETT Sorted by NRC Branch e Dacryion item DSER Sectionf NRC Memo (W) NRC No. Brands Quatam Type Status Detail tme Mod Date Status Stains tamar No. / Daar 1323 NRR/llllFB 18 10.3-11 DSERol FM% Clamad Ramalved/ g4 Westinghouse should desmhe how irnsung is evaluated Westmghouse should define the pran=== by wiiide to h4y samhnds for evaluassig trainee mastery of trianmg clies1ives, as well as overall trainee policiency in adetson, Westeghouse should specify how evalustson crutaria will be denned Per 2/16.95 confaence call between Jun IWgarra. John 011 ara & Kerth, Easter, Roth. Mumsw-Action W - NRC agreed to resolution path "in principle" and we need to I. issue docurners & SSAR revision, 2 prepare for March NRC meetang by proving test of COL apphcant responsihihty (1372.138I,1383, I 3947), and 3 revise $$AR sectices Meeting of) 895-Action W: Dran COL Action item Traming program development is the responsit=hty of die COL applicant Creation of thia COI item will close all 15 DSER items (It 10 31 thru 315)that et addresses Consider exssimg words in chapter 13 SSAR and DSER. Action stan should be in chapter I 3 and cross referenced from thaper iE Two new MFETING Open items were created. both Action W; refer to ease item number 206l and 2062. Dran SSdreEdm fEr'sest[on ti N serEtIthe NRC lillfil Closure will occur Ehen formal revision 4 is del vered l ^ i Action N NRC to resnew markup sesteon and ponde feedback. I i Action W - see NRC respome sent II 2195 L _... Closed. The trainmg program deschenent is addressed in resised SSAR Chapen 13 and I B sulmutted in Rev. 9. 7'3146 i 1384 NRR1tilFB 12 l0 3-12 DSFR ol [ F r%% Closed Resolved Westinghouse should dncuss s mfication of the adequaq of traming materials Westinghouse should provide additional information on the methods that p will be used to ser fs the accuracy and completeness of trmining course matmals s Per 2'l695 conference call between Jim thgarra, John O'llara & Kerch, Easter, Roth, Mumaw: F Action W - NRC agreed to resolution path "m pnnenple" and we need to I issue document & SSAR revisiert. 2. prepare for March NRC meeting by prosing hst of COL applecans responsihihty (1378. I18I, i131. I 3244 and 3. revise SSAR secti Meetingof 3.t95 i Action W. DraA COL Action Item Trainmg pogram dewhyvnene is the responsshihty of the COL applicard. Creation of thW t.0L item wdl close all 15 DSER items (It 10 31 thru 3-15)that at addresses Consider existmg words in chagter 13 SSAR and DSER. Action item should he in chapte cyms referenced from chape,r 13. Two new MEETING Open Items were created, both Action W; refer to ease itern =W 2061 and 2062. i Draft SSAR rension for sestion 13 9 9 sers to the NRC lillFB. Closire will occur when formal revision 4 is delivered Action N NRC to review markup section and provide feedbact Action W see NRC response sent i1/28.95 Closed. The train}m program development is adeissed in revised SSAR Chapsers 13 and IB aubnused in Rev. 9. 7/31/96 Page: 68 Total Recordr 13d ~ i

o AP600 Opese Iteen Tracking System Database: Preject Managesment Report Date: 11/21/96 Selecties [NRC Branch) like NRR/IDIFB' Sorted by NRC Branch Description item DSER Section/ NRC Mano (W) NRC No. Branch (W Type Status Detail Imt Mod Date Stasma Stanse immer Ne / Dane 1385 NRR/HHill 18 10 3-14 DSERCI 7/26/96 Clamed Ramalved [ gg Westinghouse should discuss tww the traming propani will be eyeaad Westanghouse steamld describe how thr identified trasung preyern '. _ managanne ,. systans will be used to refer and update the consent and ctwuhscs of trasung, Per 2/1695 mnference call twtween Jim Bengarra, John 011ers & Kerch. Easter. Roth. Murnsw: Action W - NRC apeed to resolution path "an pnnciple" and we need to l. issue document A SSAR reviseen. 2 prepare for March NRC meeting by i swodng lest of COL apphcant respnnsibility (1378,1381. I 32) 1384?), and 3. rense SSAR sectiert Meeting of 3 't 95 Action W: Draft COI. Action item Trmaneg propern development is the resporsibility of the COL applicant Creation of this COL inne will close all 15 DSER stems (I210 31 thru 315) that et addresses Consider existeg words in chapter 13 SSAR and DSER. Action itern should be in charser 13 and cross referenced from chapter it Two new MEETING Open items were evented twah Action W; sefer to ease item number 206 e and 2062. DemR SSAR resisico fbr sedeon Ie 9 9 sent to the NRC lillFB Closure will occur when formal revisien 4 as deliwred ~ j Action N NRC to redeu markup sedmn and prende feedak. Action W - see NRC respome sent iI 2195 Clourd. W training propam development is addressed in revised SSAR Chapters 13 and It subrnseed in Rev. 9. 7/3 I/96 1386 NRRMillFB 1810315 DsE R of 7 :W Closed Resolved Westinghouse should describe traming source matmals. Westeghouse should desmhe how the trauung prograrn is L, _ the requirannes and fk guidance of 10 CFR 50120. "Traming and Quahrecation of Nuclear Power Plant Personnel"; 10 CFR Part 55.* Operators Locames," and ANSL'ANS 3 l-1988. "Selectiort Qualfication, and Trammg of Perwnnel for Nuclear Power Plants

• Per 2/1695 conference catl between Jim ihmgarra. John O'llara & Kerdi. Easter. Roth Mumaw:

i-Action W - NRC speed to resolution path "in pnnciple" and we need to I. essue documed A SSAR revisiert 2. prepare for March NRC meeting bv prodng list of COI. appl cant respons.hility (137t,1381.138), t 184?), and 3. rense SSAR section j Mee*ing of 3 895: Action W: Draft Col. Action item Trmining program developenent is the responsibilrry of the cot. applicant Creation of this COI. itan will close att I 5 DSER items (t 810 3 1 thru 315) that it addresses Consider existing wwds in chapter 13 SSAR and DSER. Action item should be in chapte _ crass referenced from chapter 18 Two new MEETING Open items were created. twdh Action W; refer to Anne item member 2061 and 2062 L Draft SSAR revision for section 18 9 9 sent to the NRC filf FB Closure wdl occur when formal revissan 4 is deliW ~ " ' ' i l l Action N NRC to review markup section and provide fee &ack. Action W - see NRC respanne sent 11/21/95 Clemed. & M propam develapanent is addressed in revised SSAR , ^.13 and 18 subnuund in Rev. 9. 7/31,96. Page: 69 Total Records 134 1 i

,e AP600 Open Item Tracking System Datlase: Preject Management Report Date: 11/21/96 Selettles: [NRC Branch] like NRR/IDIFir Sorted by NRC Branch e Denmption item DSER Section/ NRC Memo (W) NRC No. Bra d Questaan Type Status Detail lass Mad Date Status Staten tener No. I Dane 13s7 NRJt/IIHFB 18 II.3 l.1 D5EROI fr s% Clamed .Dema6ml z ,p g {Q Westingimuse should clanry the general VAV scope regardag the TSC. Westinghouse should clanfy the rete of the 13C sa Evaluaten f-16 and 17. Per 2/16M5 crmference call hetween Jun Ihmgarra, John 011 era & Kerch Easter. Roth, Murnaw: f Action W - NRC apeed to resolutmn path "in principle" and we need to issue documern & SSAR revision to e e o p I Resolved Y p 4'l3'95 - Fas of the " Programmatic I esel Description of the AP600 Iluman factors vmfecation and Validatim Plan

• was sent to J Ikugarra and i

w J 01tara A maggung of each element 10 open item to its regnese'amwer was also provided Action N: Review the document and determine whether the element 10 open nems 12 Il*s are adequatels addressed. Resolved 5s 17 phoncnn with Jim lhmgarra. Jun corsiders all the element 10 VA V open items resolved Need to suhmit the read I t 8 2 3 o(chapter I 8 of the SSAR as part of the fiwmal SS AR reusson Closed. He iluman Factors Verificati. n and Validation i sddressed en resised SSAR Section it I t, submeted in Rev. 9. 7/115 96. _--.:--:..=-===: = = = =~-----_: .==- 1388 NRilltflFD 15 iI 312 D5FR 01 73% C3 aged M gg,Q g \\O Weamghouse should descnhe Ua V aon2cs and sequences Westinghouse should clanfy (a)the role of tmanen factm issue resolution, IISI tan serification, and final plant IIIT !!$1 design senfication in the VAV astisities, and (b) the sequence of VAV actiuties. Per 2/1635 conference call between Jun ihmgarra, John 011 ara & Kercit Faster, Roth, Mumaw-i S [ g Action W NRC acced to resolutwn path "in pnnciple" and we need to issue docurnent A SSAR revision. t 4/13 95 - Fax of the "Propammatic I ss el pescriptinn of the AP600 lluman Factors Venfication and Validation Plan" was sent to J Bongarra and 3 Ollara A mappmg of each element 10 open item to its resgmnse/ answer was provided Action N: Review the document and determine whether the element 10 cpen items 18 Il's are adequatel addressed 3 i Resolved 517 phoncon wah Jim ihmgana. Jun considers all the element t o VA V open items resolved Need to submit the revised i3 3 2 i of the SSAR as part of the formal SSAR revismn

• ]#".'#*

L b Page-70 Total Recordr I34

i e i AP600 Open item Tracking System Database: Prcject Management Report Date: 11/21/96 i Selection: [NRC Branch] like 'NRR/lD WB' Sorted by NRC Branch Desmgwion item DSER W NRC Memo (W) NRC No Ikandt Qisestion Type Stasus Detail Ime Mod Dese staans Staans tamar No. / Dee 1389 NRR/IIHFB IS.ll.3 l.3 DSERol 7r26/M Closed W- '. should deambe the VAV technical methodology source mammals. W. ^ f deando demeribe die guedmace documentsanon need to d, P develop the VAV propant [ Per 2/16.95 conference call hetween hm ibngarra Jolm 011 ara & Kerch. Imter Roth Mumaw: 4.s h Action W - NRC speed to resolution path _m principle" and we need to issue docunwn A SSAR revision Q Resel ed ~ 4'l 3 *3 - Fas of the "Propammatic inel Desmgtion of the AP600 Iluman Factors Veri 6 cation and Validasion Plan" was seva to J Ebngarra and 1(Filara A r'imppmg of eac h element 10 open nern to as respawuc! answer was provided Action N. Review the document and determine winether the elenwne to open items It i t's are adequately adhessed f Resched Se17 pfwncon uith Jim ibngana, hm rensiders all the element 10 VA V open items resolved Need to submrt the revised I8 8 2 3 of chagner IE of the SSAR as pm,1 of the r.wmal SSAR rension Closed - The ilu. man Facto.rs. Ve_n_f.k_a. tion an. d_V.a. 67 _io_n.is a_d.d_r.e_ssed in rensed SSAR Sation i B i 1. subn 1st 1390 NRRittlFD 1811321 DSFR Of 7 26 % Closed 7y OW Westmghouse should deseLp an implemevaation plan for IISI task support senikation The '_--, * - - " son plan should desmhe how all aspetts of the 18S1 requered to accomphsh the human tasks and actions demanded by the AP600 design wift he veri 6ed Weinsnghouse should desenhe how the VA V methodologs will senfv that the llSI does not include informatiort displavs. controls, etc, that do not support operator tasks Per 21695 conference call hetween Am ibngana. John 011 ara & Ecech. Easter. Roth. Mumsw: M d Atison _W - NRC agreed to rest lution path *in principle" and ue need to issue document & SSAR sevision d 4'l 3 95 - Fas of the "Propammatec f eel Descnption of the AP600 lluman factors Ven6 cation and Validation Plan" was sent to J fkngarra anJ I J (Yllara A mappmg of each element to open item to as respome answer was prmided Action N-Review the document and determme whether the elemeva 10 open items it II's are adequatelv addreued i Resolved 5'l7 phoncon unh Jim Ekngana, han considevi all the element 10 VAV open items resolved Need to submit the resised i 8 8 23 of chareer i t of the SSAR as part of the formal SSAR revision Closed - The lluman Fa.ctors Ven6 cat. ion and Validation is addressed in revised SS AR Sation I B I 1. subnutted in Rev. 9. 7/3146 _-=:----

==. _ _ _ - - _ _ i i P Page. 71 Total Records: 134 i o s.

AP600 Open Item Tracking System Database: Prsject Management Report Date: 11/21/96 Selattes [NRC Branch] hke NRRA DIHr Sorted by NRC Branch r Descrytion term DSER Sectunut NRC Memo (W) NRC No. Branch Questeen Type Staeus Detail tml Mod Dese Staans !hanaa tmar No. / Date 1391 NRR/HHFB 1831.33-1 DSERot tm cga,g ,p pg6 Westeghnuse should desmbe llFE design venficatiert methnds. W - -f - : should conumit to drwiepus a - " " ' s l' r HFE design vedicamen o and selsted criteria, taking into consideration the concems identifwd in the staffs evaluation of tinis eneanon W - f - M dancree itsw W-idmtified in the critmon will be addremed in the VAV methndology. Per 2/1695 conference call hetween Jan Ikmgarra. John :Yllare A Kerch. F4sier. Roth Mumsw' _ Action W - NRC agreed to resolution path % pnnciple" and we nm! to issue donuncre A SSAR rensson Reselsed +13 95 - l'as of the " Programmatic Isvel DesengWion of the AP600 Ilumen Iactors Vmfication and Validation Plan" was seve to J Bengarra and J 011 ara A maming of each element 10 open item to its respame' answer was prmided Action N: Review the docummt and deterune whether the elemens to open etenu la Il s are adequatch addressed Resolsed 517 ph< won usth Jun Ekmgana. Jim considers all the elemens 10 VA V open items resolved Need to sulunit the rensed i E t 2 3 of chageer I R of tir SSAR as pan of the formal SSAR raisim [I sed - De !!uman I adors Vmficatum,and Validation is mairesp res ised SSAR Section 1811. subnused in Rev. 9. 7131% L Page: 72 Total Recads: 13d

f A?tiOO Open Item Tracking System Database: Prsject Management Report Date: 11/21/96 Sesectt.:.: [NRC Branch) like 'NRR/ID GTr Sorted by NRC Branch ? Description item DSER Sectsan/ NRC Memo (W) NRC No. Brasech Quessemi _ 's;pe Status Detail lass Mod Date 9 sham Staeum Lasaur No. / Dese 1392 NRR,113fFB 1813.34-1 LSERot 17696 Clemed ved f, @p Westinghouse should conenst to developing a. c" ' 's ibe integrated system validatsosi and relmaad crienrim. W _^ " '

• g will address die seasald describe ese tools en he used in evahsating dynamic task perfonnance in the VAV enethodology. Westinghouse shonald demaibe Inow see VAV.

obsectiven hated as part of this cntenon. Weining)wmase should desenhe how the gewing ofcritualInsmsus actions will be addremand m the VAV methodology Westinghouse should desmhe how the VAV methodology will address the casesones edesclead in Appendix A to RG I.33 regarding prombare related activities Westinghouse shoulJ drscnbe how the VA V methodology will evaluate performance under a range of operatsanal condetsons and upA and provide additional infosmatum about the Evaluation 17 test scenanos Westmahouse should describe how the validation scenarios wi!I he )p made realistic as part of the VAV enethodology. I"-=t.nghouse should descnhe how the VAV enethodology will address perforrrance measures to test the g achievement of all objectnes desipi goals, and perfe:mance requirements Per 2'l6 95 cniference call hetween Jem Hongarra, John O'llara A Kerch. Easter. Roth. Mumaw: Action W - NRC speed to resolutum path -in pnnciple" and ue need to issue dement & SS AR revssion i Action N - N RC to gwoside danfkation on uluch procedures per RG I 31 should he covered by VAV. klecting oO 10 95 Clanfmation provided (in untmg) hv NRC to Westinghouse (tanalse) Dnef discussion followed Wesunghouse to issue SSAR revision and document _ [ Resolsed 4/I 3.95 - Fai of the pregammatic Inct Description of the Al%4 llamar. 5%ctors Venfication and Validation Plan' was sent to J Bongarra and J O'llara A mappeg of each element t o open item to its resp.mse'areue was :-nided Action N: Review the date and determine whether the element 10 open stems IR Il's are adequatelv addressed Reselsed 5:17 phoncon v n,enn ihmgarra. Jan considers all the element 10 VA V open items resolved Need to submit the revised it 8 2 3 of chapter I E of the SSAR as part of the formal SSAR resision Clowd - The iluman Factors Veri.fkaison and Vahdation is ad&essed in revised SSAR Sation 1811. submsued in Rev. 9. 7/3146 -i -= -._ = --- :- = -- _ - - - - - - - v i b Pagr 73 Total Records: I34

AP600 Open Item Tracking System Database: Prcject Management Report Date: 11/21/96 Selection: [NRC Branch] like NRRAIIETr Sorted by NRC Branch r Descrilenwi Item DSER SM NRC Memo (W) NRC No Ikarna Quesem Type Stanas Detail Emt Mod Date sessus w a= Laser No. I Dese 1393 NRR/lilIFB 18.11.3.5-8 D$ERol ?fww closed

"M pp Westmefumane should develap an issue resolution vmfication methodology. W '-f should cwmemit to developmg a - * * ' a for lammen factors resue moluta vmfication and related cnteria Westinghouse shnutd dencnhe how the VAV methodology will addrama inaues that cannot be resolved emutil a plant is inult, and how such issues will he incorporated una the process for Gnal plant flFFAISI design vm6 cation I)tP q

Per 2.16S$ conference call hetween Jim Bangarra, John Ullara A Kenh, Fmter, Roth, Mumsw: ^""" # NRC agreed to resolution path "a gmnciple" and we need to issue document A SSAR revisiert 1 Resolved 4'I395 - Fas of the 'Programenatic I evel ikscnprion of the AP600 liuman Feaors Vmfication and Vahdation Plan" was mese to J Bangarra and J Ullara A marpmg of each elemerd 10 open dem to its response answer was prowled Action N' Review the documers and determme whether the element to open dems it II's are adequatets addressed Resolsed 517 phoncon with Juo ihmgarra. Jim considers all the element 10 VA V open acms resolved Need to submit the revised I t 8 2 3 of chapter I t of the SSAR as part af the fonnel SSAR resisinn U H_"'-' I*d"" \\ ",'UC*"".and Val datu n is addr_ cued in resised SS \\R Section 13 i I, submitted m Rev. 9,71i 96. 1394 NRR/11HFH 1811.365 DSER ot 7h Closed ved Q Westinghouse should develop a 6nal plant llFF IIst desip venfication methodology. Westinghouse shnuld cenunit to developmg a methodology for fmal [ plant ilFElllSI desip vm6 cation and related entma Westmahouse should descnbe how the VAV methodology will addrusa aspects of the design that cannot be addressed m desip process VA V, and how thes will be addressed as part of the real plare HFFAlst desip vertication Westinghouse should 1 l descnbe how the VA V methodologv will address confinnance of the infars HFF to the design that resulted from the !!FE design process and VAV annities Per 2'1695 conference call between Jim Dongarra. John Ullara & Kenit f aster, Roth. Mumsw-Action W - NRC agreed to resolution path "m pnnaple" and we need to issue document A SSAR revision Resolwd 4/1395 - Fax of the "Programrnatic level Desmptum of the AP600 Human Factors Venrecation and Validation Plan

• was sers to J thmgarra and 3 Ullara A mappeg of each element 10 open item to its response / answer was provided Actior ' Review the document and determme whether the elemere 10 open items It i t's are adequatelv addressed Resolved 5/17 phorwon with Jun ihmgarra. Jmi considers all the element 10 VAV open items resolved Need to suhrnit the resised is R 2 3 of ch of the SSAR as part of the formal SS AR rension DN""_"_ *".{aaynyen6catum and yalidatum is e in rens,d SS AR Section I 8 I I, submitted in Rev. 9,7/3 I/96 Page: 74 Total Records 134 s

a

[ AP600 Open Itene Tracking Systen Database: Project Managesnent Report Date: 11/21/96 Selecties (NRC Branchi like NRR/lDIFIY Sorted by NRC Branch e item DSER Sectionf NRC Memo (W) NRC I No. Brandi Qusehen Type staans Detail ims Mod Dese Stasua semens tamar No. / Dane I)93 NRR/HHFB 13 12.3-1 DSERG t'2p6 Ramolved A Westeghouse should sulavue an accepteNe --' mvansory a(nd ; controls, display. and alarnas for tramaanse -mage=== WP j should drambe how the task analysis will denne a mammum avversaryo(alarna. & splays, and canar als necessary to Pericam crew taska. WeaW should densnhe the technical basis for the ~ servenutary. W ^ f _ should describe how an 1 - ^ will be idredaned of ft-d,

controls, i

esplays, and alarms necessary to pmnd encostion of slue operasar teska to place and maastaan the plarit ist a safessinsadowei==E==mt W^ J should desenhe how ad&tional detailed charadmatics of three enntrols, desplays, and alarms (e g ranges, scales, physical denenamorn, and adual Mormation prnentation) will he idereified, drfmed, and inylemented g Per 2/1695 conference call between Jim Hongarra. John 011ers & Kercis Easter. Redh. Murnsw-f Westinghouse to include thn on the March meeteg agenda I Action N - Ghe Westmghtee iceead on our proposed resolution (proposed during 2'2 95 enecting in Rockville) r 1195 meeting NRC requeced Westinghouse consider t%=t the detailed Int remam compicicly in Tier 2 Tier I would include the process to s. tut the feel avventors ACTION W. If the insentors he is ponded en chapter 7.then make the crons reference serong from chapter 18 Also, the lame should include the process s cntena that uns used to generare the list Westmghouse pasanon as that this hst is an expansion of the RG I 97 aitieria and phihwophy to adsbess centrols and displap should a Tice I hst he requaed we will pursue use of maims pesented at the Feb 2 meeting wnus the NRC criteria used on evolutionars plants Also prepare a draft Tier I hst Need to take a stab at Mening acceptable ITAAC and supporting SSAR informat.on as to how the final invian<wv will he defmed (Use PRA. FOPS. ERGS. FRTA) Caution from A Sterdis - There mil he a strong push to he specMe in defming these desigriITAAC. r ACTION N" NRC staff to prepare a position paper for NRC senior ::.:=;e...,..:. pgosing Tier I include the rocess / critiaia. Goal is to pro &xe the para to sampor{the_n,eyglyd_,,,em_(,.,, g, 7imenmg of Arni 4 l S 2/295 Presesdation of above made in Rodville. NRC staff to discuss and provide fee &al 2995-Discussed during NRC'Westeghouse senior n.-..; meeting as one of the top 50 open items. Action N - to provide feeenck on Weemghouse poposal for resolution 2/2745 Conference call with NRC (J Rongarra. "3 Gallette. J Ollara. J Easta. Aster &s A S ICerch)

1. Agreed to following defeition of" fixed possionN unique locatson in the control roorrvcontrol panel for alarms, esplap. controls where present information from the

aiversary. ceremucusly available not consinnusly esplayed 4 runt have to he class I E; alwan displayed at the same location; dedicased location where the operstor can retneve information that is part of the uninm um eventory. 2 Scope of min. inv. - failed to reach a matinal ", c-this. NRC iseacd that saye includes those controls and in& cations needed to execute the ERG high level operator actions including nosnafety syssem actions; Asagrad on this 3 Use of FBTA A ERG development task analpis I t. C list 4 when completed where does this go tier I or tia 27 Agreed te discuss at 3/8 meeting 11195 nieeting NRC requessed Westinghouse consider that the detailed list remain compleiety in Tier 2. Tia I wonld inchsde the process to se i final inventory ACTION W. If the inventory list is provided in chapeer 7. then snake the cross reference serong freni dispear I S Also, the list sh mLInde the pncess / Cntma that was used to genernae the list WJ [ . Position is that this list is an espansion ofthe RG l.97 cntsma and phalcaryhy to address controls and displays. Should a Tier I hee he sequired we will pursue use oferitieria puseased at the Feb 2 rneetang vers cnteria maad on evohstionary plares. Also prepare a dreA Tia i list. Need to take a stab at defining ITAAC and asyportsng $S AR informat.on as to how the feat invensory will be dermed (Une FRA EOPs. E RGs. FBTA) i NRC staff prepared a poestion paper for NRC annier management, proposang Tier I inchsde the process /erisierm Omelis to e * - the pape Page: 75 Total Records-134

o. AP600 Open Item Tracking System Database: Prrject Management Report Date: 11/21/96 Selectica: [NRC Branch] like NRR/IDIN Sotted by NRC Branch w Desairtinn item DSER Sect"" NRC Meene (W) NRC No. Branch Questsen Tne Status Detail Imt Med Date Status Status tener No. / Dune the nett scheduled Semor.. ......c meetag of April 4. 4/19,95 - Fan sent to J Nnga ra and O Onlletti of NRC that provided a prefirnmary (draft) decreyesen ofhow die seemi invemmary last was develayed and where in the tier 2 (SS AR) ducsunent it was found A deemptum of how the - ~ uiwseory would he seiscoed b die total % list (die crissein + to be used) was also podded This would be placed in the Tice I document A very prelimenary dreA of a mensemann suvweary list, using this crinaria, was prodded for the NRC's mformation and use as backup to thew posdron paper. The NRC (G Onlletti) has suluvutted the poestson papre for NRC ,....; resicw NRC to Detmnine whethre the positum paper is acceptable and the poposed Westinghouse appranch is acceptable Actum W - see NRC respnnse sent 2'2195 Resched - The mnimum inventarv es addressed in revised SSAR Sestum 1212, submitted in stew 9,7/3 I/96 An ITAAC will be prqared which wilt _"8'.the list o@mumayn onyent<wp,, _ 1396 NRR,1tilFB 181331 DsFR ot ' s[t[ f, ~~ Actaar W Action W Westeghouse should deIciop the ITAdUAC for certam elements of the lil E PRkt in each of the following areas, Westungh-sse should prma ITAAC DAC addre sing a........ so compl-te the implementation plan and prmvie the results to the staN for review:

• Element 3 - Functumat Requucrnents Anaf>us Allocatinn t./
• flement 4 - Task Anahsis g
• Element 3 - Starting i
• Element 6 - fluman Reliabildy Analnis
• Elemeve 7 -Ifuman.Spem Interfan.e Des;gn
• Flemene 3 - Procedure Ikvelopment
• Element 9 - Training Program Devetormere i

Westinghouse should also povide ITAAC/DAC addressing a VAV costunutment to (a) develop a detailed '_T plan, ard (b) complete the unplementationf an and provide the resuhs to the staff for review ITAAC identifung the mmimum inventory must also be developed l "") eth tiw 'N_RC lillFH our approath to ITAA~CS' Tier i duument for chapeer I t ] scun Page: 76 Total Records-134

AP600 Open Item Tracking System D;tabase: Prrject Management Report Date: 11/21/96 Selecties- [NRC Branch] hke NRR/lDIFB' Sorted by NRC Bnch 9 D NT Ptiet Item DSER Sectson/ NRC Memo (W) NRC No. lirunch Quation Type Status Detad Imst Mod Det, h staeus immer No I Dune 1397 NRR/HIIFB Ig I3 3 2 DSER of eq W Action W Action W[ Westindiouse should provide the specified level of detail fw the DCD, ITAAC, and DAC. Westinghouse should I. Prodde a complete set ofITAACDAC desmhing the (a) desip ( ....c_.... (b) inspections, test, and analyses; and (c) amytance crnma fw Elemmt 3." Functional Requirements Analpis and Allocation"; Element 4," Task Analpas"; Elemere 5.* Staffing *; Element 6 *lluman ReliaNidy [p Analysis

• Element 7.*lluman-System Interace Desip"; Flcmeen R," Procedure Devekyment*, and Elemere 9.*Trauung Program Dm:+.-.;

h\\ 2 Provide a complete set of ITAACT)AC for all VAV actintees. inclueng 1151 taA support vmfications human factors issue resolution vmfication and fenal plant IlfE' Sill design senfcation 3 Resalse the staffs concem regarang the use of life guidelmet for vmfocation 4_,Pronde iT AAC DAC for the minemum en entort (.[ct WestinghoineEiIl d'iscus< ith the RC lif TIT 1 our approach to ITAACS' Tier I duument for chapter I8 ) 1524 NRR/Illifil 20 4-1 IMR ot toin% Closed A*=M. RulW JT[ ,g Westinghnuse ed not address issue I A I 4 m sts hlay 28.1993, letter It should also address the respeewebldy of the COL applicant ut this essue for the _ iW AP600 design D ig (DSER page 20102) As escussed en NUREG 091t, Issue I A. I 4. addressed changes to 10 Cf'R 50.54," Conditions oflicensees. concenung stuft staffing and working hours oflicensed operators The final rule that amended 10 CFR 50 54 %as artwoved on Arnt 28.1933. This issue is resolved and new jgpb requerements were established f lhe staff however, considers this suue not reles ant to the AP600 design because e is an operational issue outside the scope of AP600 design certification The organizatmnal structure of the sne operator es discssed in Section 13 I of this repart_ The COL applicant will he responsible fw addressmg this issue as part of the licemmg process and is Col. Action Item 20 4-I. Westmghouse did not address tins issue in its k1av 2R.1993, letter it concluded,in Table 19 2 of that letter, that this issue uas rwd relasant to the AP603 design because this issue was issued [ ski with no new requirements. Although Westeghouse is entrect as to the design of the plant. the responsehhty of th EI: ap@ cant shouy be,iden_tified The,,_st_a_ rapaces eat We_stinghimse addras this usue fa A M deingn K Closed - There is not a riced to add a dionio~i 9 4 for this issue since (as identified in DSER) this issue is an operatinnat issue outside the scope cwtification The requirement for a COL applicant to meet 10 CFR 50 54 (which was ammended in response to this issue)in enmbu ation wp he Col b"" _ "I N ""*[ Y b __ 1525 NRR/Illifil 20 4-2 D5FR ot 30*% Closed pN p, p p [g(7 g g For Issue I C. I, the staff corniu~5s that the AP600 specific ERGS are needed to satisfy these requimneses Supposting analys 2 fP .s 7

• e 'K"ta'"'e *f *f*'" ac'ian ia mr==e!* 'raa'ien'$ aad act'de'** =ha='d *ha 6' Previded by We='iasha=*e

$f Yp e, - Revision I of the at ;w. Emergency Respose Guideluses was sul= rutted by DCP'NRC0376 on 1995. Normal, ahnermal, maintenance and P

ve plant procedures are the gibihty of the Combened License applicant as indicated in SSAR Section 13 5.

Page: 77 Total Recordr 134

o ' AP600 Open Iten Tracking Systeni Database: Prcject Managentent Report Date: 11/21/96 Selectise (NRC Branch] like NRR/IDIFD* Sorted by NRC Branch e i Desmption liem DSER Secisant NRC Memo (W) NRC No. Ibum:h Qisestian Type Status Detail Last Mod Due Status States tener No. / Date 1526 NRR/HHFB 20 4-3 DsER08 Clamed Action N < For lasue I C.S. Westenshnuw addressed the respuisibilny of the plant demipre; however, the COL applicant will, almag be ;_ _, " far the estHyacine mformation at the COL and operational phases WessirWoouse should adeems this repoembiley as well as the unsthods and mesria for die 1. l>$ .M ol l Closed luue I C 5 has been specifically addressed in the Rev. 7 of Sn.uoi ' 9 4 of the SSAR. The steun is clemed l 1527 NRR.1111FB 20 4-4 DsER E)1 p to'M % Closed Action N / <p Westinghouw did not addreu Issue I C 9 in its klay 28.1993 letter. It should adeess the responsahilsey of the COL applicant un proceeste i... -- p ^ for this inue The methods and miena for the dnelopment, vmfacation and validation _' - A M -- -- -m and revision ofproce& ares should be j addreswd Closed - The COL m2eorn requestednUhis item are addressed da COL action items 13 5 l l and 13 5.2-1. COL actaen iurm 13.51 1 states the COL applicant should onelop and desmhe its seninistrative procedures COL action item 13 5 2-1 staics the COL applicase should develop and describe the 1 operating and maintenance procedures %e DSER Open ne,n 13 51 1 and il 5 21 for reachnion W f. and COL arplacant responsibilaies with respect to methods and critena for the des clopment smfecation and saledation,implementatsost, - " and revision of proceesres are being g a addressed via Open items and COL Action Items in Chapters I3 and iB 1541 NRR3fliFB 20 4-18 DsF R eil I en M % Closed Action N / 'In its bien of Issue il J 3 I in SSAR Section 13 3. We'stmshou'se sh'~uldesplain winnt at uncens lyy *propsuly."" clearly defined " "well " -M o and "appropnate" used in Sect on I 9 3 of the SSAR. and should discuss the QA standards and organization it used fw the AP600 desigst Closed. Issue II J 3 I has beenAI5 ETable 1.9-2. Listmg of1'nresolved Safety issues and Denme Safety issues, and classified as superwded Th Itern is closed 1542 NRR.1tilFB 20 4-19 DSER of .. = ino% Closed Action N s

1. V Ald

• 13 6 (, I 3.C 1 % o0N

[To address issue II J 4 l. Westinhwww~should address the responsiintny of the COL applicant fw proceesre developummt. l Al'.o. kaa.( doe W T M d AA bl M th a at 1Ce6ft k 4

• CImed. The plare puedwes iw~ak7s tely reportmg m accordance with 10 CFR Part 21 and 10 CFR 50 55(c) are outside the scope certificatioet The COL applicant will hase the respormhildy for having the proper reposting proceesres and addressung this issue as part of the licensing

'h ** Na4 ZEJ.T.IesJua) process this is considered a part of the riant peacedures development by the COL applicant. Procedures develgenet by the COL applicars are addressed by COL Action items 13 51 1 and 13 5 2-1 These COL action items are addressed by DSER open itenes 13.5 l l and 13.5 2-I. This DSER open item is closed since ele resposisibildy of the COL appheant for this issu is tracked by two other DSER open itsens. 1557 NRR/HHFB 2051 OsERol trWM% Closed Action N / M For Issue llF41. West.--? w should address the regulatory " guidance and standards

• that it used to write the erriergency operatang proce the AP600 desig,i.

Claard. Issue liF4 I has been n. w: from the Rev. 7 of Section I.9 4 of the SSAR. and included as Table I.9-2 I.istingof Unresolved Safety Issues and i' Genmc Safety lieues, according to what was agreed with the NRC. The item is closed Page: 78 Total Records: I34

2 - AP600 Open Iteni Tracking System Datchase: Project Management Report Date: 11/21/96 Selectica [NRC Branch] like NRR/lDIFIr Sotted by NRC Branch e Dmrytion Item DSER Sectm/ NRC Mano (W) NRC No. Branch Quemason Type Staeus Detail Ima Mod Dane Semans tamar No / Dune 155s NRMfHFB 20 5-2 DsERol torm% Closed Actaan N /

1. p For issue HFS 2. Westinginnuse shnuld idmtsfy and Ascuss the "curvere guidance and requirenesses on innsynasd Imanen facears dumgi" used a densa the advanced alarm system. In addnion, Westangliouse should explain the r-lmtionalup of the -, _ _4 med gnahned display In~==9 systeun

" the, alarm span t (Closed luue llF 5 2 has been revised in Rev. 7 of Section I 9 4 of the SS AR to address these issues and refer to Chapene IS The liesn is closed l 1650 NRRallIFB 1810313 DSERot aUw Closed Resolved - Westmahouse should disness lum the effectiveness of treuung will be demon 7stred Westingliouse sinnuld i%tify the process by utiich apprnpnaec Fq methods will tw developed and uged to es atuate the oserall effectiveness of the training programs Per 2'1695 conference call hetween Jim ibngarra. John 011 ara & Kercit. Easter, Roth. kfumaw-k1mn W - NRC agreed to resolution path *m pnnaple" and we need to I inue documens & SSAR revision, 2. prepare fa kf arch NRC meetsig by pres eng hst of Col. appl cant respnnsih. hts (1372.1381.1381.1384'A and 3 reuse SSAR sectiers._ Resolved l klecting of 3 2 95,k1mn W Dran Col.,htoon item Tramma prograni development is the,., ' ?ity of the COL applicant Creation of tius COL dem udiclose all 15 DST R mems(IE 10 3 I thru 315)that it addresses Consider cuitmg words in chapeer 13 SSAR and DSER Action stem should be en chapter I 3 and cross referenced from chapter i E Two new hlf ETING Open hems were creased, both Action W; refer to ease item number 2061 and 2062 Resolsed than SSAR reusion for se61 nn I8 9 9 uns sent to the NRC lillfil Closure will occur when formal revision 4 is dehvered Flcment 9 With submittal of SSAR Rev 9 ch IR and WCAP-14655 Rev 4, this is closed. - _,. _ _. -. - - - = - = =vm- - - - ~ 1947 NR R/IlllFH 1321 D5FRM 91996 Closed .Ashase W NTD-NRC-95-4464 [2-I-a4T;p 5 The COL appheant should descnbe its personnel training _l + t {losed -The COL inforEArte$o~ incl'ude [onnel trammg of the COL organaation was ad&d to the SSAR. Section i 3 2 t Revision 3) ~] 1950 NRR/It!!FB 13511 DiER mt. 9 19 % Closed M NTD-NRC-95-4464 an nd T b Id ___ cop applyard should deg and dmnhey %strative proce&sres -.-) f i [C_ lased - A COL informatonn nem was a& led to the SSAR, Satmn 1.0, pension 'p addresa a&iunamerutive W=es for th ~ i L i Page: 79 Total Records: 134 i

e AP600 Open Item Tracking System Database: Prsject Management Report Date: 11/21/96 Seintlea [NRC Branch] like NRR/HHFB' Sorted by NRC Brancti r Denmgaion Item DSER SM NRC Memo M N Na Brandi Questum Type Status Detail im Mad Dase Stasua Staasa leaner No. / Daae 1951 NRRillfillt 83.5.2-1 DSER C)t., 9'19 % Clearal h ONIO93M ma M.n

1. I l13 5.2-1 The COL emhcant ufumaid develop and deambe the operstag and -- " -. " prMares l

Closed - A COL informaton stem was aMed to Scoson 13 5 of the $$AR (Revision 3) to adeems the L:+.. ^ ef operstag and ---- - pmcedurn for the pla_r,a _, _____,_. _ _ 1978 NRR!!IIIFR 20 4.I D$FR<0t. IS W% Cloned Action N 7 gJO {20 41 _The CO,L apphcant douhl address shdt staNing and working hours oflicensed operators in Issue I A.I 4 as part of the lansegyrocess. l ~~ Closed -Issue I A I 4 es waludd en fable I 9'-2' listmg of LInresolved Safety ssues and Genme Safety issues, and classdied as resolved withnut aw new "_9""**- _.. 1981 NRR!IlllFB 20 4-4 D3F R <0t. to to % Closed Action N / fp CD( tiJ e MWW 7D [0[_for issue I C 5. the COL apl5 cant simid de[ch the detailed proceeres for the plane.speedic design q 1 O f, D.2 8 'd h 4

• 1 'k l 7 Cloaco - The COL maions regnested with this item are addressed de COL adion stems 13 5. l.1 and 13.5 2 1. COL action item 13 51 1 states the COL I

appheans should on elop and desmbe ets admaustrative pacedures COL nason item 13.5 2-1 states the COL applicara should develop and desmhe the { eperating and maintenance pocedures See DSER Open items 13 5.l l and 13.5 21 for resolutiort 1982 NR R/lilIFB 20 4-5 DSFRUE gryM% Cloned Action N < [

1. I*

l20 4-5 ~h ]ksu'eE 9, the COL appl cant should develop the detailed procedures for the plantWie design y e.

1. /f g/ co m

.Iner-i Closed - The COL addrequested with this item are addressed de COL actum seems 13.5.l-l and 13 5 2-1. COL action item 13 5.I-I s:stes the COL apphcant should dnelop and desmbe its administrstise pacedures COL action item I 3.5.2-3 states the COL applicans should develop and desmbe the operating and ma.ntenance pacedures See DSER Open stems I 3 5.1 1 and 13 5 2-l foe resolution 19a6 NR RMIIIFB 20 4-9 D$ER<0t. . _.. = =. / toWM Cloned Action N g 28 N h. %d Co( t Tt.e 20 4-9 f for issue il J 31. the Col apphcant simuld address the organizatum for the plant, the construction of the plara, and any moddicateons to the (Q(gQ To cJ J 0, pf f C'"'fied design _ _,,,, ~ Cloned - Issue II J 3 I app ars as superseded in Table 19-2. listmg of (Snresolved Safety issues and Genme Safety Issues The Itch can he conside closed Page. 80 Totst Records: 134

o AP6CO Open Item Tracking S> stem Database: Prcject Management Report Data: 11/21/96 Selectlee [NRC Branch] like NRR/lD FIF Sorted by NRC Branch f Description Item DSER Sectm/ NRC Memo (W) NRC No. b ach Question Type Status Detail Imt klad Date States Statua laear No. / Dee 1937 NRR/HHTB 20410 DsFJtM Wm6 Cloemd Action N # pus - 20 4-10 for issue II J 4 4. the COL applicant should ederse plare procedures for -y, reportsag in accordssue with 10 CFR Part 21 and 10 Cfit 1)# 50 55(e) 8 -rAJ a h (oL O C4% h irge.1 wa OL 7.0, tVI A Closed - The COL apphcant will have the responsibehty for having the pr9er reporting pmandamus and C

this issue as part of 9se locussing process This is considered a part of the plare procedures 1-4..

by the COL applicant. Procw&rea development by the COL applicare are adhesned

by COL Action items,1,3 5 l-l and 13 3 21. These COL action items are adeessed by DSER open itenis I).51 1 and 13.5.2-1 N

l933 NRR,HHFB 20 4-11 DsF RCOI. to Cloard Artsout N / h* 20 4-I I 7er issue IIU(26), the COL arphcant should address the scope of exarninations and criteria fa hcensing examinations,, as well as new *i""E9"."."'"'5_I""P""'_.. Claned - Issue II K I (26) appears to superseded in Table 19-2. listmg of Urwesols ed Safety issues and Genmc Safay issues Pie Iteni can be considered closed -=--=-:--2~. 2042 NRRUllFI) IR DNFR olso

3 w, Closed Closed 46 Full Scage Sunulator for CR Design l<eview The staff heheses that a full scope sunularar for the control room desigri seview may be reqused While desmbing die validstami of the inteysted MkIIS in dsspier 13 of the SSAR (l 8 8 2 3 5). Westinghouse has used the term "a near full scnpe, higli Edelity sunulator cornisting of entegrated MMIS components and a high 6dehev, dwinnue simulation of plant behavior". I believe that the term "near full acope" has enade this an issue. This was discusard at a E'"E wnh,_t_h_ey,RC__on,@$_a__s, part of__the_ prnentatww on the AP600 ERG development procent Cies,d klectmg of 3 'S 95. NRC indicated that satisfaction of the PR Al requirements will address the role of the operator. This item will be adressed by closure of the chageer 18 DSFR issues Action N - NRC staKto prepare and issue a policy position paper. This open item is to remain on the top 50 list at least through June Comminion paper issuance. The hope is that the pnhey ident Ged in the June paper will be sufficient to remove this item from the hst Discussed at 2 915 Skikt - Issue to be rede6ned to focus on role of the operator in a passive plant 3/2 95 Status No longer comidered a key licensing issue by staft Resolution of related DSER issues should lead to satisfactory resolution of this matte letter to he sent to W Closed Phoncan of Sel815 with Jim Hongarra Jun has closed this open item based upon the NRC letter of 5/1295. DRC/DCP0189, Docket 8 $2@3 "AP600 Kev Licerning issue-Full Scope Sanulator/ Role of Operator".

t i P Page: 8i Total Records: 134 r r

4 AP600 Open item Tracking System Database: Preject Management Report Date: 11/21/96 b selects.e [NRC Branch] like NRRA D IFB' Sorted by NRC Branch 0 4

• f r

Dmeription Item DSER W NRC unna (W) NRC No Brands h-Twe Stasus Detail tant Mod Date Stamos Stamos teenr No. I Dame 204) NRR/HHIB 18. DSERot30 9e6 Ramalved Actian N NSD-NRC-964805 Ektf W

1. I

47. Casaces of ERGS Weatinginouse. in response to a staff request (= an AP600 ERG submittal, stased thee the kr refarana plasti EROS in h wide a desipi c_

diffences report, identiricatime of high level operasar action surasegpes, and the AP600_, _..: numerwun are maEicient fa demipi cetdkassest The staff does run agree with this Westeghouse posdien because the passive safety system phelosophy &sers. - S, froni curveed plases This was addressed in the August 1994 position paper to Wessinghouse as well as in the draft safety evaluation report (DSER) (DSER quen inams 5 4 7.6-3,15.3.4-3.20 4-2,20 4-21) Westinghouse has indicancJ thee they witt suhms the ERGS by klay 1995. W, 'f ture the staff an February 2 and prearesed and discussed ee,E_Rg des,yl peneng p(ocess _, _ f f p g% c-Red" s f-g, I pst M L DisCesstD Ar 2,95 sEsioR sirNAGEsiENT siEErisG 47. siar a conrrm in.iiechnicei a,arment has been reached end inviemenist.on is g the ontv inue klay be remnved at new enecting Westmghnuse beteeses item 47 is resolwd and waams for saaKfreenck 4-Action W - NRC ayeed to resolution path *in pnnenple" and we need to send the f RGs and backpeund documenes to NRC. These will be sera via a phawd appread unh phase i IRGs to he sent 5 3 8 95, t Status update proudrJ bv phone (D Jadson 8 21) Action W is la samr41e analpwat basis for AE.I. AES-12. AE.2, and supporteg donunentatem or shutdown ERG (ned to uhmst bad yound r informatsoes on S D ! RGs Action N - Renew r atomer. I m pouer shutdown ERGS and bad yound for atfouer and low power ERGS --~ Resalsed - Per DCI' NRC0529 this nem will be closed weh sutunertal of th atpower ERG's. =. =. -. -... - -. - - _ _ - -... 1 i I + f Page: 82 Total Records: I34 i

f. 4 i AP600 Open Itesa Tracking Systems Database: Preject Managensent Report Dau: 11/21196 l Seteettaa- [NRC Branch l hke NRRADIFH' Sorted by NRC Branch i ? Denmption . Item D5ER Secesanf NRC Memo (W) NRC No. Brand W== Type Staeus Detad bst Mod Dane Staass Stamus Imer No. I Due 204d NRR/HHFB 18. D5Motic 30 4 % Remilved .demaer4P" A # 7. A/ t 48 Muunuam Inventory of Coenrols and Displays l Westanslumme has not sulwetted a minwnum mwnsory of controls and employs for the AMoe (See JSER open inom 18.12.3-l) 11ms issue was docused wah the stat at the 2/295 meetag si Rockville A resolution to this apen itain was prapneed and the staff stased that they maah! to discuss it anumig j thenecives IFor clouare, this open aem mas Grit reqisere a completed set of Ap600 ERGS ) See it 12 31 fo_r_fu_rth.er_ status _ _ ~. i 1 Action N To renew rev. 9 of ch it, specifically sedwe I 212 [ t96 SSAR Rev 9, whish included a rension to Ch It, mas subnutted to NRC. Tius inchaded section iB 12 on"manunum inwneorv". L 2?295: presemation of shme made in R Ane, NRC staff to escuss and pmde feedmi. 2195 Discussed dunng NRC,Westmgbe senior - g.,a..: meeting as one of the any 50 open iteens Action N - to ponde feedmt on Westwigpane popmal for resolusson i 1 2/2195 Conference call mah NRC(3 thgarra, G Galletis, J O*Itara, J Easter ASimbs & S Kardi)

1. Agreed to following deGastion of"Gud poanion" - unique location in the control room centrol panel for alarms, dnplap, controls where prearnt informaison from the nunsmum invemory,

} contenuousiv asadahic not contmously desplayed, doesnt have to be class I E, slwep eiplayed at the same location, dadscased locatitui where the operator can retneve informassan that es part of the menwnum inventory. 2 Secpe of men inv - fasted to reach a suunnel " ^ . an thas. NRC stated that I scope usludes those controls and in& cations nmied to esenste the ERG lush level operanar acteases W " ; ', syssam actions, '. - en this [

3. Use of FBTA A ERG deselopment tad analpis I A C lin 4 When emipleted ukre does this go tier I or tier 27 Agreed to docuss at 31 meetmg l'895 meetuig NRC reqisested Westmgpinuse consider that the detailed list remem congdetely in Tier 2. Tier I would include the pacens to select the Gnalinventors ACTION W: If the ins entors he is povided in chapter 7, then make the crees referesace serung team chapter I t. Also, the last should uslude the pacess / crema that was used to generate the hst Westinghouse pmition is that this het is asi egensson of the RG l.97 cename and d

4 I ulosophy to address casarols and dnplap Shnuld a Tier I hst he required we mill pursue une of cntama premesned at the Feb 2 nuveing versus alie NRC creena used on endutionart plants. Also prepare a eaft Tier I his Need to take a stab at defaning acceptable ITAAC and supportug SSAR siformation as to how the Gnal inventory will he de6ned (Use PR A. EOps, ERGS, FRTA) Caution froni A. Sterdus - There will be a serong passh to be specinc in deGning these desippi ITAAC. / I ACTION N NRC staff to prepare a posnian paper for NRC senior management, propos ng Tier I include the process I critieria. Goalis to prodsce the i paper to support she nest scheduled Semor enanagemem meetmg of Apnl 4 { 4/1995 Fan sent to J Ihgarra and G Galletti of NRC that prmided a, - -, (draR) b - of how the total invenaary list was developed and f where in the tier 2 (SSAR)docunnent it was foisnd A descnytion of how the sunnunum inventory woestd be selected fressi the tasal inventary list (the c{ to be used) was also provided 1hes would be peaced in the Tier i docteriana. A very preteninary draft of a nunmemun invesawy 1,4, useg this entma! prmided for the NRC's information and use as hectup to thew position paper The NRC (G Galletti) has subnused the pnsitiosi paper for NRC l 7 enanagemem renew. 5/2/95 Status thscussed dunng March 8 9.1995 meg proposed approach under NRC manageninst review ) Action N. Deternune whether the pnsition paper and Westeghouse approach is arreptable May require a SSAR reviamen to chapeer It Action W - ase NRC response sent s/21/95 L [ a Page: 83 Total Records: I34 [ i i

4 AP600 Open Item Tracking Systen: Dat; base: Prsject Managensent Report Date: 11/21/96 Selecties: [NRC Branch] Itke WRR/ID G'B' Sotted by NRC Branch 1r Desmptimi Item DSER Sectd"l' NRC Memo (W) NRC No Branch Questaan Type Status Detail tast Mod Date Staeus Status Lamar No. / Dune 2061 NRR/HlfFB 18.10 MToot 7 % 96 C1amed Actien N # The Trainmg Program th..:,, .: open nans of diagner I E of the DSER (I810.3-1 tlwangh i S.10.3-15) were encummed wids NRC enring 3295 meetmg h was decided that a COL actum nern would be written stating that tramag proyam a.4. ^ was the., ' 2rry o(die COL _o Once &me dus will close all IS DSFR seems that it adeesses. Ilowever, a new opm nem was apeM upon wisere W ^ -j - : in to commit to povide . inputs to the COL applicare for their consideentum in the developmes of thnr trameng Imyant DraA SSAR renuen for settion iE 9 9 sne to the NRC tilIFB Closure will occur when fwmal rension 4 es dehvered Action N-NRC to renew markup section and prowde fee &ack Actmn W - see NRC response sent 11'21.95 cmference call held wah NRC on 3 '21196 for clanfcation Resolved WCAP.I4655. Designer's input for the Traming of the Ilumen Fadors Enginemng Vmfication and Validation Persarmel. DraA SSAR Sulwtion. W AP600 Trammg Program and DraA Subwo on 13 2. Tramma were suturutted to the NRC as attactwncms to NSD-NRC-96-4722 on 5'l496 ftem will be clowd when Giapter I e of the SS AR is inued Closed - SS AR Sects.e 1810. Trammg tvogram Develonnent. presided m SSAR Rg 7/3 I 96. addresses the trammg progr Aclopmem and d l esigner's input,to_,t_h, in g7,oparn - _ _ _ _ 2062 NRR/HilFB IE 10 MTGOt 73 % Closed Action N / M$ The Training Propam DesclNEhnems of chapter i2 of the DSER (l810 3-1 through It 10 315) mere escussed with NRC &anns 3195 enectmg 1 mas decided that a COL actwn item wwld he uniten statmg that trainmg program 1..:y.-.; maa the vnponsibilery of the COL applicant-Once done this will close all 15 DSF R seems that n addresses flowever a new open dem was agreed upon where Westmghouse is to preside a desmption of the trammg for the life V & V crew Dran SSAR resismn for seawm 18 9 9 sena to the NRC lilIFB Closure will occur ulien formal revisior 4 is delivered Actum N NRC to renew markup sestmn and provide feedback. Actmn W-see NRC response sent !I 2I 95. conference call held urth NRC on 3 2196 for clanfcation. Resolved WCAP-l4635. Designer's input for the Trainmg of the iluman Factors Engmemng Vmt.ation and Vahdation Personnel was submetedla the 3 NRC as an attaciunent to NSD-NRC.96-4722 on 5/1496 Item mitt he closed when Chapter it of th SSAR is issued Closed - SSAR Sectum It 10. Trarrung Prapam Develegnent. prended in SS AR Rev 9. 7/3 I/96, addresacs the tramma pregum 1..:,,.-.; and dengner's input to this program WCAP-I4401 wended the Propammatic level Desmition of the AP600 llumen Factors Vmfication and Valadstum t Plan Page: 84 Total Rmwds: 134 ~

a AP600 Open Item Tracking Systeni Database: Prsject Management Report Date: 11/21/96 Selecties [NRC Branch] hke NRRAIHFB' Sotted by NRC Branch T D=carsson femm DSER Section/ NRC Menio (W) NRC No. Brandi Qaensan Type Staeus Detael Im Mod Date Stasas Staeus tamar No. I Dane 2063 NRR/lfIfFB Ia.3 MToot iW2tm Closed Aceimi N [NTD.NRC 96-4845 d), Westatshauw to conesct operateg expmence review of she human fa: tor aspects of the er d.._: Immed in Appendix B a(NURIG478 I and the 13 NRC exument. Durms the 3/2 meetag, Weningpwnine stated position that the application of shame innace p===& to be asimissere acrase the i i 4/2495 Fai sent to J Bangarra and J O'llara that presents resprese to this open itern Ust of essues nre to be included in our OER hased on rmew of ~ Agy B and the Irl 395 lence against Nt' REG 0933 and section I 9 4 ofour SSAR was sulmutted for NRC review NRC provided feedback (sia coetference catt of 6,1915 ) Action W. Provide draA OER sddressing NRC issues Dran of WCAP.I4645 submnted 515 96 Item will be cimed when NRC correnents are incerpornfed into the final WCAP. Flement 2 Comeneves retiered froen NRC on 2 I 3 To <lme ilus stem. SSAR th! t u as subm tted and we owe a rev to WCAP.I 4645. I Closed with WCAP submenal on 1017 e - rkn 10 25 =_:-.. --~;- 2064 NRR/IlflFR 18 4 hfTG ot 4 a w. Closed Closed h f t:569-A43 Dunng meeting of 5 3 with the NRC, Eedmt)mnisc aded th't clN i(Functional Requirunents Analaysis and Task Allocasion) he reswwed at the ~ ~ ~ g. hp a N ,g p complete element inci instead of the implementation plan in,el as %as done for the DSER C S, i Y g NRC reevaluated element 3 and prouded clarification M Westenghouse needs to respond to the NRC feedhad and clanfication issues sia a functional Requirements Analysis and Allocation report Considered losed per plume call of 2 96 (the elemced 3 DSF R open items suffic eralv cos er the nsues c 2063 NRR/lflitn It s kfTool --- --- -~ ~--------w--- _.:----=:-... 73% cgo,,a w jg M I" As a resuh of our discussiom of element 7 (llSi design) closure paths dunng the meeting of 3'l0 with NRC IlliFB penannel, the need to rniew and resise '_h*!"." }_8..of the SSAR for teme and "realit(* impt,icat, sons mas identified {CompleteEm of ChapTtl't kohd'in R'ev. i ofiSM 7'3I 96. ~~~ =-

=== = = - - - - - ____==---.=} '~ ~~ ~ i L Page: 85 Total Records: 134 l

1 AP600 Open Iteen Tracking Systen Database: Project Managensent Report Date: 11/21/96 Selecties: (NRC Branch] like 'NRR/IDIFIr Sorted by NRC Branch 9 Descrytion i Itan DcER W NRC Memo (W) NRC No. IIrandi Question Twe Stasus Detail be Mod Date Stanna sesses Imaar No. / Dne I 2463 NRR/IIHFB 1841 MTool Imes6 Clamed Rassived [NSD-NRC 96 4831 p3 A descrytion of the *...? ' M* used to done try WEC to arnve at the cwrent AP600 level a( , % Anncemen dedenhen and h t aangrennns already made. Remed upon discussions held &aring the P.Wch natsig, it is our cumse usedsreaanding ens the "W isw to a A degree on operating expmence with predecesaw plants and symems. Time appiscaniest of' &ssary masatards,.-- ' . and pr=e-r (each as m the ALWR t!RD) should be ideveified The descrytson should seek to revise ce clanfy the docuenessed snaamal alrundy reviewed try the maffin the SSAR and RAI resportses Information prouded in &an WCAP taled "AP600 Functmn Requiremeses Analnis and furnetion Allocation" sne by NSD NRC-96-4722 on 5'8496 i This WCAP mill be referenced in a renion to chaser 18 of the SS AR- [ Rensed Chapter it of the AP600 SS AR sulmutted in Revismn 9,7/31196 WCAP.I4444 is refermced in SSAR IB 4. Functaanal Reqaarements Anafpis f and Allocatmn Fonnal WCAP trammertal will be made follommg receipt of NRC commnes Element 3 Comments Reciesed from NRC on S't i I o (Ime this stent 3S AR Chi t uas submitted and me owe a rev to WCAP.I 4644 Closed In refnence to letter NSD NRC.96-4231 dated 9 ( Atober 1996 . -... = = ~.. - - .-.=:.-.-a--:.-, 2466 NRR/IIHFR 18 4-2 MrGot 10 3 % Action N .Asanan.3M. _4Lbb yh A descrytion of the AP600 functuwis, promses and sntems and a comparison to the reference plantWsperms so that one can identify areas of differeur-- that exist To help prodde a scope to the request, it should not he necessarv to deseky a comparison down below the syWan level (unless Westmginnac deems it necessari) The focus on pner spiems as sustied since the successful expmence of predecessor syneems appears to be the pnncipal base for AP600 design actinties in this area Further, one ayect of resoldng cunmns of operator role change is to see how AP600 functaorm. proarsses, and sntems have changed in comparismn to pnar sutems The resswwise should address the stafPs spec 4c concems ident4cd in the evaluation section of DSER Section i 8.4 3.2.cnterion I. The response shoulJ also adens Imm_ the resups of fug1i_ nalyntuenmasts ana,1 us are vmfied and how the resuhs are upeded as the des @ pmcess gwM o L f Information prodded m &an WCAP taled *AP600 Function Requirements Analwis and Function Allocation", subnutted by NSikNRC.96-4722 on 5114 96 This WCAP udl be referenced m a revsion to chapter I t of the SSAR. Revised Chapter it of the AP600 SS AR suhnutted in Revision 9. 7/31196 WCAP-14644 is refemiced a $$AR I8 4. Functional Requirernents An and Allocation Formal WCAP transmittal will he made following receipt of NRC comments Element 3. 1 Conunents Recieved from NRC on S!! 3. To close this item SSAR Ch!8 was subnutted and we owe a rev to WCAP-14644 Even weh sulwnitial of this WCAP, at is the NRC adaan to deternune how to clone this man, related to task d,._, not '- 1--"--- rka 10/196 l l 1 Page-86 Total Records-134 t

4 AP600 Open Item Tracking Systens Database: Preject Management Report Date: 11/21/96 Selecties: [NRC Branch] hke NRR/lDIFir Sorted by NRC Branch f Damrison Itan DSER Sect.oa' NRC Memo (W) NRC No M Qasstasi Twe Staeus Detail lane Mod Date Stasus Stamos I.,ese N o. I Date 2467 NRRallifil 18 4-3 MTaol t'h I W Closed Resolved !NSD4:RC-96-4831

1. j A denmption of the human role in AP600 functe pmcesses and systens (as defined in apai itani is 4-2) dandd be prwded si tansa of penaanal respons hilary and level of automasson Sence il as our.".. - " ; that the tacteucal basis br allocatson was largely based an operatag egensuce (e g, auxrasful allocations were not changed and problemetse allocatieren were changed), a cargenson to the referuence planets /synssens dionald be doctensemed so that differences in allocation can be identifed %here allocarsons have changed, the basis for the change should be Mentified Passive systens should be considered a spenal form of automation because inituation and corarol of these fumtsons often do not require personnel actions This itan addrennes the second aspect of resolving concerns of operstor role change, i e, to detmnene how AP600 fundsons, procm and rystems levels of automation have danged in compenson to pnor sweems A desmption should he pmided as to how the funcional a!!otation process for the AP600 m!! accomodese the need for thorough OffE irput earty in the design process (as dacussed in part 2 - section 2 of enclosure I to NRC element 3 clanfication letter of 5/1595) This is particularly irTortant for alone areas identified above that are %fferene" frorn the predecessor plant systems g-This informaen n will be placed in a WCAP titled "AP600 Fundian Requirements Analysis and Fumtion Allocation. This WC AP will be referenced in a renion to chapter iR of the SSAR Resolsed Informatmn prmeded in draft WCAP titled *AP600 Function Requirements Analysis and Function Allocation *, suhnuned by NSD-NRC 4722 on 5'14 96 This WCAP unit he referenced in a revisaan to chapter Ia of the SSAR.

Resned Chapter 13 of the AP600 SSAR suhrruned in Revision 9,711/96 WCAP l4644 is refermced in SSAR IR 4. Furutional Requirements Analvsis and Allocation Formal WCAP transmettal will be made following receipt of NRC swnments Flanese 3 Commeras Reciesed from NRC on R> 11 To close this unem. SSAR Chlt was sulwmtred and we owe a rev to WCAP.I4644 Closed. In reference to Ictter NS!1NRC-96-4231 dated 9 ( ktober 1996 Page: 87 Total Records-I34

g AP600 Open Iteen Tracking Systeni Database: PrEject Management Report Date: 11/21/96 Selecties. [NRC Branch] like NRRA DUTY Sorted by NRC Branch 7 Dmenrtian tiem DSER SM NRC Mceno (W) NRC l No. Bruncit h-Type Status Detail tast Mod Date Staans Staans I.mmer No. / Dune [ f 2468 NRRalHFB Ie 4 4 MToot savi4% closed Ramalved NSD-NRC-964818 /) A dreenption of how the iraegrated role of the apermeor across att epsems is ennfamed far =-,

• hty (as " si part 2.esceum 2 ofendamust I of NRC letter) If function allocasion was gwrformed by indoidual sperm desigrien, m!! the IAEA process descrthed in the RAI respanass be used at all, and i

dse haw? Will the t?RD processes he esed7 The process should be descnhed by mbch funoteorm are re-allocated in an iterstne manner,in response to developing desipi specif'ics. operating experience and the outcomes efon-gomg analpes and trade studies t ,-n __n This mformation mitt he placed in a WCAp titled "AP600 Function Requirements Analvsis and Function Allocation. This WCAP mil he refaenced in a tenian sa chapter la of the SS,Jt L i Resolsed Information prmided m draft WCAP taled AP6(M Function Requwemmes Analysis and Function Allocation, subnuned by NSD NRC ' 4722 on St14 96 Ths WCAP unti he refnenced in a rrmon to dapter It of the SSAR 1 Flcment 3 i Conwnents Retiesed from NRC on R I1 To chw.e this item. SSAR Chi 8 was sulmuned and we owe a rev to WCAP.I 4644 Closed - la reference to letter NSIFNRC 9648II dated 9 atober I996 1919 NRR.lf HIB 6421 TTl a . r.- to ei % Resolved M NSD-NRC-96-4816 wAM 46M [ ge* b.R,C _staNyequkes addawma]mfamatum on the prmisions fw sanylmg th_e supply _av and the air stored in the tar 6s fw the VES. ) Action W - The capabilits for samphng in the CAS and VFS will be noted a SSAR rension. l { _ Resolved - Resporne prodded in letter NSIANRC-_96-4816. dated atober 10.1996 SS AR subacction 6.4.5.3 will be added

_==._.._--__:-.--==.- = =:--. = _ _ =

1940 NRR/IllfrB 64$ IT L ot R&25% Resolved AsensurW SD-NRC-96-4tS7 A f.E Ihe staff reguests a comnutment for an integrated test that smfies the perfonnance of the installed VES. The staff agrees that sud a test should not be rim-M Closed - A test of the VES for the first plant is included in subsettion 14 2 9 I 6 The resporme for this cuestiori was provided in lettee, NSD-NRC-%-4RS9 dated atober 25.1996. A draA SSAR rension for subsection 3941 NRRilIHFB 644 TTm _- 14 2 9.16 was prodded l =.- tor 2% Acison W Action W[ (The stafIis needs a reference that saw that a 10 c_arbon diossde Imut is acceptable ] [ y [ Action W - Provide an adddional reference to the NRC. ~~~] Page: BR Total Records: 134

O, AP600 Open Item Tracking System Database: Project Management Report Date: 11/21/96 Selectlas- [NRC Branch] like NRRM DIFIr Sorted Ivy NRC Branch Ds.cnytion I Ince DSER Sectirn/ NRC Memo (w) NRC No. Ikama Quesasan Type Stasus Detail tm Med Dnie Stasma h tener No. / Dune 3942 NRR/HHFB 3.9.6 M IW2996 Resolwd AsesseW-NSD-NRC-94859 htf N The samfrdoes run accept the frapsency of pressmusemen tests of die snain contrei ronen as specded un Tame 3.9-17. SECY-95-1995 - the poincy thee tunned & ration tests be condtscted Ainns each reibeleg The currers revision of the SSAR and Todi Specs does sud coderm to 2

y. It has a

/* frequency of every ten years aAcr two successful Lsts. Y Action W - Resetve frapsency issue Resolved - The respnene for this questson was pavided in letter. NSD-NRC-96-4t39 dated October 25.1996. A drmA SSAR emsion for Table 3 9-17 to commst to the staff position was provided = -. _. -...., - I t l 1 1 I Page 89 Total Records: 134 i t}}