ML20149F091
| ML20149F091 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 07/10/1997 |
| From: | Mcintyre B WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Quay T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NSD-NRC-97-5231, NUDOCS 9707220036 | |
| Download: ML20149F091 (173) | |
Text
~,.. ,.
Westinghouse Energy Systems Box 355 Electric Corporation Pittsburgh Pennsylvania 15230-0355 NSD-NRC-97-5231 l DCP/NRC0954 Docket No.: STN-52-003 July 10,1997 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: T. R. QUAY
SUBJECT:
INFORMAL CORRESPONDENCE
Dear Mr. Quay:
Please find enclosed a formal transmittal of correspondence we have previously sent to you informally.
This informal correspondence wa.s sent over the period May 15,1997 through June 5,1997.
Attachment 1 provides the index of the attached material as you have requested.
/
fh Bnan A. McIntyre, Mana Advanced Plant Safety and Licensing jml Attachment Enclosure cc: N. J. Liparuto, Westinghouse (w/o Attachment, Enclosure) 7 M. M. Slosson, NRC (w/o Enclosure) l//
! U l
9707220036 970710 _
PDR ADOCK 05200003 g PDR, ya n.. o cc; Illlllll!IlllllMyllilillll 1
G
- n o Attachment I to Westinghouse Letter DCP/NRC0954 l l
DATE ADDRESSEE DESCRIPTION 1
5/16/97 Bongarral Markup of SSAR section 18.8.3.2. Will be in revision 13. '
Sebrosky 5/15/97 Sebrosky Agenda for 5/20 meeting with contaimnent systeas.
5/16/97 Quay Reminder of items needing isRC acknowledgement.
5/16/97 Sebrosky Suggested preface to WCAP-14690.
5/15/97 liuffman Markup of SSAR section 5.4.7.2.1. Will be in revision 13 unless we hear from you.
5/19/97 Sebrosky Request to be prepared to discuss results from NRC PAR testing at Sandia to 5/20 meeting.
5/20/97 Quay Examples of correspondence that is received by Westinghouse that is not readable. Request to not fold letters, 5/19/97 Sebrosky Advanced copies of RAI responses on WCT CAD.
5/20/97 Sebrosky Information on RAI 440.80. Will be in revision 10 of the PRA. Request for NRC to change status.
5/20/97 Jackson Westinghouse notes from 5/19 fire protection meeting. I 5/19/97 Kenyon Request to set up a meeting on remaining ECGB issues.
5/20/97 Quay List of things we owe NRC.
5/19/97 Sebrosky Request to discuss relationship between CE System 80+, TMI and the AP600 as concerns NRC request to add a tech spec to nonsafety related hydrogen igniter power supply at 5/20 meeting.
5/16/97 Kenyon Markup of SSAR section 11.5.7. Will go in revision 13 unless we hear from you.
5/21/97 Quay Comment that NRC practice of saying we had opportunity to comment on letter implies we agree with letter. Request for change in wording.
5/21/97 Sebrosky Comment on NRC request to suggested preface to WCAP-14690.
5/21/97 Kenyon Agenda for 6/9 lilCB tech spec meeting.
5/22/97 Kenyon/ Markup of SSAR section 3.2.2.7 to resolve Chang Li question.
Jackson Will go in revision 13 unless we hear from you.
5/22/97 Kenyon/ Markup of SSAR section 11.5 and 11.5.7 to resolve Chang Li Jackson question. Will go in revision 13 unless we hear from you.
3295 A wpf
l 4 . .
I 5/23/97 Jackson /Kenyon Information to resolve open item 253 from 11/5/96 phone call.
Will be in revision 13 unless we hear from you.
5/28/97 Jackson Section 3.9 open items we thought were closed weeks ago.
l
{ 5/28/97 Sebrosky Chapter 19.1 OITS status.
5/23/97 Quay Clearing open items on FSER sections.
5/29/97 Quay Concern over lack of identified progress.
5/30/97 Sebrosky OITS question on PRA chapter 42 - Second request.
5/30/97 Quay Section 3.9 open items - Lack of response from staff.
5/29/97 Quay Progress on open items.
6/2/97 Bongarra Markup of tier 1 material as discussed on 5/27. !
5/28/97 Iluffman Informal correspondence tracking.
6/3/97 Iluffman I&C tech spec markups.
5/23/97 Sebrosky Section 14.2.10.4.28.
6/3/97 Quay Open item status report.
6/4/97 Kenyon Better sketches. ;
6/4/97 Iluffman Tech spec 3.3.1 markup.
6/3/97 Kenyon SSAR markup showing radiation monitor for criticality .
I detection.
6/5/97 Iluffman Chapter 21 open item update. )
5/29/97 Iluffman ' Westinghouse summary of 5/6 RTNSS meeting.
6/4/97 Quay / Slosson Wednesday reminder of items needing NRC acknowledgement.
l l
12e A wpf
... - - -.. ~.. ~- ---. - - - - .~.----.... . --- - .- ~.
e, 4
1 z..
4 i ** TX CONFIRMATION REPORT **. AS OF MAY 16 '97 12:09 PAGE.01 1
- AP600 DESIGN CERT l .-
1 h DATE TIME TO/FROH MODE MIN /SEC PGS STATUS i 01 5/16 12:08 #23:NRC G3--S 01.*10 02 OK I
2 i
i I
1 1 l 1 l 1
i I ;
i j.
t a
t d
4 I
i i
q
- 18. Hum:n Fectors Engine: ring f .
F N /W cus 19% the Chaw'P s tdl{r e :be in operator decision-makmg proces&
Fed A.
s, and promotes faction the mte SSM with - other plant personnel, while preventing distractions by non-operating personnel. The main control room provides the interfacing resources between the operation of the plant and the maintenance of the plant. Its areas include the main control area, the switching and tagging area, the shift supervisor's office, the shift supervisor's clerk's office, and the operations staff's area (see Figure 1.2-8). Habitability systems are described in Sections 6.4 and 9.4.
18.8.3.2 Main Control Area Mission and Major Tasks The mission of the main control area is to provide the support facilitie n essary for the operators to monitor and control the AP600 efficiently and reliably. Fi 6.4-1 provides a view of thp main control area. The main control area inc.udes reactor operator
_.), N and the pahl associated with the wall panel information The layout, size and syst ergonomics of the operator workstetbns and the wall panel information system depicted in this figure does not reflect the results ei the human system interface design implementation plan described in subsection 18.8.1. The actual size, shape, ergonomics and layout of the operator workstations and the wall panel information system is an output of the implementation plan.
The major task of the main control area is to provide the human system interface resources that determine the plant state and implement the desired changes to the plant state during both normal and emergency plant operations. The main control area provides alarms to alert the operator to the need for further investigation. Plant process data displays permit the operator to observe abnormal conditions and identify the plant state. The controls enable the operator to execute actions. The process data displays and the alarms provide feedback to enable the operator to observe the effects of the control actions. l 1
i EmL g' % deactor operator Workstatiorg m.d :?c~ontairghe displays and contr maneuver the plant, and shut down the plant. Reference 44 presents input from the designer to the Combined License applicant for the determination of the staffing level of the operating 1 crew in the main control room. Each workstation is designed to be manned by one operator.
There is sufficient space and operator' interface devices for two operators. The physical makeup of,"/ci=icas A .d " is identical. The human system interface resources available at each workstation are:
%e g (egQ ogerxhrtGot W 'h3 Plant information system displays i Control displays (soft controls)
Alarm system support displays l
Computerized procedure displays '
Screen and component selector controls -
\the readrarnocrg m bM,c p ;
The supervisor workstation is identical toi"le&3i Gu/A i.J 0, except that its controls are
~
locked-out. The supervisor workstation contains both internal plant and external plant commumcations systems.
l l
Revision: 10
[ W8Stiflgh0US8 18.8 17 December 20,1996
/
~*
- 1. Introduedon and General Description of Plant k
O Table 1.8-2 (Sheet 4 of 4)
SUMMARY
OF AP600 STANDARD PLANT COMBINED LICENSE INFORMATION ITEMS Item No. Subject Subsection 12.5-1 Radiological Protection Organization and Procedures 12.5.5 13.1 1 Organizational Structure of Combined License Applicant 13.1.1 13.2 1 Training Program for Plant Personnel 13.2.1 13.3 1 Emergency Planning and Communications 13.3.1 13.4-1 Operational Review 13.4.1 13.5-1 Plant Procedures 13.5.1 13.6-1 Security Plans Organization and Testing 13.6.13.1 13.6-2 Vital Equipment 13.6.13.2 13.6-3 Plant Security System 13.6.13.3 13.6-4 Vulnerability Analysis Report 13.6.13.4 14.4-1 Initial Test Program 14.4 16.2 1 Design Reliability Assurance Program / Site Specific 16.2.7.1 16.2-2 Operational Reliability Assurance Activities 16.2.7.2 1 18.3 1 Operating Experience Review 18.3.1 l 18.5-1 Task Analysis 18.5.4 18.6 1 Plant Staffing 18.6.1 Ita 6
- 18. a.g. g Efw2rp Opem% Fad \i l8. AM- A bACCOhb d bfhOn '
Fochres Enjneermg 9mpm j l
l l
. l O
O Revision: 10 g ggg 1.8-13 December 20,1996 i
__ - - . - _ _ _ _ _ .___m . .- _ . _ _ _ . __ _
M
'q D Lindgren, Donald A.,04:18@M 5/15/97A Subject l v -
From: "Linderen. Donald A." <lindglda@ westinghouse.com>
To:{brcsky, J <jms3 @nrc. gov >,
mi. . .;.., aniel J."
[pMw[ **
<medermdj @ westinghouse.com>,
"Gresham, James A."
<greshaja@ westinghouse.com>
Cc: "Schulz, Terry L." <.schulztl@ westinghouse.com>,
"Vijuk Ronald P."
<vijukrp@ westinghouse.com>,
"'Huffman, Bill'" <WCH@nrc. gov >,
" Haag, Cynthia L." <haagcl@wesmail.com>,
"Scobel, James H."
<scobeljh@ westinghouse.com>,
'McIntyre, Brian A" <mcintyba@wesmail.com>
Subject:
Date: Thu,15 May 199716:18:16 -0400 X-Priority: 3 The following is our draft Agenda for next Tuesday's meeting. The topics are grouped based on the support people we need here.
Don Lindgren Agenda for Meeting May 20,1997 with Containment Branch Staff Review of mixing study and dead ended compartments The need for hydrogen control (PARS and igniters)in dead ended compartments Hydrogen controlin upper dome l
Effectiveness of two standard size PARS Function and classification of PAR on the IRWST vent Review of RAI responses (August)
Hydrogen compliance with regulttions SSAR poison testing commitments Open item status for 6.2.4 Initial Test Plan issues for containment and isolation RAls 260.118-260.139
~
~
Printed forflirian ' . McIntyre" <mcintyba@wcsmall.com> _ _ _
l' j
f 1
Review of screen design (sumps) 9 l
l l
1 i
i Printed for " Brian A. McIntyre" <mcintyba@wesmail.com> 2
j l i Winters, James W.,11:22 AM 5/16/97, Wednesday Reminder of Items Ne l From: " Winters, James W." <winterjw@ westinghouse.com>
l To: "' des ! @ nre. gov'" < des t @ nrc. gov >, "'trq@ nrc. gov'" <trq @ nrc. gov >,
"'jms3@nrc. gov'" <jms3@nrc. gov >
Cc: "'dtj@nrc. gov'" <dtj@nrc. gov >, "'tjk2@nrc. gov'" <tjk2@nrc. gov >, 1
"'wch@nrc. gov'" <wch@nrc. gov >,
"McIntyre, Brian A" <mcintyba@wesmail.com>,
"Cummins, Ed" <cumminwe@ westinghouse.com>,
"Vijuk, Robert M." ,
<vijukIrm@ westinghouse.com>, l "Rarig, Bruce E." l
<rarigbe@ westinghouse.com>,
"Nydes, Robin K." <nydestk@ westinghouse.com>, l "Lindgren. Donald A." <lindglda@ westinghouse.com>,
" Haag, Cynthia L."
<haagIcl@ westinghouse.com>,
" Chase, Wayne L." <chasewl@ westinghouse.com>,
"' mms @nre. gov'" < mms @nrc. gov >, l "Tupper, Robert B." <tupperrb@wesmail.com>,
" Winters, James W." <winterjw@ westinghouse.com> l'
Subject:
Wednesday Reminder of Items Needing NRC Acknowledgment Date: Fri,16 May 199711:22:45 -0400 X-Priority: 3 l
> To meet the SECY-97-051 schedule of " Applicant Submits Final SSAR
> Revisions & Documentation" by 5/97, we believe that NRC must
> acknowledge receipt of all Westinghouse submittals by May 30,1997.
> This is just 15 calendar days (11 business days) away.
> The background for each of these items is outlined in the Open Items
> Tracking System. They ALL have been addressed by Westinghouse.
> NRC is requested to please acknowledge receipt ofinformation related
> to each of the following Open Items. The reviewer in each case should
> have a submittal from Westinghouse as identified in OITS for the item.
> Re;ognizing that reviewing for completeness of the response in each
> case constituus an NRC action, we recommend that receipt
> acknowledgement be accompanied by direction to change their "NRC
> Status" to " Action N" If these are truly " Action W", please provide
> a description of the action Westinghouse is expected to take. We know
> of no action required. Many of these are very (over 6 months) old.
> We are not asking for resolution or even NRC review at this time,just
> acknowledgement that you have received the information as outlined in
> the OITS Status Detail. If your investigation shows I goofed and
> didn't remove item numbers that I should have, please let me know.
ltems associated with PRA are in bold. Items associated with containment are in italics.
> 3, 4, 27, 370, 372, 457, 459, 500, 501, 502, 504, 505, 549, 562, 563,
> 564, 608, 616, 649, 662, 664, 668, 706745, 750, 766, 769, 772, 782, Printed for " Brian A. McIntyre" <mcintyba@wesmail.com> 1l j
e(
L p
l > 783, 786, 793, 798, 800, 801, 805, 814, 819, 820, 821, 854, 972, 973,
- > 984,988,1002,1007,1008,1009,1012,1019,1023,1024,1025,1134,
> 1140,1142,1151,1152,1194,1259,1261,1270,1278,1279,1280, 1 > 1281,1282,1283,1284,1285,1406,1432,1447,1448,1450,1452,-
> 1458,1460,1461,1466,1482,1521,1525,1576,1612,1616,1623,
>1627,1633,1638,1639,1652,1653,1654,1655,1656,1657,1658, !
> 1659,1660,1661,1662,1663,1664,1665,1666,1667,1668,1669,
> 1670,1671,1672,1673,1674,1675,1676,1677,1678,1682,1683,
> 1684,1685,1686,1712,1763,1797,1802,1803,1807,1885,1888, ;
> 1925,1970,1971,1975,1991,2060,2074,2089,2141,2142,2143, I
> 2144, 2145, 2146, 2148, 2149, 2150, 2152, 2153, 2154, 2156, 2157 -i
> 2158, 2159, 2160, 2161, 2162, 2163, 2164, 2165, 2187, 2188, 2189,
> 2190, 2191, 2192, 2193, 2194, 2195, 2196, 2197, 2198, 2199, 2200,
. > 2201( 2202, 2203, 2204, 2205, 22%, 2207, 2209, 2210, 2211, 2212, ,
~> 2213, 2214, 2215, 2216, 2217, 2218, 2219, 2220, 2221, 2230, 2233,
> 2234, 2235, 2236, 2237, 2238, 2239, 2241, 2245, 2254, 2255, 2259, ;
> 2260, 2261, 2262, 2267, 2271, 2343, 2351, 2352, 2353, 2354, 2355,
> 2387, 2411, 2413, 2415, 2416, 2417, 2418, 2419, 2421, 2434, 2436,
> 2437, 2438, 2439, 2440, 2441, 2442, 2443, 2444, 2445, 2446, 2447,
> 2449, 2450, 2451, 2452, 2453, 2455, 2456, 2457, 2458, 2459, 2460,
. > 2462, 2463, 2469, 2485, 2487, 24%, 2502, 2503, 2504, 2505, 2512,
> 2514, 2515, 2536, 2537, 2538, 2539, 2540, 2541, 2542, 2597, 2605,
> 2606, 2608, 2609, 2610, 261 1, 2613, 2615, 2631, 2632, 2633, 2634,
>2635,2636,2637,2688,2718,2738,2739,2740,2741,2791,2792, . .
> 2793, 2794, 2795, 27%, 2797, 2798, 2799, 2800, 2801, 2802, 2803,
> 2883,2884,2885,2887,2888,2889,2892,2893,2894,2895,28%,
>2915,2922,2923,2924,2925,2927,2939,2942,2945,2958,2959, j
> 2960, 2961, 2981, 2982, 2983, 2984, 2986, 3009, 3053, 3054, 3062, ;
> 3%3, 3064, 3065, 3066, 3%7, 3068, 3069, 3070, 3071, 3072, 3073. -
>3074,3075,3076,3077,3078,3079,3080,3081,3082,3098,3105, ,
> 3106, 3107, 3120, 3121, 3122, 3124, 3125, 3126. 3127, 3128, 3129, - !
> 3131, 3133, 3140, 3141, 3142, 3143, 3145, 3146, 3151, 3152, 3153,
>3154,3155,3156,3160,3161,3162,3163,3164,3165,3166,3167,
> 3168, 3169, 3170, 3183, 3187, 31 %, 3197, 3198, 3200, 3202, 3208,
> 3209, 3210, 321 1, 3215, 3220, 3223, 3224,- 3225, 3226, 3227, 3228,
>3229,3231,3232,3233,3234,3236,3238,3239,3240,3372,3381,
> 3384, 3385, 3390, 3395, 3397, 3413, 3419, 3422, 3424, 3427, 3431,
>3432,3433,3434,3435,3436,3481,3482,3485,3486,3487,3488,
> 3489, 3490, 3491, 3492, 3493, 3494, 3495, 34%, 3497, 3498, 3499,
> 3500, 3501, 3502, 3503, 3504, 3512, 3520, 3521, 3522, 3941, 3943,
> 3960, 3 % 1, 41 16, 41 17, 41 18, 41 19, 4121, 4122, 4123, 4124, 4125,
> 4126,4127,4128,4129,4130,4131,4132, 4133,4134,4135,4136, ,
>4137,4138,4139,4140,4141,4142,4143,4144,4145,4148,4151,
> 4158,4165,4166,4170,4172,4182,4187,4188,4190,4198,4224,
'E > 4225,4226,4227,4525,4615,4852,4970,4971,4972,4985,4986,
> 4987, 4988, 4989, 4997, 5004, 5013, 5014, 5015, 5016, 5028, 5030, p5031,5032,5034,5035,5036,5037,5038,5039,5040,5041,5042,
>5043,5044,5045,5046,5047,5048,5049,5050,5119,5120,5150,and
>5250.
Printed for " Brian A. McIntyre" <mcintyba@wesmall.com> 2l
i f
> Thahks
> Jim Winters
> 412-374-5290 l
Printed for " Brian A. McIntyre" <mcintyba@wesmall.com> 3l
r Lovato, Janet M.
From: Nydes, Robin K. l Sent: Friday, Ma/16,199710:56 AM i To: 'jms3@nrc. gov'; 'wch@nrc. gov' Cc: Nydes, Robin K.; Kerci, Steven P.; Lovato, Janet M.; McIntyre, Brian A
Subject:
Suggested Preface to WCAP-14690. )
Janet - Would you please print this and place a copy in the informal correspondence file Thanks.
Joe - 1 incorporated your (Jim's) comment from this morning regarding the number of work station (s) on SSAR page 18.8-17 (2 places). With this, all of the SSAR Chapter 18 changes related to deleting reference to a l computerized" procedure system, except for our caveat related to NRC acceptance of a computerized procedure system, will appear in the end-May SSAR Rev.
Regarding the caveat, I do not think the SSAR is not an appropriate place for that text. Understanding the NRC concern that a statement in the SER is not enough for the rulemaking, I propose Westinghouse revise WCAP-14690, the primary reference for the computerized procedure system, to include the caveat as a preface. The end-May SSAR revision for Chapter 18 would then include a change in the revision number for WCAP-14690, from 0 to 1 and WCAP-14690 Revision 1 (which would include the preface) could be submitted to the NRC by the end of May.
Please review this idea and the following preface text and let me know if you find it an acceptable resolution of this issue:
Although the AP600 human system interface resources include a computerized procedure system, evaluation of the acceptability of a computerized procedure system is not part of the NRC staff AP600 Human Factors Engineering Program review. The NRC neither endorses or rejects the possibility of using a computerized procedure system as a means for providing instruction to plant personnel. At the time of AP600 design certification, the NRC staff does not support or deny the acceptability of implementing a computerized procedure system in a nuclear power plant environment. The acceptability of such a system for application to the AP600 design will be determined during the implementation of the AP600 man-in-loop test program and verification and validation program (ITAAC 3.2," Human Factors Engineering").
9 Page1
A' Wsmus W85110gl10VS8
% vvvcrivincb.i RECIPIENT INFORMATION SENDER INFORMATION OATE: /y)/4i/ / F , /99 7 NAME: _gg TO:
D / LOCATION:
ENERGY CENTER -
U / LL bl0 % A AI EAST PHONE: FACSIMILE: PHONE-ottice:///2-3 7V-5 29o COMPANY: Facsimile: Win: 264 4 % 7
() J Al/lc outside: (412)374 4887 LOCATION:
Cover + Pages 1+/
The following pages are being sent from the Westinghouse Energy Center, East Tower, Monroeville, PA. If any problems occur during this transmission, please call:
WIN: 284-5125 (Janice) or Outside: (412)374 5125.
COMMENTS:
OlLL Q (.h MAllic4 SHcuto /265cLui /Outt Qu esDor) Beam cu A. $tto_Alf
/3 CALL fL-Mit=tOku & w e a Go u(1)b 10Gu. [ l 77/F S3 All 0 4Lc1]
wF AMIL Filom bd . $f 7HE u/A/. 60A ALMAML= RiL 2 27 7 WA.5 ftAsr F RKfC Tb /
tou GN Anc is,iee7.
ce; .r u c t e o u DN w vvTe%
- CD i
<teo un su<
c w.u.s
[of?. L GMl -
l ggAoE cMaJ 1 !
l l'
in
- _n i 5. Reactor Coolant System and Connected Systems One safety relief valve is located on the normal residual heat removal system suction header inside containment. His valve provides low temperature overpressure protection of the reactor coolant system. Subsection 5.4.9 describes the sizing basis of this valve. Anotha.r safety relief valve outside of containment provides protection against excess pressure for the piping and components.
When the normal residual heat removal system is in operation the water chemistry is the same as that of the reactor coolant. Sampling may be performed using the normal residual heat removal heat exchangers channel head drain connections. Sampling of the reactor coolant system using these connections is available at shutdown. . Sampling of the in-containment refueling water storage tank is available during normal plant operation.
5.4.7.2.1 Design Features Addressing Mid Loop Operations The following is a summary of the specific AP600 design features that address Generic Letter (GL) 88-17 regarding mid-loop operations. g ,g, 3 . (o ,
Loop Piping Offset - As d " ' -[ - ' ' ' ' the reactor coolant system hot legs and cold lep are vertically offset. His permits draining of the steam generators for nonle dam insertion with hot leg level much higher than traditional designs. The reactor coolant system must be drained to a level which is sufficient to provide a vent path from the pressurizer to the steam generators. This is nominally 80 percent level in the hot leg. This loop piping offset also allows a reactor coolant pump to be replaced without removing a full core.
Step-nozzle Connection The normal residual heat removal system employs a step-nozzle connection to the reactor coolant system hot leg. The step-nozzle connection has two effects on mid loop operation. One effect is to substantially lower the RCS hot leg level at which
. a vortex occurs in the residual heat removal pump suction line due to the lower fluid velocity in the hot leg nozzle. His increases the margin from the nominal mid-loop level to the level where air entrainment into the pump suction begins.
Another effect of the step-nozzle is that, if a vortex should occur, the maximum air entrainment into the pump suction has been shown experimentally to be no greater than 5 percent. His level of air ingestion will make air binding of the pump much less likely.
No Normal Residual Heat Removal Throttling During Mid Loop - The normal residual heat removal pumps are designed to minimize susceptibility to cavitation. He plant piping configuration, piping elevations and routing, and the pump net positive suction head characteristics allow the normal residual heat removal pumps to be started and operated at their full design flow rates with saturated conditions in the reactor coolant system. The normai residual heat removal system operates without the need for throttling a residual heat removal cor. trol valve when the level in the reactor coolant system is reduced to a mid loop level.
Revision: 11 5.4-43 February 28,1997 T Westinghouse
' sie.$,:
Brian A. McIntyre,08:22 AM 5/19/97 Hydrogen meeting l Date: Mon,19 May 1997 08:22:33 -0400 To: jms3 @nre. gov, TRQ@NRC. GOV From: " Brian A. McIntyre" <meintyba@wesmail.com>
Subject:
Hydrogen meeting Cc: mcintyba@wesmail.com Joe, Please be prepared to discuss the results of the NRC confirmatory PAR testing that you are performing at Sandia during the meeting tomorrow.
Brian A.McIntyre Bell 412.374.4334 4 WIN 284.4334 FAX Bell 412.374.4887 FAX WIN 284.4887 1
i d
1 l .
1
~
Printed for " Brian A. McIntyre" <mcintyba@wesmail.com> 1I
1 e, 1 lV WESTINGHOUSE ELECTRIC CORPORATION PO BOX 355 PITTSBURGH, PA 15230-0355 ADVANCED PLANT SAFETY AND LICENSING
, FAX NO: 412474 4387 (WIN 284) 4 CONFIRMATION NO: 412 4 74-4237 1
DATE:
TO: Go FA C/ V l
LOCATION:
I l l
FAX NUMBER:
i FROM: Brian A. McIntyre PHONE: WIN: 284-4334
- BELL: 412-374-4334 1
NUMBEM OF PAGES (INCLUDING COVER SHEET):
1
, COMENTS / MESSAGE:
a h
&caso Ana L Ac-xr Ewn- &
Gua we-a Ru, A % 2; 46r Gaunee dL M.i su
&~ kncee AM An s. m A,
kmuem e %r > % /&~.
4
=
j
( L,
- "% NAC/kPCN9'
, y \ UNITED STATES j
j NUCLEAR REGULATORY COMMISSION
- WASHINGTON, D.C. 20666-0001 7
'+ g
- .* May 14, 1997 ,6 3 !
!( MAY l 91997 ~!
' Gu ,,)
Mr. Nicholas J. Liparulo, Manager Snan A. Mc Intyfe Nuclear Safety and Regulatory Analysis j
Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, PA 15230 l
SUBJECT:
FOLLOWON QUESTIONS REGARDING THE WESTINGHOUSE AP600 INITIAL TEST
. PROGRAM (ITP)
Dear Mr. Liparulo:
I As a result of its review of the June 1992, application for design certifica-tion of the AP600, the staff has determined that it needs additional informa-tion. Specifically, the enclosure to this letter contains requests for ,
i
- additional information concerning the AP600 ITP resulting from a review done by the Containment Systems and Severe Accident Branch.
You have requested that portions of the information submitted in the
! June 1992, application for design certification be exempt from mandatory i public disclosure. While the staff has not comoleted its review of your reque.a 16. ...; :mtaa.e ei+h' t5 .ig". 2e c .-
"D 2.:'ah 4.'.Tt' prv;.rn of the submitted inform ~ation is being withheld from.public disclosure pending the lj staff's final deterniination. The staff concludes that these followon ques-tions do not contain those portions of the information for which exemption is
{ sought. However, the staff will withhold this letter from public disclosure
, for 30 calendar days from the date of this letter to allow Westinghouse the opportunity to verify the staff's conclusions. If, after that time, you do not request that all or portions of the information in the enclosures be
- withheld from public disclosure in accordance with 10 CFR 2.790, this letter will be placed in the Nuclear Regulatory Commission Public Document Room.
i 4
i
- . .- ., - ~ - .. .. .~ ~.-. - . - .- - - -.. .-.- .~.-- - . -. -..-.- - . .
A Q
k 0kf f
- l UNITED STATES
, '~
s
- j i
NUCLEAR REGULATORY COMMISSION
\
k p' WASHINGTON. o.C. SceaHoot April 17, 1997 L ,'
. < r
{ APR 231997
) Mr. Nicholas J. Liparulo, Manager Cl s
] Nuclear Safety and Regulatory Activities A{
i Brian A. Mc Intyre Nuclear and Advanced Technology Division i Westinghouse Electric Corporation
! P.O. Box 355 l Pittsburgh, PA 15230 i
SUBJECT:
WESTINGHOUSE'S SUPPORT OF THE NUCLEAR REGULATORY COM 0F THE AP600 DESIGN CERTIFICATION REVIEW
]
Dear Mr. Liparulo:
In a March 6,1997 letter, the staff forwarded SECY-97-051, " Schedule for the l Staff's Review of the AP600 Design Certification Application," which was based
!- on the November 20 and 21, 1996, scheduling meetings between the staff and
{.*
1 Westinghouse.
1 Certain key information has not been submitted in accordance with the Novem-ber 1996 agreements (see attached).
ted late; other information has not yetSome beenofsubmitted.
the information has been submit-In some instances, it l' is the <t f' We +tanding tW aa.'le ]houw is dC r/inq "t fini i . v; d . ' s .s . c., .f .0 ' icuiyutats respunics to starf coments on l grev u usly-reenived, advance information.
i its . g eed-to comment milestones. The staff has also missed some of Although the staff believes that it is desirable for Westinghouse to incorpo-rate responses to early staff feedback based on advance information Westing-
{ - house should not wait for that feedback if such action will cause a,signifi-i cant delay in the submittal schedule. The staff agreed to review advance
! ~information when it was able to help expedite the review of the AP600, but i
such review cannot always be provided because of assignments of the staff to
[ higher-priority activities. For example, Westinghouse is waiting for staff inspections, tests, analyses, and acceptance criteria (ITAAC) comments in the containment systems area. While the staff expects to send these coments to Westinghouse in the next week, Westinghouse should not delay its revised ITAAC submittal any longer. The containment systems ITAAC represent only a few of i
the total number of ITAAC, and modifications to these ITAAC to respond to l staff comments should not hold up submittal of the entire ITAAC package.
4' 4
i In order for the staff to allocate its limited resources appropriately, and
' assess whether the review schedule described in SECY-97-051.can still be met, Westinghouse should submit revised dates for the items listed in the attach-i ment as well as other submittals that Westinghouse expects will be late. The i staff concluded that the schedule presented in SECY-97-051 can be achieved if j
Westinghouse submits timely, high-quality standard safety analysis report, ITAAC, and technical specification information. Deviation from these sub-i mittal dates has resulted in delays in initiating staff reviews. When the
]
i
a..
I O
W 1 Westinghouse D
FAX COVER SHEET RECIPIENT INFORMATION SENDER INFORMATION DATE: Monday, May 19,1997 NAME: Earl H Novendstern TO: Joe Sebrcsky LOCATION: Westinghouse PHONE: x1132 PHONE: (412) 374 4790 COMPANY: NRC FAX: (412) 374-4011 Cover + Pages = 1 + 23 Comments:
Jos ; .1 ached are advance RAI responses on WCT CAD. They are marked draft, only because they ha- i gone out under a Westinghouse Cover Letter. No text should change when finally submitted.
! :se give copy to Lambrose and Bill. Thanks. _ . _
) .
[.Ovv - _
cc: B. McIntyre (NRC Informal Correspondence File), S. Fanto, R. Kemper, L. Hochreiter, File 7.5.1.2 l l
l 1
fax DOT
.. ?M J . . ', 4 A G J COMMENTS ON WESTINGHOUSE'S REPORT 1 WCAP 14171, REV.1 WCOBRA/ TRAC APPLICABILITY TO AP600 LBLOCA NOTE: The questions are based on the review of information Westinghouse submitted in Reference 1. p
- 1. The following questions relate to the AP600 Phenomena identification and Ranking Table (PIRT) presented by Westinghouse in Section 2.1 of Reference 1. They also represent followup questions to item 8e in the May 17,1996, NRC fetter.
In several cases, Westinghouse stated that a lower ranking was given to a 4G34 a.
l certain phenomenon in the AP600 because of the low peak cladding temperatures (PCTs) calculated for the plant. Examples include reflood heat transfer, entrainment/deentrainment in the core, and containment pressure. For these phenomena, and for others if Westinghouse makes similar arguments for them, clarify if (a) calculating these phenomena are important even if PCTs are low or (b) they are important because they contribute to the calculation of the lower PCTs. If Westinghouse answers yes to either a or b above, provide additional information to justify the lower AP600 ranking.
I The calcuinelon of these parameters le important to the calcuinefon of the PCT.
However, because of the lonerlaw1t raelng of the AP600, better blondown cooling, etc., one can have a larger sHonobio uncertainty in the calcuinefon of these phenomene. Thereibre, they are ranked loner then ibr a N4 loop plant in which there is less rnergin availabie and Ibr which one can not 60dernen a large uncertainty.
- b. For containment pressure. reflood heat transfer, and core //G3f entrainment/deentrainment, and for other phenomena if Westinghouse makes similar arguments about the lower AP600 PCTs for them, clarify if the INEL understanding is correct regarding the conservatism of the calculations or how the uncertainty is accounted for in the Westinghouse methodology:
(1) containment pressure: Westinghouse uses a lower bound containment
- pressure consistent with current conservative (Appendix K) analyses.
See Tabie 4.41, a bounded value le used sim6lnr to Appendbc K.
i (2) reflood heat transfer: Uncertainties in this area are included in the uncertainty methodology.
Correct, uncertaineles are included in the unwrtainty moiti&&dagy same a
as N4 piente.
Page1
/ctrV444RMK wpf c
L .. DRAFT ,
core entrainment/deentrainment: YlCOBRA/ TRAC analyses are l I
(3) conservative in this area as discussed in Section 3.1.6 of the Revised 4
Methodology Report (RMR).' In addition, the uncertainty in core l entrainment/deentrainment is covered in Westinghouse's overall heat transfer coefficient (HTC) multiplier methodology, which captures q
differences in local fluid conditions.
Conect, uncertainties are treated in the same fashion as 3/4 loop plants.
- f. On page 2 2, Westinghouse stated that core top down flow /CCF limit is
] ffff V>8 addressed under the PIRT upper plenum component discussion. However, the PIRT does not rank upper plenum CCF drain / fallback while the upper head
- blowdown flow is ranked. Clarify if the upper head ranking is what .
Westinghouse was referring to on page 2-2, or if West,inghouse was referring to i
I the information on page 2-8 discussed in part d.
The discussion of the CCFL is on page 2-8, 4th paragraph. The phenomena is not ranted since its etllrcts only occur momentarily at the end of blondown as the now transitione thom co-cument downnow to co-cunent up60w during the renood phase.
- g. Given the AP600 results in Section 2.2.3, clarify if the INEL is correct in N[vh interpreting that accumulator nitrogen discharge is not an large break loss of-coolant accident (LBLOCA) issue with AP600 because the core quenches before the accumulators empty. Clarify how much liquid is left in the AP600 accumulators at the end of the analysis discussed in Section 2.2.3 and how long it would take for the accumulators to empty. If there is less than 20% of the accumulator liquid left at the end of the analysis (so that a change in plant design or the analysis could result in the accumulators emptying) or Westinghouse concludes accumulator nitrogen discharge is a LBLOCA issue for AP600, then provide the following information. On page 2-10, Westinghouse stated that the affects of nitrogen discharge after the accumulators empty were addressed in the Code Scaling, Applicability, and Uncertainty (CSAU) report.'
However,in the CSAU report, only the affects of dissolved non-condensibles were studied, not the large amounts of nitrogen discharged after the accumulators empty. Therefore, clarify this reference to the CSAU report or provide the correct reference. Also,is accumulator nitrogen discharge addressed for AP600 in the same manner as for 3 /4 loop plants?
The PCT occurs bellore the accumuinear is empty. In the SSAR DECLG break analysin, the remaining accumulator imentory when the re600d PCT is reached, is about 60% of the inittel. The accumulehors empty at 300 seconde which is oser 200 seconde steer the PCT. Ad&rseing the uncereninty in the accumulator
' nitrogen diocherpe is not needed since the accumulators are self infectfog no#
aller the PCT and inclusion of the uncerteinty woukt not etlInct the calcuinted PCT.
Page 2
/Cm/444RMK.wpt
DRAFT
)
- h. In the call on November 25,1996, Westinghouse stated Discussion item 8b h from the May 17,1996, letter was discussed in the 4th paragraph of Section 2.1. This paragraph, however, addresses downcomer behavior not upper plenum CCF/ fall back. Should Westinghouse have referred INEL to page 2-8, 4th paragraph?
i Yes.
- i. As a followup to Discussion item 8d, May 17,1996, letter.
g[L (2) For core entrainment/deentrainment and reflood interfacial heat and mass transfer (as part of reflood heat transfer) see parts a and b above. i For core top down flow /CCF, upper plenum multidimensional flow / flow distribution (hot legs / core), and upper plenum CCF/ fall back see parts d ,
l and e above.
See responnes to perte a and b pnMded herein and M parte d and e when pnMded (3)
For core multidimensional flow in reflood, clarify the low Westinghouse ranking relative to the CSAU study and the LANL PIRT (see page 64 of the LANL report).'
This phenomenon in rarderd kner h the Weathghouse PIRT as compared to the LANL PIRT. There were two elemente 80 the LANL l rationnietbr the ran6dng of thle ihm; kom page 64 d the LANL report, \
l
'Multidimenolonel ellincte M the core enhance the heat tranener by j
supplying more weerr to the high powered bundes below the quench kont". We agree nnh this part of the statement, and thle le one reason ,
that the low powered regione are modeled as a seperate channelin the WCOBRAfTRAC PWR model The quench kont le uninorm acrose the core such that the lower powered bundes quench at about the same ,
time sa the high ponered bundes, and there Je crose now into the hot neeembly kom the a4ecent, low ponered aseembeles BELOW the quench kont.
LANL sino seye h the some senernoe on page 64; "and more entrained nemr h the liquid dencient region". We do not agree that there le more wakr entrained into the hot aseembly kom the a4ecent assemb6es ABOVE the querdt kont, which le what the LANL sukment imp 6es.
Therenore, ne raried thin 18em as a '5" but dd consider it importent enough that ne modeled mun$is channoin h the resceor lo cepeurs thin three dimenodonel behevior.
Page 3 Icm/444RMK.wpf
- 2. These items relate to Table 2.1-2 and followup Item 8f (5/17/96 letter).
- a. Because of low PCTs, Westinghouse has a low ranking for cladding oxidation in its PlRT and did not discuss cladding oxidation in Table 2.1-2. The INEL
- g. bo agrees that the low cladding temperatures currently calculated by Westinghouse l 1 for the AP600 indicate this is not an important phenomenon for the AP600. For ;
3-/4 loop plants, however, the uncertainty evaluation included the cladding j oxidation uncertainty. Clarity if Westinghouse has removed cladding oxidation j uncertainty from the AP600 uncedainty evaluation. If yes, will Westinghouse i
commit to including cladding oxidation uncertainty if plant design or analysis l changes result in calculated cladding temperatures that cause oxidation to be -
! important?
i
{ .
The ceiculated PCTs sto signinoendy below the threshoid tbr signMoent zircMakr reaction which can h6uence the PCT. Honewr, the methodbiogy l which is used to ceiculek the AP600 PCT le the same as that used Ibr the i three and ibur loop plante. Thereibre, the unoettninty of the ziro%eter reaction
- j. and its efibete wif be ceicudend h the ' hot spot"ceiculations; howowr, shoe i' the PCTs compund Ibr the AP600 are low, the impact of the uncertainties and -
' the zircMeter reaction are emected to be neg6gible.
{
3
,t b. Gap conductance was not listed in Table 2.1-2. Based on the discussion on
- ' page 2-4, is the INEL correct in interpreting that this highly ranked phenomenon is covered under stored energy?
Yes Westinghouse stated decay heat uncertainty is addressed in the same manner d g c.
as 3 /4-loop plants. However, the portion of the 3-/4-loop plant methodology .
that addressed decay heat was changed for application to AP600. Therefore, provide additional information to justify how the decay heat uncertainty is addressed for the AP600 plant.
Tabis 2.1-2 le hoorrect. As described h Section 4.4, the une of toch speo!COLR peakhg Ibctore and 102% core poner resulte h equivaient or
- higher linest heat reus then if the Ad best estimate snethodoiogy were used.
The questions f 2c response wif ghe Asther frWbrmedian,
- d. For rewet, Westinghouse stated the same approach for 3-/4 loop plants would hb be used to address the uncertainty. Clarify if Table 2.12 should also state that this approach is supplemented by the information in Section 4.1 Yes, reviener is correct. A more conservalho approach wir be used tbr the AP600, as deouneed M Section 4.1.
- e. Westinghouse did not discuss the following highly ranked PIRT items in Table 2.12: core 3D flow and void generation / distribution, core flow reversal / stagnation, upper head blowdown flow and flow area, downcomer condensation, and direct vessel injection (DVI).
Page 4
/cm/444RMK.wpf
>.. DRAFT :
j . ... ..
- 4. Westinghouse discussed pressurizer location in AP600 LBLOCA analyses on page 2-g7% 32. The reference given to support the chosen location does not seem correct; therefore, provide the correct reference. Also, have any AP600 specific studies been
/ performed to support the pressuriDr location relative to the break? If yes, provide them for review, if not, justify why they are not needed.
l g/
The impact of pressuriter locadon relathe to the break has been inves6pekd in a l
- sensativity case. The locadon that is IrxHoekd in WCAP-14171, Revision 1 has been shown limiting. The tellerence provided is incorrect; it should be Rektence S.
- 5. On page 2 33, Westinghouse stated that after 10 s vapor flows out of the core in the guide tube locations. Clarify this statement because Figure 2.2-34 shows vapor l l g downflow after 10 s.
The last sentence on page 2-33 should read 'Dunng thin time inktval, vapor Rows l
down into the ccve at the guide tube locatione" rather than 'Up out of the core."
i.
\ 6. Westinghouse's discussion on the response of the low power rod in Figures 2.2-31 to
) 2.2-33 on page 2 34 is confusing. First, Westinghouse indicates that the low power l
i g% rod undergoes a small temperature excursion but later states that no initial temperature excursion in blowdown. Based on Figures 2.2-31 to 2.2-33, the later statement i appears to be correct. Therefore, clarify the apparent inconsistency or correct the report.
)
The hext should read that the peripheral rod exhibite 'no signlRcent initial temperature excursion" dunng b6cndown. Review of Figures 2.2 31 and 32 indiceers that at the 6.0 and 8.5 lbot elevatione a smnN 8emperature increase, on the order of 10 degrees F,
. is predicted at the incepdon of b6ondown.
l 7. The following questions relate to the CCTF analysis in Section 3.1.
Clarify the statement on page 3 8 that in the calculation the low power rods l
j
.g a.
quench early at the lower elevations. Figures 3.1-16 to 20 show an early j quench calculated at all elevations.
Figures 3.1-16 through 3.1-30 Indicate that WCOBRAf7RAC predicts an early
- quench of an IUel rode modeled in the simuinalon of CCTF Test 58 at nN elevations. The Aower elevatione are emphasired becoune the exceedingfy deinped quenching of the upper elevatione in this CCTF erst le not importent reinthe to the AP600 large break LOCA event, in which the quenching of a6 4 rode occurs within 100 seconds.
4
)
)
Page 6
/cm/444RMK.wpf J
i DRAFT
- b. Clarify the statement on page 3-9 that Figures 3.131 to 33 show the calculated i
g.g g quench front is 80 s too early. This is true for the high power rods, but the quench fronts on the medium and low power rods are early by approximately 120 s.
The fact that WCOBRNTRAC predcte early quenching of the uppermost L
elevadone of the medum and low power rode in CCTF Test 58 le unimportent.
As shown in Figure 2.2 26 of the report, at tuelin the AP600 core quenches l
during the Mrst 100 seconde of the large break LOCA transient. Therefore, the l
most signMcent comperieon of quenching le the elevatione between the bottom i
j core elevation and the elevnNon tbr which WCOBRNTRAC predicte the maximum quench time. Within this elevation ennlope, the code-predicted
+ quenching occurs wsthin 80 seconde of the times obeerwd in_ the CCTF Test 58 s for rode at each poner lowl.
I
- c. Clarify if the first paragraph on page 310 should be deleted because it refers to l
- ph the WCOBRA/ TRAC analysis in Rev. O of Reference 1.
The nrst two sentences of the Ifrst perngraph on page 3-10 are artifacte of l*
i WCAP-14171, Revision 0 and should be deleted.
- d. Clarify if the references to Figures 3.1-41 and 3.1-41 A, Rev. O and Rev.1, l g.97 respectively, in the fourth paragraph on page 3-10 should have been to Figures 3.1-45 and 3.145A.
/
1 i The iburth paragraph on page 310 conteine a typographical errori tenerences made to Figures 3.1-41 and 3.1-41A should ineensd rener 80 Figures 3.1-45 and i
3.1-45A, reepm2,ely.
l 4
- 8. The following questions relate to the UPTF analysis in Section 3.2.
I i c. In the discussion on page 3-81 on the LOFT lower plenum refill, provide comparisons between the Westinghouse WCOBRA/ TRAC results for LOFT Tests L2 2/2-3 and the test dat'a for L2-2/2-3 already provided in Reference 1.
p 7, This is a followup to item 7, May 17,1996, letter.
)
The LOFT L2 5 comperieon shows that the loner plenum and core reRE i
prodcted by WCOBRNTRAC le coneervathe (page 3-81). Further
?
?
documentetion of this may be ibund in the WCOBRNTRAC ' Compensating Errors" Report, NTD NRC-95-4586, for LOFT Test L2-3 (See Figure a10).
l Taleen hogether, the L2-3 and L2-5 comperieone are adequeen 80 teache that i
the code capably and conservalhely prodcts AP600 loner pienum tfMing.
1 i
}
i Page 7 Icm/444RMK.wpf
. . 1
.. DRAFT
- d. In response to RAI 440.348, Westinghouse provided a table comparing UPTF Test 21 test conditions to AP600 conditions. For the comparison in Reference
.. 1, the AP600 table was different from that provided in the RAI response, DON Clarify the reasons for the differences. f
^,
The AP600 conditions in the WCAP 14171 Rev.1 Table are taken from the WCOBRAfTRAC analysis presented in Chap %r 2, which had not been performed at the time of the RAl440.348 response. The condition dinierences
' are not great and are a result of modeling more restrictin accumulator conditione, specincally a higher water temperature and a lower injection Mow (Retier to Table 2.2 2) which causes the " Total ECC Injection to Downoomer" and the maximum ECC water subcooling value to be somewhat reduced. The steam Rowrate from the core into the downcomer has a lower value because end of-bypass is delayed with these accumulatbr condations.
- e. Based on the information in Section 3.2.8, is the INEL correct in assuming that l l ff[-[pf there is not sufficient data to develop a flooding curve for the CCTF and UPTF DVI tests directly from the test data and that other flooding correlations are not applic mie for the reasons discussed in that section? This is a followup queswa to Discussion item 6a, May 17,1996, letter.
] l Yes, the INEL Interpretation is conect
- 9. The following questions relate to Section 4.1.
i i
- b. Is the Tu, identified in Section 4.1 used in blowdown only or both blowdown i g.gt[ and reflood?
The Tmin value identined in Section 4.1 is used during blondown only.
- d. On page 4 4, Westinghouse discussed the temperature criterion used to screen the initial temperatures of the thermocouples used in the Tu, evaluation. The
" }[ temperature given was an average Tu, based on bundle average data from the RMR analysis. Justify whether it is appropriate to use this bundle average temperature Tu, to screen individual thermocouples as done in Section 4.1.
J This approach le designed to be conservalhe since the only T/Cs that will be considered are those which are initially GREATER then the awrage.
4 f
1 4
Page 8
/cm/444RMK.wpf J
s .
- DRAFT 1
! 10. The following questions relate to Section 4.2.
- e. Clarify the meaning of the word saturated in Table 4.2-1 regarding inlet water l temperatures for AP600. Is Westinghouse implying that AP600 sees only b
saturated water inlet conditions during blowdown? If yes, clarify the j temperature range relative to the pressure range which indicates some subcooling for the temperatures given.
i I
The word " saturated" indicates that AP600 Ilquid condfelone for blowdown cooHng am saturated or are wry nearty so. The pressure range :.hown in ,
[
Table 4.21 should read "approm\mately 250-1500 peln . j i '
l
- 12. The following questions relate to Section 4.4.
- a. Table 4.4-1:. Has the Westinghouse grid deformation analysis been approved l
by the NRC7 If not, will Westinghouse commit to addressing grid deformation if l l g the NRC review results in this becoming a concern for the AP6007 For mixed I
l cores, how will Westinghouse address mixed cores if they are used in AP600 in the future?
Since seismic lande are a slee W paramekr, it le dMicut 80 assess their l Impact at thin time. The structural and mechanicalintearity of the fuelis evaluated for each fuel cycle. In the ennt tuelgr1\d detiormation becomes a concern ibr a propoeed AP600 sien, Westinghouse wit addrese its impact on the Aarge break LOCA analysis, If Westinghouse IUelof a dMlrrent design or another vendor's tuel is pieced into AP600 in the IUture, an evaluation wiW be j
j peribemed of the mixed core; the evalunefon wid consider any dMferences in the dimensione, hydraulic resistences and bumup elllrcts between the IUel types to j ;
' beloaded.
i
- b. Westinghouse identified power shapes (PSs) 2,3,4 and 11 as the PSs it would evaluate from the RMR to determine the limiting PS for AP600. Justify the
, g/g.g basis for selecting these PSs as the ones to study the AP600. Could the
! excellent blowdown cooling for the AP600 cause the limiting axial power J -
shape (s) to change for AP600 relative to the 3 /4-loop plants? Also, Westinghouse has an approach to identify limiting axial power shapes to meet Appendix K, item I.A. Does this approach have any applicability for AP6007 I Justify your answer.
' The 3/4 loop power shapes nere astebMehed 80 be bounding ibr aM Westinghouse core designe, and they are boundng tbr AP600 as ne#. To
- turther demonstraen the Ilitunng nature of poner shapes 2, 3, 4 and 11 tbr AP600, a bottom skened poner shape case was sino execund and shown to be non limiting. Poner shape 3 in the bounding shape and le appued in aH AP600 metrix senartMty cases. The power shape resuden wit be reporend and
- icnV444RMK.wpf
=
4 DRAFT i f. Justify'the basis'for the choice of bounding accumulator conditions on page 4
- 14. Based on the CQD studies in Section 22. sometimes the limiting PCY was calculated when an accumulator condition other than those proposed for AP600
) 6 jp
- by Westinghouse was used. Are sensitivity studies needed? Justify your.
i answer.
i
- The AP600 is equipped whh tw large accumulators & large break LOCA midgadon. Because of the limrted accumulator capacity which 3/4 loop plants
- poense, downcomer undernH and downcomer boiling dudng core reRood 1- associated whh a minimum inidal accumulator water volume can somedmes i result in a more limiting PCT, These phenomena are unimportant Ibr AP600; the signdcant phenomenon & AP600 renood PCT is the dme required to reMil l the downoomer. A sensitMty case executed assuming the Technical SpecrRcedon maximum gas pressure in the accumulator has nnned that bounding the accumulatrx ?njecdon rate on the low end is indeed the conservadw approach.
}
i l
i i
4 1
i a
4 I
1 4
4 Page 10
/cm/444AMK wpf
O .
DRAFT czrs es c l 1.c. The AP600 PIRT shows a lower ranking for downcomer entrainment
. because it is less important during reflood for Two AP600 large break phenomena which I
LOCA events than it is for 3/4-loop plants.
can lead to liquid entrainment (and deentrainment) in 3/4-loop plants do not apply to AP600. First, the direct vessel injection of accumulator water and the very large accumulators with which the AP600 is equipped mean that no downcomer boiling occurs in AP600 during the time of interest for the calculation of peak cladding temperature. Second, the elevation of the DVI nozzle entrance into the AP600 downcomer ir about two feet below the bottom cold leg elevation, and the downcomer is equipped with flow diverters to direct safety inj ection water downward toward the lower plenum.
The safety injection water is not subject to surface entrainment
. into any high velocity steam which might be progressing frca the intact loop cold legs across the dowrcomer to the break.
The attached Figure 1.c-1 plots the entrained liquid flow predicted between cells in COBRA downcomer channel #56, which is connected to the broken cold leg, in the AP600 WCOBRA/ TRAC CD=0.8 DECLG analysis FEM (56,1) is presented in Chapter 2 of WCAP-14171, Revision 1.
the entrained droplet flow into the channel's lower cell from the channel below, and FEM (56,3) is the entrained droplet flow out of the channel upper cell, which is connected to the broken cold leg, into the channel above.TheFEM (56,2) shows the flow between the two figure illustrates that although as much cells of channel 56.
as 3000 lbm/sec of entrained liquid flows into the cell connected to the break during blowdown, there is almost no entrained liquid entering into that downcomer cell from adjacent cells to oroceed Further, Figure 1.c-2 prestats the out the break during reflood.
entrained droplet flowrates in the gaps connecting channel 56 and adjacent channels 55 and 57. The flow direction is into channel 56 in both gaps. Again, after the end of blowdown the droplet flow through these gaps is insignificant. For the reasons specified in the first paragraph, downcomer entrainment during reflood is not as important during reflood for AP600 as it is for 3/4 loop plants.
DRAFT l
l i
l l
AP600 BELOCA CAD CASE 0: MERGE OF NSAPLOT FILE u20 rEv 55 1 3 ENT axial vass rt:n
--- rEv 55 2 0 ENT axial VAss :_:n
--- TEM 55 3 0 ENT Ax.AL VAs5 03 3000 \
i i
)
1 m s N
~
'/ t l
E 2000 ' t ,3 ;Ig n s l
- - i t, \
v i lf .
1
,\
\
- 1
-i
! o ~
I l \ I\
l c 1000 I,1 Y, ' ' ,
I f i i l
- 3
- -
ti s l o- ~
l i
\\
l
_ l w - l l l m 0 i ,,, f<
- j. U -
\ y
%I ,
O \ l
~
E
\*\
I
/
1
-1000 80 10(
0 20 40 6'O Iime (S)
Gkrouse l(A Fiwoee- /
1
~
DP_ AFT flGGBE- f C-L AP600 BELOCA CAD CASE 0 MERGE OF NSAPLOT FILE u20 l WEM 56 3 0 GAP ENT FLOW RATE :
0 GAP ENT FLOW RATE l
MTH00006 55 2 1500 1000 i;
^
m I 'i s
,O N -
i i .
E i i o -
i i
~
i I i 1 500 I y
e l
- _ i t o
I l Il M
^
l\,
i i su o 0 ,
' '.gr --
~
4 L_
^
t cn 1 o _
E
-500 ,
i 1
-1000 80 100 120 140 20 40 60 Iime (S)
1 4
R 7 3 -
"?j
" ' ~
g 1 % 4 (a 3^1 1.d. The attached Figures 1.d-1 and 2 depict the flow in the two !
hot legs at the junction of the vessel outer global channel during f
- the AP600 blowdown. Early on, within the first second following l
the break, flow in the intact loop hot leg reverses and proceeds 4- into the vessel. During the remainder of the 35 second blowdown, !
any liquid flowing at the intact loop hot leg / vessel junction flows into the vessel. During the initial seconds of the transient, the influx of liquid from the intact loop hot leg (Figure 1.d-1) into the upper plenum is far less than the flow through the broken loop I
! In the first second, liquid and entrained hot leg (Figure 1.d-2). '
droplet flow into the outer global channel from the inner global channel through gap 58 contributes most of the rest of the large flow that feeds the break through the broken loop hot leg (Figure 1.d-3). The flow through both levels of gap 58 is frem inner to j outer global channel during the blowdown.
In the five to six'second time frame, a portion of the influx from a
the intact loop hot leg enters the core as a downflow into the l peripheral or guide tube fuel assemblies (WCAP-14171, This is apparent Revision from Figure 1.d-4,1, Figures 2. 2-3 4 ar.d 2. 2 -3 6 ) .
the liquid flow c.t the elevation of the bottom of the hot leg in ,
outer global channel #61. During the first few seconds the mass l initially present in this channel drains. The inflection in the increase of l channel 61 downflow observed at 5-6 seconds is the net :
- approximately 700 lbm/sec being provided by the intact hot leg. !
Shortly after six seconds, the broken loup hot leg flow from the j-vessel once again exceeds the flow into the upper plenum from the
' broken loop hot leg, and the flow inflection in Figure 1.d-4 ends.
j Beyond 12 seconds, the liquid flow from the intact loop hot leg is in-part predicted to enter the core, and in part proceeds out the broken loop hot leg as liquid and entrained droplets. This pattern 4
continues until the liquid flow in each of the hot legs diminishes i
to'a small value approximately 18 seconds into the transient.
Note the discussion on page 2-8 does not state that ALL the upper head fluid draining into the upper plenum proceeds into the core.
' Some of this upper head fluid also becomes part of the liquid and i .' entrained. droplets passing from inner to outer global channels and leaving the upper plenum out through the broken loop hot leg in the 5-12 second time frame. Overall, approximately one-fourth of the l
i upper head fluid draining into the upper plenum during this time
- interval exits through the broken loop hot leg. The possible uncertainty associated with upper plenum flow split is addressed in i
two ways. First, a sensitivity case is performed to identify the worst break location relative to the pressurizer, and the limiting
- location becomes the basis for the SSAR spectrum. Also, variation of the parameters in the global model matrix performed for the AP600 SSAR will impact the flow split of liquid from the upper 4
plenum. Together, these studies address the uncertainty in the upper plenum flow split by varying the loop parameters which determine the relative flow between the core and the hot legs.
)
3
.. n m.
} .
k Tmin=800F. WITH PXS AP600 LSLOCA AC/T CAO vessel CASEPlenum Uppger 0: DECLG. to HotC0=0.8. Legs Flows A Flows - Blowdown F i g u r e id -l j u.v 59 2 0 GAP .0 _:n RA I
____ gy 59 2 0 GAP ENT " .' O 'N 9,A
- 5
. . . ugy 59' 2 0 GAP VAP FLON RA~E 1000 i l
^
en .. . . -
l N 0 '
E -
o , ,
-1000 f
as c -2000 -
c:: I, l m !
-3000
. W _
Cn -
cn -4000
-o
~
'2 -
i
-5000 20 30 40 10 Tim 8 (S)
. - . . .- - . .. .. . . . . - . . ~ . . - - - .. .,
. DD s . r. a i
- \ T l
AP600 L9LOCA WQ/T CAO CASE Oi DECLG. C0=0.8. Tmin=800F. WITH PXS Figure f d- J._l Vessei Upper Plenum to Hot Leg 8 (Brook) Floss-Blowdown n.v 53 2 0 GAD L Q r';N RA E
NEV 60 2 0 GAP ENT .ON RA*E .. '
i NGM 60 2 0 CAP VAP FLCu RA E 14000 m
4 m 12000 N f !
, E L
-Q 10000 -
~_ _
1 8000 -
c; i ..
i o 6000 -{
0::
- 4000 o _
u -
, 2000 - .
m - I ,s m .s
_,i
~~~~- _-- ~-
o 0
)
2 -
-2000 40 00 O 10 20 30 Time (S) 4 J
9
-- .. .= - - . _ _
& 7 .T - ~ /t i
, l I * ,
l !
l
\
fg y[E=. f.Cbb AP600 BELOCA CAD CASE 0 MERGE OF NSAPLOT FILE u20 l l WLM 58 2 0 CAP L10 FLOW RATE i ----WLM 58 3 0 GAP LIO FLOW RATE l
WEM 58 2 0 GAP ENT FLOW RATE j
--- WEM 58 3 0 GAP ENT FLOW RATE i
[
10000 i
_ i L
i 1
. 8000' i
- _1 m i
-t N j E 5
_a 5
__ 6000 ;
v _
t
\
- \
\
g -
\
' I o 4000 g s .
t 3: -
g o -
' 2000 s
~
\
m
. g W _
'm u
o %
% '~'='
2 -
, ,,__,3,, , .e ._,
' ~ ^ --
0 m
-2000 6 8 10 0 2 4 Time (S)
DD.?. _ ,,,\ ;G rauzz /,& F AP600 BELOCA CAD CASE 0: MERGE OF NSAPLOT FILE u20 FLM 61 1 0 L10 AXlAL MASS FLOW 6000 M
4000 4
^
U3
\
E
.a 2000 e , _
w D ^
T k
G I VY
- f !
w U3 D -
2 .
l
-2000 l I
-4000 40 50 0 10 20 30 IIme (S)
.. e i .
, DRAFT
- . 01rs4sse i
l.e. Liquid downflow at the top of the core does not contribute to AP600 core cooling during reflood. Attached are figures which show the liquid, entrained droplet, and vapor flows. predicted at the core outlet during the WCAP-14171, Revision 1 Section 2.2 DECLG break case for the hot assembly, guide tube, open hole / support I column and peripheral channels. The figures show that during the
- ) reflood, through the time of core quench, no significant downflow exists in any of the channels, except the peripheral channel. For the low power peripheral fuel channel, .the downflow calculated ,
,! begins almost 90 seconds into the transient, well af ter the reflood l phase PCT has occurred. Therefore, core countercurrent flow during 4
reflood is unimportant and need not be included among the ranked
- phenomena. ;
1 4 1 t' I l
j D
a
DRAFT l
C0=0.8. Tmin=800F. WITH PXS AP600 L8LOCA WC/T CAO CASE 0 DECLG.
l I F i g u r e/p/s Core Hot Assembly Channel Outlet Flows (Reflood)
CLV 27 15 0 LIQ AXIAL VASS FLOW
FEV 27 15 0 ENT AXlAL MASS FLOW l- ----FGM 27 15 0 VAP AXlAL VASS FLOW l 10 P
+
I i
^
w h 6 q
\
N -
r E 5 I l
.c
- \ t v _
_ i 0
- T '
$\h )% % ~ }-! =
K []
o 0 1 _
/, .
i R -
I o -
t i
I I
L -
I I
,m -5 g m -
)
o _
JE
-10 120 140 40 60 80 100 Time (S) l g.
1..
DRAFT I i
, i Tmin=800F, WITH PXS AP600 L8LOCA WC/T CAO CASE 0: DECLG. CD=0.8.
F i g u r pgl C o r e OutIet FIows (Guide Tube ChanneI)-RefIood F :_ v 26 15 0 L10 AXIAL MASS FLOW
FEM 26 15 0 ENT AXIAL MASS FLOW
- --- FGM 26 15 0 VAP AXIAL MASS ~ LOW ,
1000 ;
- ~
j
~
n m 800 x _.
E _
^ _
1 i I v 600 c,
~
i
\ \
l
}
c 400 oc _
f 1 .-
C
~
l ; I I
200 ,
t i I i u_ _
~
w "W' \ g e ,\ , I,,' } q ' s ~ ~ ' ' f[ ,r3% , .._ ,, , , .
\
f .
y l' o 0 - - ,v 3
s t y
s _
(i {,
I
-200 80 100 120 140 40 60 Time (S)
i.
% 3) A "[ t w > 2 .,"
AP600 LBLOCA WC/T CAO CASE 0: DECLG. C0=0.8. Tmin=800F. WITH PXS F i g u r e/4 3,'C o r e Outlet Flows (0 pen Hole / Support Column Channel)-Reflood FLM 25 15 0 L10 AXlAL MASS FLOW
FEM 25 15 0 ENT AXIAL MASS FLOW
-.-.- - FGM 25 15 0 VAP AX!AL MASS FLOW l
l 1000 i
~
1 m 800 N -
E - -
_a
(
v 600 I
ca {
~
o 400 I ,
cr _
I i
i ic k o -
( 1 200 '
~ -
t
~
m
,i.
m ~l y py ,,, , \ j \.I4! 16*~^"" p)3 ,s, gj. , A m ,} fM f h o 0
- lE _
-200 120 140 40 60 80 100 Time (S) :
1 I
l 1
i i
l .
l .*
l
- ).. A' r l
AP600 L8LOCA WC/T CAO CASE 0: DECLG. CD=0.8. Tmin=800F. WITH PXS F i g u r e/W;C o r e Outlet Flows (Peripheral Channel)-Reflood FLM 24 15 0 LIQ AXIAL VASS FLOW
FEM 24 15 0 ENT AXIAL MASS FLOW FGM 24 15 0 VAP AXlAL MASS FLOW .
1000 16 Z
\ ~
E 500
.a v _ ,
i o \
l_ u s A t- L s < - - - ~/$ . .
e _ W t
O ~
k I
w _
l m -500 I l[ r}'
v g l
\
m _
O -
{ l
- E t{
~
I l 8
-1000 100 120 140 40 60 80 Iime (S) i 1
4*
- g -*=g
- :w 'j'L ' Clf fh Y$kh 2.f. The liquid level oscillations observed in the WCAP-14171 and AP600 SSAR WCOBRA/ TRAC analyses in the core and downcomer regions are those associated with the introduction of water into a hot fuel bundle. As cold water quenches the fuel rods, steam generation pressurizes the core region, the core level drops and the downcomer level rises for a short period; then, water flows in again from the ,
downcomer, and the cycle repeats. This predicted behavior is the '
same as that observed in FLECHT and other reflood heat transfer tests.
In the AP600 SSAR bounding parameters to minimize accumulator flow delivery and therefore downcomer level at any point in time are modeled: minimum gas pressure, maximum water volume,. maximum flow resistance in the inj ection flow path. This. approach penalizes the downcomer filling. rate and level relative to a best estimate value at any point in time during the large break LOCA transient. This follows the conservatism in the ECC bypass calculation, which initially penalizes the downcomer level. As a result, the possible level oscillations which could be calculated are suppressed and exert less of an effect on the cooling of the upper regions of the core. Another possible effect of core level oscillations would be large changes in core heat transfer during the reflood transient.
The AP600 cladding temperature transients during the' reflood. phase of the SSAR cases.are smooth. Because flow oscillations predicted by WCOBRA/ TRAC correspond to those expected for gravity reflood, and the liquid present in the reactor downcomer is calculated in a bounding, conservative manner, and the calculated PCT transients are well-behaved in the SSAR cases, the uncertainty associated with the calculation of core flow oscillations is covered"for the AP600 SSAR large break LOCA analysis.
4 4
e 4-a INFORMATION PROVIDED TO JOE SEBROSKY May, 20,1997
Subject:
OITS #1652 (RAI 480.80) Draft marked-up PRA pages JOE PLEASE PROVIDE A COPY TO BOB PALLA cc: Jim Scobel l Brian McIntyre
- Per our AP600 OITS Level 2/3 PRA status telecon on May 16,1997, Westinghouse agreed to change the Westinghouse status column of OITS #1652 (RAI 480.80) from Closed to Action W. De Westinghouse action is to provide a revision to PRA Chapter 39 to fix an incorrect statement.
Attached to this correspondence are the marked-up PRA pages associated with this action, Please review and inform Westinghouse if this satisfies the staff's concern.
. Dese marked changes will be incorporated into Revision 10 of the AP600 PRA. Since the Westinghouse action is being addressed via the attachment, and the information will be incorporated into the next revision of the PRA, the Westinghouse status column of OITS #1652 will be changed to "Confrm-W". Please inform Westinghouse of what the NRC Status column should be for this open item.
D anks.
(5 M Cynthia Haag 412-374-4277 4
e l
I l
1
s.
- 39. II Vessel Retention of Moltes Ccre Debris 3
' (.sh l 1
I head is greater than 45 minutes after initiation of rapid oxidation in the core. The top of the I reactor vessel hemisphere is at the 83' elevation in the containment (reactor cavity floor I elevation is 71' 6"). Herefore, to meet the first criterion, the water level must be greater than l 1 the 83' elevation within 45 minutes of the rapid core oxidation. t o
1 Full relocation of core debris after core support plate slump occurs more than 75 minutes after ' !
I initiation of rapid core oxidation. The height of the core debris and the uncertainties in height k )
I are discussed in Chapter 7 of Reference 39-1. Maximum debris pool depth is 2.8 meters in 8 I the lower head. His depth corresponds to a containment elevation of approximately 86', '
l Therefore, to meet the second criterion, the water level must be greater than the 86' elevation 3 I within 75 minutes of rapid core oxidation. Based on this elevation, core makeup tank (CMT) ]
I water and accumulator water alone are not sufficient to prevent vessel failure, and the in- j l containment refueling water storagt. tank water must be drained into the floodable region of I the containment to achieve wate cooling of the reactor vessel. W k
l The success criteria are summarized as follows:
=
I Cavity water elevation greater than 83' within 45 minutes of rapid cladding oxidation 4
, I
- Cavity water elevation greater than 86' within 75 minutes of rapid cladding oxidation e 4
I 39.4.1.2 Manual Action Success Criteria .p I De operator action to flood the cavity is determined in Emergency Response Guideline %.
[' ~
I (ERG) FR.C-1, which instructs the operator to flood the reactor cavity dca 0.c cercw y l ,
ee r- pb . ' 2^^^*F er containment radiation reaches levels that indicate fission-I product releases as determined by a core damage assessment guideline. He high core-exit I temperature and containment radiation levels coincide with rapid core oxidation.
I Flooding rates for one and two cavity flooding lines open are presented in Figure 39-7. With I one flooding line open, the 83' elevation is reached within 20 minutes of opening the valves I and the 86' elevation is reached within 40 minutes. At least 25 minutes are available for the I operator to open the cavity flooding valves after rapid core oxidation signals the need for I cavity flooding. Water in the cavity prior to the operator action is conservatively neglected.
I ne criterion used for operator action to flood the cavity is the manual opening of at least 1 i of 2 cavity flooding lines within 20 minutes of rapid core oxidation as evidenced by very high I core-exit thermocouple readings or very high containment radiation readings.
. I 39.4.1.3 Limited In-Vessel Debris Relocation 1 In accident classes 3A, recovered anticipated transient without scram (ATWS) sequences with I success at node DP, and depressunzed 1 A and 1 AP, core damage is limited, no significant I debris relocation to the lower vessel is predicted, and the reactor vessel remams water filled.
1 In these cases, success is credited at node IR since there is no molten core debris in the lower I head.
Revision: 8 3 W8Stillgh0088 September 30,1996 39-5 =W%*_reec39.wpf:lt492296
l s i
- 35. Containment Event Tree Analysis I
l m l
./ ]
l l Post-Core-Uncovery Cue for Operator Action: ERG E-0 entered at reactor trip or safety I injection signal l Successful contamment isolation determines initial containment integrity. If the containment !
l l is not isolated, the result is a fission-product release to the environment from the initial stages 1 I of core damage. The containment is isolated by the protection and safety monitoring system !
I or by the operator at step 5 in the E-0 ERO. Containment isolation is required before the !
I accident conditions exceed the design basis after core uncovery. The time available prior to l l significant fission-product release for the operator to isolate the containment is approximately j l I hour (Reference 35-4), except in the 3A, 3BR, and 3C accident classes, in which core l
I damage occurs relatively quickly due to inability to reflood the vessel. In accident classes 3A, '
. l 3BR, and 3C, only automatic contamment isolation is credited.
l Equipment survivability of the contamment isolation system is covered under the design-basis I I equipment qualification program. A fault tree evaluating hardware and operator success is I linked to top event IS to quantify success of contamrnent isolation.
I 35.7.3 Top Event IR - Reactor Cavity Flooding l Nodal Question: Is the in-containment refueling water storage tank water level in the reactor I cavity sufficient to submerge the reactor vessel above the elevation of the in-vessel core I debris?
I Success Criteria: 2 of 2 valves open in 1 of 2 recirculation lines from the in-containment I refueling water storage tank to containment sump or in-containment refueling water storage .
I tank injection through the progression of the accident l Severe Accident Phenomena Addressed: Reactor vessel integrity I 1 Actuation: Automatic or manual l
'[ Post-Core-Uncovery Cue for Operator Action: ERG FR.C-1, m, h;,,h ww; ;cirti l -ee very high containment radiation i The basis for in-vessel retention (IVR) of molten core debris in the AP600 is the l DOE /ARSAP report (Reference 35-1) on IVR. Success of IVR is demonstrated if the outside I of the reactor vessel is submerged in water at least to an equivalent elevation as the in-vessel l molten debris pool. The cavity water level must be at least to the 83' elevation within l 45 minutes and at least to the 86' elevation within 75 minutes after core damage. He l
I b[ operator determines r= d L..gn ; or verythat highthe cavityinneeds radiation to be flooded the containment. in ERG FR.C-1 He required based elevations for on w, hl L
- I successful flooding are based on covering the entire hemispherical portion of the lower head ,
I before the earliest time of debris relocation to the lower head (Appendix P of Reference 35-1)
I and covering the maximum estimated depth of molten core debris before the failure of the I support plate into the lower head. Failure at node IR is conservatively assumed to result in
- am +c re c ove r Rts .gW em ---
Sep r 30,1996 Westingh00S8 mspaxynwv_ruc35.wpt;ib 35-14
^
< n.
[
In l Table 35-6 0 8
l
SUMMARY
OF OPERATOR ACTIONS CREDITED ON CONTAINMENT EVENT TREE o
l Top Time P.
l Event Description of Operator Error Event ID Cue (s) Window M E
l DP Failure te recognize need for post-core-uncovery RCS LPM-REC 01 core-exit T/C > 1200*F 20 minutes Q
l depress during small LOCA or transient with loss of PRHR (ERG FR.C-1) g l Failure to complete ADS as recovery from failure of ADN-REC 01 core-exit T/C > 1200*F 20 minutes I automatic actuation or manual actuation after core damage (ERG FR.C-1) fr g
g l IS Failure to recognize need and failure to isolate the CIC-MAN 01 high containment pressure, 60 minutes l containment, given core damage following an accident high containment I temperature, high I containment radiation
- v. l (ERG E-0)
Y
@ l PC Failure to recognize need and failure to open PCS water PCN-MAN 01 high containment pressure 60 minutes I valves to drain cooling water on containment shcIl (ERG E-0) l 1R Failure to recognize need and failure to open recirculation REN-MANO3 high containment radiation, 20 minutes I valves to flood reactor cavity after core damage -bigh-core-exit temperaturg I (ERG FR.C-1) (>gzovF l IG Failure to recognize need and failure to actuate hydrogen VLN-MAN 01 core-exit T/C > 1200*F 15 minutes p l control system, given core damage following an accident (ERG FR.C-1)
\ l o b I
n r.s =a
.g e g 2- '
.Ws-C3 ll.
..D
@1
y ! Wirters, James W.,02:35 PM 5/20/97, My Notes from Fire Protection I 1
From: " Winters, James W." <winterjw@ westinghouse.com> l To: "McIntyre, Brian A" <mcintyba@wesmail.com>,
"Vijuk, Robert M."
<vijukrm@wesmail.com>,
"Cummi " <cumminwe@ westinghouse.com> l Cc: " - ..." gs " <winterjw@ westinghouse.com>, j Hutchings, Donal F." <hutchidf@ westinghouse.com>, l
- "'dtj @ nre. gov'"
<dtj@nr ov>, "'tjk2 @ nrc. gov'" <tjk2 @ nrc. gov >
bject: My N rom Fire Protection Meeting Da ay 199714:35:44 -0400 j X Priority: 3 !
He.:e are my notes from the Fire Protection meeting we had with NRC on 4
- l
_ May 19,1997. NRC had West, Kenyon, Quay, Marsh, Holmes, Connell and George Thomas. We had Hutchings and me.
We first talked about Items I and 2, the philosophical difference on how to treat " normal" shutdown systems. We have received each others positions on die subject and believe we understand the other's position. l Westinghouse presented an opinion that GFJABWR was judged the same way that Westinghouse is requesting. NRC stated that GE was different in that it has an inerted containment and that 60% of their safe shutdown j systems are also their " normal" shutdown systems. Westinghouse stated that these two items were irrelevant to the fundamental issue of do we license AP600 in accordance with operating plant, Appendix R precedence or in accordance with explicit BTP 9.5-1, GFJABWR precedence. We (NRC
- and Westinghouse) disagree. Next step is to bring it to Mr. Collins.
T. stinghouse has the action to request this next step. We need to ,
precisely define the question for Mr. Collins. We agreed to share i presentation materials with each other before meeting with MR. Collins j to avoid " surprises." j NRC completed their separation in containment review and have written a position letter. It will be issued in the near future. NRC provided a copy of the letter's attachment which indicates which fire zones have inadequate explanation of redundant equipment separation.
NRC completed their smoke control review and have written a position letter. It will be issued in the near future. NRC did not provide any written information at the meeting but did offer some general guidance.
Portable exhaust fans and ductwork and not acceptable per NFPA-204M, NFPA-92A, SECY-90-016 and c.5.f of Appendix R. For areas with normal ventilation, we must show that the system is capable and available for removing smoke. We need to specify smoke removal methods for stairwells and elevator shafts. We need to better address pressurization of spaces adjacent to that with the fire.
Key Issue #12 should be redefm' ed with the current items in lieu of the 4 in the original Key Issue letter.
Printed for " Brian A. McIntyre" <mcintyba@wesmaii.com> (( ~il
- ~
J
'f 4
k i l
i
, Item 4 - We need to include in our description of the normal source of
. fire suppression water for the clean aux., the time it takes to open the
]
l valve to the main fire main.
4 ,
Item 6 - We need to include a discussion of explosion hazards.
- Items 7 & 8 - These are comments on the example markups we provided two
] weeks ago.
~
4042AF01 - Delete " equivalent fire duration". Replace with " light fire hazard," " barrier provided adequate separation," and the like.
Describe where in the room the cables run and relate them to the fire protection features of the room.
j IEEE-383 does not apply to cables any more. We should have referenced j
- . IEEE-1202. l 1250AF01 - We didn't address ventilation adequately. We should use
" light" or "high" hazard and not " equivalent fire duration." For example,50 pounds of gas is a different hazard from 50 pounds of gas.
I100AF206 - need more information on the temperature of entering gas and i the environmental qualification requirements of equipment in the area.
The hot gas jet may be at 1500 F. we need to show it is cooled down to what and why we are making the judgment that all is OK.
4 Gypsum vs. Masonry walls around stairways - We need to say how we j protect against missiles, both equipment generated and explosion l generated and request a deviation from the BTP.
t NRC will get back to us on: QA issues forTechSecs, Admin Controit,
. shutdown operations including compliance with NuReg 1449,if required.
t Westinghouse promised to provide answers to position letters by the end 3
of May.
Our next meeting is tentatively scheduled for the week of June 9 in 2
Monroeville.
f Jim
- 412-374-5290 i
i i
t Printed for " Brian A. McIntyre" <mcintyba@wesmall.com> _i _ [2]
r
Lindgren, Donald A.
i'
' From: Lindgren, Donald A.
7: Sent: Monday, May 19,1997 5:03 PM To: 'Kenyon, Tom' Cc: Orr, Richard S.: McIntyre, Brian A; ' Jackson, Diane'
Subject:
Site and Structural Open item Resolution 3
Tom, We need to set up a meeting to discuss the remaining ECGB issues. We expect to provide open item and RAI
, responses and SSAR revisions by May 30. In anticipation of this, we would like to block out some time mid to late June to have a meeting to complete resolution of the remaining items.
. One of the areas of interest is the site parameter related issues. These include issues related to the difference
!* between site parameters and interface requirements. . Also RAls 231.35 through 231.42 need to be responded to.
We will have the RAI responses and a related markup of SSAR Section 2.5 sent in by the end of the month.
The other area of interest is the remaining structural issues. These include the effects ofload changes on the shield building roof. These changes include live load, snow load, and an increase in the water mass. A significant number of open structural questions are related to the shear wall design and how the walls tie into the basemat.
The meetings should probably be in Monroeville since the staff will likely want to review some of the analyses.
I will be in the meeting on hydrogen control on Tuesday so leave me a message or I will talk to you on Wednesday.
Don Lindgren Page 1 3 i
I j
. _ _ - - _ .- . _ , . . . - ._ - - - ~ . _
Winters, James W.,01:13 PM 5/20/97, RE: Thursday's List of Things l From: " Winters, James W." <winterjw@ westinghouse.com>
To: "Alfieri, Elizabeth M." <allierem@ westinghouse.com>, ,
"Andreychek, Timothy S." <andreyts@ westinghouse.com>, i "Bachrach, Uriel X." <bachrach.u @mts400.pgh.wec.com>, I
" Drown, William L." l
<brownwl@ westinghouse.com>, i "Bruschi, Howard J."
<bruschhj@ westinghouse.com>, 1 "Bueter, Tim W." l
<bueteltw@ westinghouse.com>,
" Canton, Mike H."
cIMCEAEX _O= WESTINGHOUSE _OU= HUB _CN= LEGACY +20 MAIL +20 RECIPIENTS _CN= CANTON +2EM
+2EH @ westinghouse.com>,
"Carlin, Edward L." <carlinel@ westinghouse.com>,
"Carlson, William R."
<carlsowr@ westinghouse.com>, I
" Chase, Wayne L." l
<chasewl@ westinghouse.com>, l "Conway, Lawrence E." )
<conwayle@ westinghouse.com>,
"Corletti, Michael M."
<corletmm@ westinghouse.com>,
"Cummins, Ed" <cumminwe@ westinghouse.com>,
"Delose, Frank" <delosef@ westinghouse.com>,
"Deutsch, Kenneth L."
<deutsckl@ westinghouse.com>,
"Fittante, Randy L."
<fittante.r.1 @ mt s400.pgh.wec.com>,
" Flanders, Ruth M."
<flanderm@ westinghouse.com>,
"Forgie, Alexander"
<forgiea@ westinghouse.com>,
" Fowler, Stephen B."
<fowlersb@ westinghouse.com>,
"Freeland, Jim M." -
<freeland.j.m @ mts400.pgh.wec.com>,
"Cagnon, Andre F "
<gagnon.a.f@ mts400.pgh.wec.co m>,
" Garner, Dan C."
<g arner.d.c @ mts400.pgh.wec.com>,
"Gresham, James A."
<greshaja@ westinghouse.com>.
"Grover, James L."
<1MCEAEX _O= WESTINGHOUSE _OU= HUB _CN= LEGACY +20 MAIL +20 RECIPIENTS _CN=GROVER+2EJ+
2EL@ westinghouse.com>,
" Haag, Cynthia L." <haagel@wesmail.com>,
"Haessler, Richard L."
<haessirt@ westinghouse.com>,
"Halac, Kent E."
<halac.k.e@mts400.pgh.wec.com>.
Printed for " Brian A. McIntyre" <mcintyba@wesmail.com> [~ ll
,9
)
" Hayes, Thomas P "
<hayestp@ westinghouse.com>,
"Hellested, Rhonda L."
<hellestl@ westinghouse.com>,
" Hicks, William W," ;
<IMCEAEX _O= WESTINGHOUSE _OU= HUB _CN= LEGACY +20 MALL +20 RECIPIENTS _CN= HICKS +2EW+2 EW@ westinghouse.com>,
" Howe, Kirk S." < howe.k.s@ mts400.pgh.wec.com>,
! "Hughes, Janice W "
l <hughesjw @ westinghouse.com>,
! "Hutchings, Donald F."
<hutchidf@ westinghouse.com>.
"Israelson, Gordon A."
<israelga@ westinghouse.com>, i "Jakub, Robert M."
<jakubrm@ westinghouse.com>,
"Kaushansky, Mark" l
<IMCEAEX _O= WESTINGHOUSE _OU= NORTH-AMERICA _CN=MICROSOFT+20 MAIL +20 RECIPIENTS _C N=KA US HAM 654080C9 @ we sti nghou se.com>,
"Keaney, Susan L." <keaneIsl@ westinghouse.com>,
" Keeler, Robin M."
<keelerrm@ westinghouse.com>,
"Kemper, Robert M."
<ke mper.r.m @ mts400.pgh.wec.com>,
"Kerch, Steve P."
<IMCEAEX _O= WESTINGHOUSE _OU= HUB..CN= LEGACY +20 MAIL +20 RECIPIENTS _CN=KERCH+2ES+2 EP@ westinghouse.com>,
"Lindgren, Donald A." <lindglda@ westinghouse.com>,
"Loftus, Michael J."
<loftusmj@ westinghouse.com>,
"Lovato, Janet M."
<lovatojm@ westinghouse.com>,
"Mahlab, Moshe" <mahlabma@ westinghouse.com>,
"Mandava, Rao" <mandavpr@ westinghouse.com>,
"Mankowski, Michael H."
<mankowmh@ westinghouse.com>,
"Mazon, Mary E." <mazonme@ westinghouse.com>,
"McDermott, Daniel J." <medermdj@ westinghouse.com>,
"McIntyre, Brian A"
<mcintyba@wesmail.com>,
'"Mcnamee, Kevin F."
<menamee.k.f @ mts400.pgh.wec.c om>,
"Miele, Kellie E."
<mieleke@ westinghouse.com>,
"Millslagle, Tom C."
l <IMCEAEX _O= WESTINGHOUSE _OU= HUB _CN= LEGACY +20 MAIL +20 RECIPIENTS _CN=MJLLSLAGLE+
! 2ET+2EC@ westinghouse.com>,
" Morgan, Dale G." <morgandg@ westinghouse.com>,
"Nissley, Mitch E."
l <IMCEAEX _O= WESTINGHOUSE _OU= HUB _CN= LEGACY +20 MAIL +20 RECIPIENTS _CN=NISSI.EY+2EM Printed for " Brian A. McIntyre" <mcintyba@wesmall.com> 2l
s.
I "J l
+2EE@ westinghouse.com>,
"Novendstem Earl H." <novendeh@ westinghouse.com>,
"Nydes, Robin K." I
<nydestk@ westinghouse.com>, l "Ofstun, Richard P" l
<ofstunrp@ westinghouse.com>, I "Ohkawa, Debra K." I
<ohkawadk@ westinghouse.com>, I "Orr, Richard S." <orrrs@ westinghouse.com>, !
"Osterrieder, Robert A." <osterrra@ westinghouse.com>,
"Piplica, Eugene J." <piplicej @ westinghouse.com>,
"Rarig, Bruce E."
<rarigbe@ westinghouse.com>,
"Rosenthal, Philip W."
- <IMCEAEX _O= WESTINGHOUSE _OU= HUB _CN= LEGACY +20 MAIL +20 RECIPIENTS _CN=ROSENTHAL+
2EP+2EW@ westinghouse.com>,
. "Rowell, Timothy D." <rowelltd@ westinghouse.com>, j i "$ancaktar, Selim" I i <sancaks@ westinghouse.com>,
i "Scherf, Dave E."
<scherf.d.e @ mts400.pgh.wec.com>,
a "Schreiber, Roger B."
<schreirb@ westinghouse.com>,
i "Schulz, Terry L." l
< schul 7tl@westin house.com>.
o , es H."
<scobe 'h@ westinghouse.co >, "Sloane
. Cc: "'trq@nrc. gov'" <trq@nrc. gov >,
l "Vijuk, Ronald P."
<vijuktp@ westinghouse.com>
" Winters, James W."
<winterjw@westin se.com> l
Subject:
TimMon ust of Things We Owe NRC Date: Tue,20 May 199713:13:09 -0400 X-Priority: 3 p This is status as of last Thursday, May 15.
> To meet the SECY-97-051 scedule milestone of " Applicant Submits Final
> SSAR Revisions & Documentation" by 5/97, we believe that NRC must
> acknowledge receipt of all Westinghouse submittals by May 30,1997.
> This is just 11 calendar days away (9 business days).
> As a result, all open items need to be closed as soon as possible. We i > need to get NRC to acknowledge that they have received our input in
- > addition to our sending it out. So here's the list of who owes how
> many and how many NRC hasn't given you credit for. Please issue the
> ones we think we owe and get with your licensing engineer to get NRC
> to accept responsibility for the ones you've already sent out.
4 > Remember, until NRC says it is theirs, it is still yours.
Printed for " Brian A. McIntyre" <mcintyba@wesmall.com> _ 3l
a.
1 i
> Items We Owe
> We Say NRC Says
> Lindgren (13054) 1 6 ,
> Lindgren (13559) 0 2
> Lindgren (3.2 3) 4 4 Up2
> Bhowmick 1 2
> Bueter 0 14
> Winters (Butler) 0 5
> Canton 1 1
> Piplica (Chapter 14) 1 2 Downi
> Corletti 2 7 Up1
> Deutsch 9 9 i 0 l
> Nydes (ERG) 1
> Haag (FAI) 0 0 Down8
> Gresham 452 493 Up5 '
> Grover 6 5
> Gresham (H&MT) 20 21 1'
> Haag 5 8
> Hayes 2 3
> Hutchings - 1 3 Down5
> Israelson 4 6 Up4
> Schreiber(ITAAC) 1 6 Downi
> Jambusaria 0 1
> Ed Johnson 2 5
> Tupper(Kloes) 0 1
> Lindgren 2 23 Up1 l
> Nvndstrn (LOFTRAN) 0 0 Down1
> Gresham (LST) 2 2 -
> Lutz 0 2
> McDermott 7 10 Down2 l
> McIntyre 3 5 Upi
> Dick Miller 7 10
> Kerch (MMIS) 1 2 Up1
> Mahlab (More) 0 1
> Narula 0 5
> Novendstem 75 105
> Nydes 2 2
> Ohkawa 0 7
>On 21 45 Up tl
> Piplica - 103 123 Up 78
> Haag (PRA 1) 18 30
> Haag (PRA 2) 9 102 Down6
> Nydes (RAP) 0 1
> Rosenthal 0 4
> Rowell 0 8
> McIntyre (RTNSS) 8 18 Up1
> Novendstem (Ch 15) 68 68
> Gresham (Scaling) 10 11
> Schreiber 22 23
_ i[
~
Prinied for " Brian A. McIntyre" <mcintyba@wesmall.com> T . T T 24]
T g, 1
> Schulz 2 7 Up1
> Scobel 1 71 Down 25
> Hutchings (SCS) 0 1
>Nydes (Shutdwn Rpt )2 5 Down 13
> Lindgren (Singleton) 0 1 Downi Haag (SMA) 6 6 Up6 i
> Lindgren (SSARREV) 0 4 Down1 i
> Nydes (Sterdis) 0 1
> Suggs 0 2
> Nydes (TechSpec) 5 52_ Up3 l
> Haag (T/H Uncert) 22 22
> Nvndstrn (TRUMP) 1 29
> Ron Vijuk 2 2
> Wallace 0 4
> Gresham (Water) 3 3
- > Novendstern (WC) 0 1
> Novendstem (WCT) 66 66
> Gresham (WG) 22 22
> Willis 8 8
> Wills 1 28
> Winters 36 54 Down 17
> Woodcock 0 2
> Go get them out and resolved.
> Thanks
> Jim
> x5290
.> l l
_ _ Printed for Brian A. McIntyre" <mcintyha@wesniall.com> __ ___ _ . 5]
i Briaa A. McIrtyre,10:44 AM 5/19/97, Igniter power supply tech spec l Date: Mon,19 May 199710:44:04 -0400 To: jms3@nrc. gov, TRQ@NRC. GOV From: " Brian A. McIntyre" <mcintyba@wesmail.com>
Subject:
Igniter power supply tech spec l Cc: meintyba@wesmail.com, vijuktm@wesmail.com, fantosv
-Joe, In your April 3,1997 letter to Westinghouse concerning the AP600 hydrogen igniter power supply, you asked for a tech spec on the hydrogen control system based on operating experience at TMI and the precedent set on the System 80+. We would like to discuss that position to develop a better understanding of how that relates to the AP600.
Please be prepared to discuss that during our meeting tomorrow.
Brian A. McIntyre l
Bell 412.374.4334 WIN 284.4334 FAX Bell 412.374.4887 FAX WIN 284.4887 l d
3 l
Printed for " Brian A. McIntyre" <mcintyba@wesm' ail.com> 1l
I ._W $ 5tj[)8jggy$
r UdVER SHE5T l v
- l l RECIPIENT INFORMATION SENDER INFORMATION i
OATE:
TO:
A1A/ /l, /99 ;
NAME: jy gg '
p LOCATION:
ENERGY CENTER .
_/OA nFM/ cal EAST PHONE: FACSIMILE: PHONE:
Otsee: t/ft.37q.7t,3 l COMPANY: Facsimile: y,in:
284 4887
_ll 5 t/eC. outside: (412)374 48a7 LOCATION:
1 Cover + Pages 1+2 2
The fo!!0Wln9 Pages are balng sent from the Westinghouse Energy Center, East Tower, Monroeville, PA. If any problems occur during this transmission, please call:
WIN: 284 5125 (Janice) or Outside: (412}374 5125.
A COMMENTS:
loM .
h Aam z e, < 99 7 7Fteiai^4 rr w.u.co ,sTo dewi<,o /3 or rus nse u acer.s we hem. /;te !ka .
CC ', t A/ d L/t W ptx 4 e " ~~
Au diluti Ce <aJ (4hYO 3cAuvi 6ni(H t .
b.o
a
.g, q.
I. Introduction cad General Descriptios c.f P1rt Table 1.8-2 (Sheet 3 of 4)
SUMMARY
OF AP600 STANDARD PLANT COMBINED LICENSE INFORMATION ITEMS Item No. Sub. lect Subsection 6.4-2 Local Toxic Gas Services and Monitoring 6.4.7 6.4-3 Procedures for Training for Control Room Habitability 6.4.7 661 Inspection Programs 6.6.9.1 6.6-2 Construction Activities 6.6.9.2 7.1 1 Setpoint Calculations for Protective Functions 7.1.6 8.21 Offsite Electrical Power 8.2.4 ,
8.31 Onsite Electrical Power 8.3.3 9.1-1 Fuel Storage and Handling 9.1.6 9.51 Offsite Communications Interfaces 9.5.2.5.1 9.52 Emergency Response Facility Communications 9.5.2.5.2 9.5-3 Security Communications 9.5.2.5.3 9.5-4 Cathodie. and Erivironmental Protection for Fuel Oil Tanks 9.5.4.7 l
10.1 1 Erosion-Corrosion Monitoring 10.1.3 10.2-1 Turbine Maintenance and Inspection 10.2.6 10.4-1 Circulating Water Supply 10.4.12.1 10.4-2 Condensate, Feedwater and Auxiliary Steam System Chemistry Control 10.4.12.2 10.4-3 Potable Water 10.4.12.3 11.2 1 Liquid Radwaste Processing by Mobile Equipment 11.2.4.1 l
11.2-2 Cost Benefit Analysis of Population Doses from Liquid Effluents 11.2.4.2 11.2-3 Identification of Ion Exchange and Adsorbent Media for Liquid Radwaste 11.2.4.3 l
11.2-4 Dilution and Control of Boric Acid Discharge 11.2.4.4 11.3 1 Cost Bene.. Analysis of Population Doses from Gaseous Effluents 11.3.4.1 11.3-2 Ident.eation of Adsorbent Media for Gaseous Radwaste 11.3.4.2 11, l-l %Iid Waste Management System Process Control Program 11.4.6 11.5- Plant Offsite Dose Calculation Manual (ODCM) 11.5.7 a t I . 5- t- CHIsu4 n w S wa Sa4to o II .s. 7 "12.1 1 ALARA and Operational Policies 12.1.3 12.2-1 Additional Contained Radiation Sources 12.2.3 12.3 1 Administrative Controls, Criteria and Methods for Radiological Protection 12.3.5 ll 5*- 3 Io c Fe 50, And1 T gg , g, 7 Revision: 12 April 30,1997 1.8-12 3 Westingt)0use
I 11. Radioactive Waste Manag:me:t l
( 11.5.6.4 Quality Assurance l The quality assurance program for design, fabrication, procurement, and installation of the !
I radiation monitoring system and radiation monitors from other systems is in accordance with I the overall quality assurance program described in Chapter 17. ;
i 1 11.5.7 Combined License Information The Combined License applicant will develop an offsite dose calculation manual that contains (
l the methodology and parameters used for calculation of offsite doses resulting from gaseous and liquid effluents. The Combined License applicant will address operational setpcints for !
l the radiation monitors and address programs for monitoring and controlling the release of l
udioactive material to the environment, which eliminates the potential for unmonitored and i l une o release. The offsite dose calculation manual will include planned discharge flow ra s. Combined License applicant is responsible for the site-specific and program aspects process and effluent monitoring and sampling per Regulatory Guides 1.21 and 4.15. l
! e Combined License applicant is responsible for addressing the 10 CFR 50, Appendix 1 A Ti guidelines for maximally exposed offsite individual doses and population doses via liquid and gaseous effluents.
l l
\ !
l i
i l
i Revision: 12 April 30,1997 11.5 18 W Westingh0tlSe l
f I l
,i :
s
. WESTINGHOUSE ELECTRIC CORPORATION l
k PO BOX 355 PITTSBURGH, PA 15230-0355 l
ADVANCED PLANT SAFEiY AND LICENSING FAX NO: 412474-4887 (W1H 284) i i CONF 1RMATION NO: 412 474-4237 l l
l i DATE:
! TO: So #P LOCATION: A/E O t
owpa /o & Pc
!- FAX NUM8ER:
! FRosa: Brian A. McIntyre
, PHONE: WIN: 284-4334 4 BELL: 412-374 4334 l l
NUMBER OF PAGES (INCLUDING COVER SHEET):
1 COIAAENTS / MESSAGE:
i 4
4
i .
1 May 13, 1997 ,
1 A draft of this meeting summary was provided to Westinghouse to allow them the opportunity to ensure that the representati 4 of their comment nd discus-sions were correct. 1 I
g o ph M. Sebrosky, Pro e t Manager fStandardizationProjectDirectorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.52-003 Attachments: As stated cc w/ attachments:
See next page Vf7tf.9'?
Th %
% x-c+~~ &%A~
h>hrmaAmeSSn %
&,nm Ai Wm. L A"~% \
>h Ntr c h<amsea.i L. d~~
g,,. A o, Op d% Go- r.'. h6/ ;
N , /'./assne n b 5 "
- w a r Min as sa + . '77 Gan du- l 0 nana&L G---
t) C4n, W h &e doa L A ce n n .h /?n n / n G-nr 2
\
w , m , G u n n .19 /n & ~ j dyw+. I i
p :
)
i Lovato, Janet M.'
From: McIntyre, Brian A Sent: Wednesday, May 21,1997 2:05 PM To: Nydes, Robin K.
Cc: 'jms3@nrc. gov'; 'wch@nrc. gov'; Nydes, Robin K.; Kerch, Steven P.; Lovato, Janet M.; McIntyre, Bnan A
Subject:
Re: Suggested Preface to WCAP-14690.
l e
I do not understand your double negative wrt placing the information in the SSAR. The WCAP has no standing except as a reference. If it is important to have computerized procedures open as an OPTION, then it goes in the SSAR and not in the preface to some topical report somewhere.
.At 10:50 AM 5/16/97 -0400, Nydes, Robin K. wrote: j
> Janet - Would you please print this and place a copy in the informal
> correspondence file. Thanks.
> Joe - I incorporated your (Jim's) comment kom this morning regarding
>the number of work station (s) on SSAR page 18.8-17 (2 places). With
>this, all of the SSAR Chapter 18 changes related to deleting reference
>to a " computerized" procedure system, except for our caveat related to
>NRC acceptance of a computerized procedure system, will appear in the j
>end-May SSAR Rev.
>Regarding the caveat, I do not think the SSAR is not an appropriate
> place for that text. Understanding the NRC concern that a statement in j
>the SER is not enough for the rulemaking, I propose Westinghouse revise '
>WCAP-14690, the primary reference for the computerized procedure system, l l
>to include the caveat as a preface. The end-May SSAR revision for
> Chapter 18 would then include a change in the revision number for
>WCAP-14690, from 0 to 1 and WCAP-14690 Revision 1 (which would include
>the preface) could be submitted to the NRC by the end of May.
>Please review this idea and the following preface text and let me know
>if you find it an acceptable resolution of this issue:
> Although the AP600 human system interface resources include a l
> computerized procedure system, evaluation of the acceptability of a
> computerized procedure system is not part of the NRC staff AP600 Human
> Factors Engineering Program review. The NRC neither endorses or rejects
>the possibility of using a computerized procedure system as a means for
>providing instruction to plant personnel. At the time of AP600 design
> certification, the NRC staff does not support or deny the acceptability
>of implementing a computerized procedure system in a nuclear power plant
> environment. The acceptability of such a system for application to the
>AP600 der.ign will be determined during the implementation of the AP600
> man-in-loop test program and verification and validation program (ITAAC
>3.2, " Human Factors Engineering").
l Brian A. McIntyre l Bell 412.374.4334 i WIN 284A334 l FAX Bell 412.374.4887
! FAX WIN 284.4887 Pagei
i Lovato, Janet M.
From: Nydes, Robin K.
Sent: Wednesday, May 21,199712:03 PM To: 'tjk@nrc. gov'; Suggs, Charles W.; Nydes, Robin K.; Deutsch, Kenneth L.
Cc: Lovato, Janet M.; McIntyre, Brian A
Subject:
HICB Mtg in DC Hi Tom. Yes, we can meet the afternoon of June 9. We'll leave the Energy Center by 7:30am and meet you in the Westinghouse /Rockville office at 11:00 (we can alljust grab a quick take-out lunch at the deli right there). Do you think an 11:00-5:00 meeting will give us enough time?
My understanding of the agenda is:
- 1) We'll go through the HICB Tech Spec DSER open items 2434 to 2464 and explain /show how they were j resolved.
- 2) Prior to the mtg, we'll send a current TS markup for section 3.3. During this meeting, we'll discuss any NRC comments on that markup.
- 3) Anything else?
Please let me know if the time, lunch arrangement, and agenda are good. Thanks, Robin Janet - Please book me a car for pickup June 8 and return early June 10 (what are their working hours?).
' And please put a copy of this emailin the informal correspondence file. Thank you.
Page1
[' -
V V' Wectlllgflouss TAA UOVER SHEET
' l' RECIPIENT INFORMATION SENDER INFORMATION DATE: _
/}h/ 22' '
/99 7 NAME:
L Q),oruu TO.- / LOCATION:
% byso/amgJew '
ENERGY CENTER -
EAST PHONE: FACStMtLE: PHONE:
_Omce: ///z-37y-re 9o_ {
i COMPANY: Facsimile: win:
gp gg 284 4887 outside: (412)374 4887 1 LOCATION:
. . , - .L-- . .--
Cover + Pages r$ I+[
. a The following p~ ges are being sent from the Westinghouse Energy Center, East Tower,
, Monroeville, PA. If any problems occur during this transmission, please call:
WIN: 284 5125 (Janice) or Outside: (412}374 5125.
' COMA'ENTS: % fD<Me I
kete a A MAhtue Of S. S. E 7 INDWo Gd % lE Esow s A Qu a nau
/?Aues ist Gmm Lu .i r u s, a c o ,~ ,e ss n 2 J2 e v. 6 o v e m ,,. g< m (M hu . (
n . l. woc a ea near A Al O tJ W 4.
Cu m meus u)ov W J ~~ '
7(. M Wsf C UA M T. UVATn (3 cc's t ori.;iun U
m_.
(!
l 4
~ :(
l
- 3. Design of Structures, Compone%', Equipment and Systems
- Prevent interaction that could result in preventing Class A, B or C structures, systems, and components from performing required safety-related functions 3.2.2.7 Other Equipment Classes Equipment classes E, F L, P, R, and W are nonsafety related. They apply to structures, systems, and components not covered in the above classes. They have no safety-related function to perform. They do not contain sufficient radioactive material that a release could exceed applicable limits.
Stmetures, systems, and components that do not normally contain radioactive fluids, gases, or solids but have the potential to become radioactively contaminated are classified as one of these nonsafety-related classes if the following criteria are satisfied:
- The system is only potentially radioactive and does not normally contain radioactive material.
- The system has shown in plant operations that the operation with the system containing i radioactive material meets or can meet unrestricted area release limits.
- An evaluation of the system confirms that the system contains features and components that keep the consequences of a system failure as low as reasonably achievable.
- Tb sjs% ha no o+k- 29(cJw( dy e~r rcyMy ,fs dw < A Omr5 W" This review of the system features andcomponents includes tne following as a minimum. !
- Features and components that control and limit the radioactive contamination in the system
- Features that facilitate an expeditious cleanup should the system become contaminated
- Features and components that limit and control the radiological consequences of a potential system failure
= 'Ihe means by which the system prevents propagation to an event of greater consequence.
There are no special quality assurance requirements for Class E, F, L. P R, and W structures, I systems, and components. Unless specifically specified,10 CFR Part 21 and Part 50, Appendix B do not apply. The systems and components are normally not designed for seistaic loading. However, there may be special cases where some seismic design is required.
See subsection 3.2.1 for more details.
Structures, systems, and components are designed in accordance with an industry standard at the discretion of the designer. The following provides examples of industry standards which
! may be used for these classes:
Revision: 11 3.2-11 February 28,1997
[ We.5tlngh00S8
W f W i We511ngi100se -
JAX GOVER SHEET
]
l RECIPIENT INFORMATION SENDER INFORMATION i OATE: _ fy)Ai/ 2a r9 97 TO:
NAME:
$ gg LOCATION:
% I6ww/o , h ENERGY CENTER -
EAST PHONE: FACSIMILE: PHONE:
Otnce: t//2-J 7y-fz se COMPANY: Facsimite: win:
_(/Jo/tc 284 4t%7 c<.:tside: (412)374 4887 LOCATION:
l.._ _ _ _ _ _L i
l Cover + Pages 1+2 The following pages are being sent from the Westinghouse Energy Center East Tower, Monroeville, PA. If any problems occur during this transmission, please call:
WIN: 284-5125 (Janice) or Outside: (412)374 5125.
COMMENTS:
I
//ncorue me<~s aie pwax cus~a t, a ou caa cu s oa rrwca,a Av.nar-, swan ~ U uem = 6 w l.com~
a er~ww
/2r., N Vr.KAIC C c,t m a t4/ J t.u a a w.) -~
Is/2 AL-1 J0d 176f%Nf EUI\"5
.T 1.cvA TO (3 cc 'sQimD
- 3
.Z ;
'! r 11. R-dioactiv2 Waste Mr.nagemert l
l detector. He accident range radiogas detectors, VFS JE-RE104A (high range) and VFS JE- I RE104B (mid range), are beta / gamma-sensitive detectors with small sensitive volumes compared to the normal range radiogas detector.
The plant vent radiation monitor detector ranges and principal radioisotopes are listed in Table 11.51. He arrangement for the plant vent radiation monitoris shown in Figure 115-4.
He plant vent radiation monitor accepts analog signalinputs from process and sample sensors for plant vent effluent flow and temperature. Rese signals are used to control the sample flow to maintain isokinetic extraction at the sample nozzles, and to calculate concentrations, releases and flow rates at standard conditions. Rese analog signals are also used to calculate total process flow, total sample flow, and total discharge for an operator-selected period.
He normal range particulate, iodine, and radiogas detectors are deactivated automatically when the gas channel concentration exceeds the normal range. He sample flow bypasses the normal range detectors and a small portion is extracted for the accident range particulate and iodine sample filters and radiogas detectors. This prevents normal range detector damage and allows these detectors to be used to measure the concentrations after they decrease again to within the normal range detector ranges. I Turbine Island Vent Discharge Radiation Monitor )
l The turbine island vent discharge radiation monitor (TDS JE-RE001) measures the concentration of radioactive gases in the steam and non-condensable gases that are discharged
)
by the condenser vacuum pumps and the gland seal steam condenser. His measurement '
provides early indication of leakage between the primary and secondary sides of the steam generators he monitor provides an alarm in the main con'rol room if concentrations exceed a predetermined setpoint. Refer to subsection 5.2.5 for leakage monitoring details and to subsections 10.4.2 and 10.4.3 for process system details. He turbine island vent discharge radiation monitor meets the guidelines of Regulatory Guide 1.97 as discussed in Appendix 1 A and Section 7.5' 1 i cion yell p .. S t y d k l. % : A M 7 C N i3,l a4 1 Y
ne turbine island vent discharge radiation monitor provides data for reports of gaseous releases of radioactive materials in accordance with Regulatory Guide 1.21. De monitor is an inline monitor that uses two beta / gamma-sensitive Geiger-Mueller tubes with overlap in the detector ranges. De range and principal isotopes are listed in Table 11.51.
De arrangement for the turbine island vent discharge radiation monitor is shown in Figure 11.51.
Liquid Radwaste Discharge Radiation Monitor The liquid radwaste discht.rge radiation monitor (WLS-JE-RE229) meatwes the concentration of radioactive materials in liquids released to the environment. T. e liquid releases are made in batches that are mixed thoroughly and sampled. He samples are analyzed on site before Revision: 12 April 30,1997 11.5 12 3 W85tiligh00S8
e f p 11. R dlorctiva Wasta M:nagement 11.5.6.4 Quality Assurance I ne quality assurance program for design, fabrication, procurement, and installation of the I radiation monitoring system and radiation monitors from other systems is in accordance with I the overall quality assurance program described in Chapter 17.
11.5.7 Consbined License Infcrmation ne Combined License applicant will develop an offsite dose calculation manual that contains the methodology and parameters used for calculation of offsite doses resulting from gaseous and liquid effluents. He Combined License applicant will address operational setpoints for the radiation monitors and address programs for monitoring and. controlling the release of radioactive material to the environment, which eliminates the potential for unmonitored and uncontrolled release. He offsite dose calculation manual will include planned discharge flow rates. The Combined License applicant is responsible for the site-specific and program aspects of the process and effluent monitoring and sampling peg Regulatory Guides 1.21 and 4.15.
De Combined License applicant is responsible for ad, dressing the 10 CFR 50 Appendix I guidelines for maximally exposed offsite individual ses and population doses via liquid and gaseous effluents.
/
ANSI Pl i 3. / a %{
Revision: 12 April 30,1997 11.5 18 3 Westinghouse
.y f
- -TX CONFIRMATION REPORT ** AS OF MAY 23 '97 8:32 PAGE.01 APG00 DESIGN CERT DATE'- TIME T0/FROM MODE MIN /SEC PGS STATUS O! 5/23 08:30 #23:NRC G3--S -01"36 03 OK ,
i e
9 e
i
I a l I
l Cindy Ency, 12:18 PM 5/28/$7 , AP600 Chapter 19.1-OITS status l
'Date: Wed, 28 May 1997 12:18:07 -0400 To: jms30nrc. gov i .From: Cindy Haag <haagc10wesmail.com>
Subject:
AP600 Chapter 19.1 OITS Status
. .Cb: HAAGCL, mcintyba, wch0nrc. gov i
-Hi Joe, I ran an OITS report on Chapter 19.1 items _where " Action W" is identified in
, the NRC Status column. There are 92 items listed. Below is a summary of j the topic, OITS_ number, and whether Westinghouse agrees _that they are Action i W. Please work with the appropriate NRC staff to update the OITS NRC status
! column. If you wish to have a telecon or series of telecons to discuss the i ' status, please let me know. I'believe you previously printed a subset of these items (but also included in the printout specification the Westinghouse status = Closed) and probably have the staff looking at those already, f- List of Chapter 19.1 OITS items:
Topic OITS #s W Status = Action W?
- Level 2 PRA Mtg OI 2718 No SGTR RAIs 5014-5016 No Shutdown-PRA 1447, 1448, 1450, 1452, 2939, Yes only for 2980 & 1
- (2987) ~>
2942, 2945, 2958, 2959, 1
2980-2984, 2986, 2987, 3007, 3009 j
F .THU a) 2960, 2961, 3381, 3384, a) No l j 3385, 3390, 3427 i b) 1400, 5207-5227 b) Yes 1
i SMA 1425, 2792-2803, 3432, 3437, Yes only for 5033.,
3
. Ca[4 -~ 5033, 5286-5291 5286-5291, s
l' Misc. Level 1 PRA a) 5121, 5124, 5131, 5134 a) Yes b) 5119, 5120, 5122, 5123, b) No
. 5125-5130, 5132, 5133 Misc. DSER 1406, 1423, 1432 No Thanks, Cindy' Haag P.S. - A printout of this email will be placed in the informal correspondance file.
Printed for Cindy Esag <hangc19weemail.co'> e 1 l
Lindgren, Donald A. _ _ _ _ _
From: Lindgren, Donald A.
Sent: Wednesday, May 28,199710:12 AM To: ' Jackson, Diane' Cc: McIntyre, Brian A; Winters, James W.; Johnson, Edward R.
Subject:
Section 3.9 open items Diane, The open items update provided by Kenyon in your absence shows a few items in Section 3.9 as open that I thought were closed weeks ago.
782 and 783 - 3.9.2.3 and 3.9.2.4 of the SSAR were revised in Revision 11 to clarify that the AP600 is considered l i
a prototype for the purposes of vibration testing. We removed text that said reference plant and prototype meant the same thing. These items should be closed.
. 1797 was in reference to additional information on the Japanese CRDM seismic testing. We resolved this issue by deleting the reference to the testing in the SSAR and by providing clarification about the tests that do support the seismic response of the CRDMs. This items should be closed.
1801 states that the staffis waiting for revision to WCAP-13054. The SSAR and WCAP-13054 match and both match Appendix 1 A and the commitment in the open item tracking system. - This item should be closed.
Shou Hou told me a while ago that we are done on internals and CRDMs. I do not know why these popped open agam.
Also on 3.9 have the IST folks confirmed that Revision 12 closed or resolved the IST and valve qualification items? Of course we do have to resolve the ADS test frequency exemption.
Don Lindgren 1
=
l l
9 Page1
i Winters, Jrm:s W.,11:42 AM 5/23/97, Cimring Open Items on FSER Se l From: " Winters, James W." <winterjw@ westinghouse.com> l To: "'trq @ nre. gov'" <trq@ nrc. gov >, "' des ! @ nrc. gov"' < des t @ nrc. gov >,
'"dtj @ nrc. gov'" <dtj @ nrc. gov >, "'tjk2 @ nrc. gov'" <tjk2 @ nrc. gov >,
"'wch@nrc. gov"' <wch@nrc. gov >,
"Orr, Richard S." <orrrs@ westinghouse.com>,
"McIntyre, Brian A" <mcintyba@wesmail.com>, l "Cummins, Ed"
<cumminwe@ westinghouse.com>,
"Vijuk, Robert M."
<vijukirm@ westinghouse.com>
Cc: "Lindgren, Donald A." <lindglda@ westinghouse.com>, )
" Haag, Cynthia L." l
<haagicl@ westinghouse.com>, l "Nydes, Robin K." <nydestk@ westinghouse.com>, l "Rarig. Bruce E." <rarigbe@ westinghouse.com>,
" Chase, Wayne L."
<chasewl@ westinghouse.com>,
"Novendstern, Earl H."
<novendeh@ westinghouse.com>,
"Carlin Edward L."
<carlinel@ westinghouse.com>,
"Osterrieder, Robert A."
<osterrra@ westinghouse.com>,
"' mms @nrc. gov'" < mms @ nrc. gov >,
" Miller, Richard B." <millerrb@ westinghouse.com>,
"Piplica, Eugene J."
<piplicej@ westinghouse.com>,
"Gresham, James A."
<greshaja@ westinghouse.com>, ,
" Winters, James W."
<winterjw@ westinghouse.com>,
"Israelson, Gordon A."
<israelga@ westinghouse.com>
Subject:
Clearing Open items on FSER Sections Date: Fri,23 May 199711:42:26 -0400 X-Priority: 3
> To meet the SECY-97-051 seedule milestone of" Applicant Submits Final
> SSAR Revisions & Documentation" by 5/97, we believe that NRC must
> acknowledge receipt of all Westinghouse submittals by May 30,1997.
> This is just 8 calendar days away (5 business days).
> For the 7 sections scheduled to have their FSER sections turned into
> NRC Projects by the end of January, NRC Status shows no actions for
> Westinghouse for 6 of them (3.5,6.1,6.6,7,8, and 17). The open
> actions are:
> Section 6.5 1025 Ted, please get us a revised NRC Status.
> This item is open only awaiting NRC review of Section 6.2 and Chapter Printed for " Brian A. McIntyre" <mcintyba@wesmall.com> 1!
w
> 15. It is closed for Section 6.5
> For the 2 sections scheduled to have their FSER sections turned into
> NRC Projects by the end of February, NRC Status shows no actions for
> Westinghouse for 1 of them (13). The open action is:
> Chapter 1221 Design change is being prepared to _
> eliminate the need for an exemption. Action Winters.
> For the 5 sections scheduled to have their FSER sections turned into
> NRC Projects by the middle of March, NRC Status shows no actions for 4
> Westinghouse for 1 of them (3F). The open actions are: i PRA Chapter 42 3268,3269 Haag responsible for providing additional information.
> Section 3.7 628 Orr responsible for providing new
> information.
649,662,664,668,1885,5031 Ted, please get us a revised NRC Status.
> Section 3.10 814 Dino, please get us a re bed NRC
> Status. This went out with NSD NRC-97 5028 of 3/19/97, l
> l Chapter 185247 Ted, please get us a revised NRC Status.
> For the 12 sections scheduled to have their FSER sections turned into
> NRC Projects by the end of March, NRC Status shows no actions for j
> Westinghouse for 2 of them (3.6.2 and 3.12). Open actions are:
l
> Section 3.8.2 706,708,1888,3269 Orr responsible for I
> providing additional information.
> Section 3.8.3 732 Orr responsible for providing new
> information.
> Section 3.8.4 751,5242,5243,5244,5246,5318 '
> responsible for providing new information.
> 745,750 Dino, please get us a revised
> NRC Status.
>~'
> Section 3.8.5 767,768,5029 Orr responsible for providing
> new information.
> 766,769,772, 5028,5030, 5032 Ted,
> please get us a revired NRC Status.
> Section 3.9 (less 3.9.6) 782 Lindgren responsible for
! > providing additional information.
1801 Ed Johnson responsible
- Printed for " Brian A. McIntyre" <mcintyba@wesmall.com> _ 21
4 j I
for providing additional information.
783,1797 Dino, please get !
us a revised NRC Status.
> Section 3.9.6 798,800,801,805 Ted, please get us a i
> revised NRC Status.
> Chapter 4 854 Ted, please get us a revised NRC Status.
l
> Chapter 1i 1171,5346 Israelson responsible for
> providing additional information.
I194,3424,5004 Ted, please get us a revised NRC Status.
> For the 3 sections scheduled to have their FSER sections tumed into l
> NRC Projects by the middle of April, NRC Status shows no actions for
> Westinghouse for 1 of them (13). The open actions are:
> l
> Section 9.2 3,4,3105,3106,3107 Dino, please get us a l
> revised NRC Status.
> 224,233,1090,1091 McIntyre responsible for d issue of RTNSS information sufficient to resolve these items.
> NOTRUMP 33 items Ted, please get us a revised NRC Status.
> 53 items Novendstern responsible for
> providing new information.
> LOFTRAN 2738,2739,2740,2741,2791,3131,3133,3226 Dino,
> please get us a revised NRC Status.
> 3084,3132,3134,3222,5149 Novendstern
> responsible for providing new information.
> For the I section scheduled to have its FSER sections turned into NRC
> Projects by the end of April, the open actions are:
> Chapter 2 547,4997,5229,5230,5231,5232,5233,5234,
, >5235,5236 Orr responsible for providing new information.
> 549 Ted, please get us revised NRC Status.
> For the 2 sections scheduled to have their FSER sections turned into
> NRC Projects by the middle of May, NRC Status shows no actions for
> Westinghouse for none of them. The open actions are:
> Section 6.4 1019,1023,1024,2892,2893,2894,2895,2896,
>3053,3941 Ted, please get us revised NRC Status.
l F >
> Section 9.4 25 ITEMS Winters responsible for
> providing information.
> For the 7 sections scheduled to have their FSER sections turned into
~
Printed for " Brian A, McIntyre" <mcintyha@wesmall.com> ..[ ~ _'~~~~ ((l
d t
> NRC Projects by the end of May, NRC Status shows no actions for
> Westinghouse for three of them (3.4,3.5,3.6.1). The open actions
> are:
> Section 3.11 819,820,821 Dino, please get us revised NRC
> Status.
> 3475,3476,3477,3478,3479,3480 Dick
> Miller responsible for providing information.
> Section 9.3 253,3967,3968 Winters responsible for
> providing new information.
> Chapter 10370,372,1134,1142,1151,1152,1712,2060,
> 3120,3121,3122 Ted, please get us revised NRC Status. ,
> 368 Winters responsible for ,
> providing new
> information.
> Chapter 2199 ITEMS Ted, please get us revised NRC
- Status.
> 10 Items Piplica responsible for
> providing new information.
> 19 Items Novendstern responsible for
> providing new information.
> 90 ITEMS Gresham responsible for
> providing new information.
> Thanks
> Jim
> 412-374 5290
> )
i Printed for " Brian A, McIntyre" <mcintyba@wesmall.com> 4l
t 4
WESTINGHOUSE ELECTRIC CORPORATION 8 PO 80X 355 PITTS8URGH, PA 15230-0355 ADVANCED PLANT SAFETY AND LICENSING FAX NO: 412 374-4887 (WIN 284)
CONF 1RMAT10N NO: 412 374 4237 DATE: Il TO: (( MM '
LOCATION: hdN/ZC FAX NUMBER:
l l
FROM: Brian A. McIntyre j PHONE: WIN: 284 4334 BELL: 412 374-4334 NUMBER OF PAGES (INCLUDING COVER SHEET):
ColmdENMB / MESSAGE:
r: 1 % kn Lu a26s 6 , t 2; ain Gce-6>
9
)
, AP600 REVIEW STATUS May 28,1997 l
FSER Last Total Action W Action N FSER STATUS Section Update OITS items Start Draft DRPM DRPM with w/o 01 O!
--mummmmummeummmmmmmmmmummmmmesummmemammmmmmu-1.1 1.2 1.3 1.4 1.5 1.6 1.7 l
1.8 l.9 2.1 5/19/97 8 0 0 X X X 1 l
2.2 5/19/97 7 0 0 X X X l 2.3 5/19/97 13 0 0 2.4 5/19/97 29 0 0 X X X 2.5 5/19/97 55 11 0 X X X 3.1 5/19/97 X X X 3.2.1 5/19/97 X X X 3.2.2 5/19/97 X X X 3.3.1 5/19/97 X X X 3.3.2 5/19/97 X X X 3.4.1 5/28/97 31 0 0 3.4.2 5/19/97 4 0 0 X X X 3.5.1 5/28/97 18 0 0 3.5.1.3 5/19/97 18 0 0 X X X 0613BAM WPF/May 28.1997 2
FSER Last Total Action W Action N FSER STATUS Section Update OITS i items Stan Draft DRPM DRPM .
with
~
w/o 01 OI nummmmmmmunm-mummmmmmmummumummmmmmummmmmmmumeummmmmmu-nummmmmu l 3.5.2 5/28/97 6 0 0 l 3.5.3 5/19/97 0 0 0 X X X 3.6.1 5/28/97 13 0 2 3.6.2 5/19/97 20 0 0 X X Conf 3.7.4 5/19/97 5 0 0 X X X I
3.8.2 5/28/97 43 4 4 1 3.8.3 5/28/97 37 1 1 l
3.8.4 5/28/97 35 8 0 l
3.8.5 5/28/97 30 9 0 3.9.1 5/19/97 1 0 0 X X X 3.9.2 5/28/97 15 3 1 3.9.3 5/19/97 15 1 0 X X X l 3.9.4 5/19/97 0 0 0 X X X 3.9.5 5/19/97 7 0 1 X X X .
3.9.6 5/15/97 75 4 2 X X X 3.10 5/28/97 9 1 0
- 3. I 1 5/28/97 23 9 12 3.12 5/19/97 41 0 0 X X X 4.1 5/19/97 0 0 0 X X X 4.2 5/19/97 3 1 0 X X X 4.3 5/19/97 0 0 0 X X X 4.4 5/19/97 1 0 0 X X X I l
4.5 5/19/97 25 0 0 X X X ,
4.6 5/19/97 0 0 0 X X X 5.1 5/15/97 0 0 0 0613B AM wPF/May 28,1997 3
l l
FSER Last Total Action W Action N FSER STATUS Section Update OITS items Start Draft DRPM DRPM with w/o 01 01 mmmmmmmmummuummmmmmmu nummmmummamammmmmmmmm-muummmmnummmmmmeummmmmu 5.2 5/15/97 76 2 10 X 3 of 6 l
5.2.3 5/19/97 X X X l l
5.2.4 5/19/97 X X X l 5.3 5/15/97 15 0 0 X 3 of 5 5.3.1 5/19/97 X X X 5.3.2 5/19/97 X X X 5.3.3 5/19/97 X X X 5.4 5/15/97 99 5 27 X 2 of many 5.4.1.1 5/19/97 X X X i
5.4.2.1 5/19/97 6.1 5/28/97 13 0 1 X X X 6.2.I 6.2.2 6.2.3 6.2.4 6.2.5 6.2.6 6.3 6.4 5/28/97 29 10 6 6.5 5/28/97 2 1 0 6.6 5/19/97 14 0 0 X X X 7.1 5/1/97 5 0 2 X X X 7.2 5/28/97 7 0 3 X X X 7.3 5/28/97 2 0 0 X X X 7.4 5/28/97 2 0 0 X X X 0613B AM WPF/May 28.1997 4
I 4
1 FSER Last Total Action W Action N FSER STATUS Section Update OITS items Start Draft DRPM DRPM with w/o 01 01
-mummmmmmummmmmmmmmmmemmmmmmmmm es m ummmmu .
7.5 5/28/97 3 0 1 X X X 7.6 5/28/97 6 0 4 X X X 1
7.7 5/28/97 1 0 1 X X X 8.1 0 0 0 8.2 15 0 1 8.3 14 0 1 1
9.1 5/1/97 27 0 19 X i
9.2.1 5/1/97 8 2 1 X X 9.2.2 5/1/97 6 2 0 X X 9.2.3 5/1/97 1 0 0 9.2.4 5/28/97 4 3 0 9.2.5 5/28/97 2 0 0 9.2.6 5/28/97 1 0 0 9.2.7 5/28/97 2 1 0 9.2.8 5/1/97 2 0 0 X X 9.3.1 5/1/97 15 2 6 9.3.2 5/28/97 0 0 0 9.3.3 5/1/97 4 0 'O
. 9.3.4 5/28/97 0 0 0 X X X 9.3.5 5/28/97 19 1 5 X X X
, 9.3.6 5/1/97 3 0 0 9.3.7 5/28/97 X X X 9.4 5/28/97 64 25 17 9.5 9.5.3 5/1/97 3 0 2 0613BAM WPFMay 28.1997 5
)
A FSER Last Total Action W Action N FSER STATUS Section Update OITS items Start Draft DRPM DRPM with w/o 01 01 munummmmmemunummumusunummummmummusummmmmmemummmmmmmmsummmmmm-nummmmum-10.1 5/28/97 1 0 0 10.2 5/28/97 19 2 2 10.3 5/28/97 10 0 2 10.4 5/28/97 46 10 5 11.1 5/28/97 7 I i 11.2 5/28/97 21 2 3 11.3 5/28/97 16 0 0 11.4 5/28/97 14 1 1 11.5 5/28/97 23 1 4 12.1 5/28/97 5 1 0 12.2 5/28/97 4 0 0 12.3 5/28/97 3 0 0 12.4 5/28/97 12 0 0 f I
12.5 5/28/97 0 0 0 l
13.1 5/28/97 2 0 1 13.2 5/28/97 2 0 1 13.3 5/28/97 7 0 3 i
13.4 5/28/97 2 0 2 13.5 5/28/97 4 0 4 13.6 5/28/97 21 0 16 j 14.1 14.2 14.3 l 14.4 15.0 l
0613B AM WPF/May 28.1997 6 1
l
)
In i
l
'FSER Last Total Action W Action N FSER STATUS Section Update OITS items Start Draft DRPM DRPM with w/o 01 OI muumummunenmusumunununumummmmmuammmmmmusumemmmmmmmmmemummme mummimumm-15.1 15.2 15.3 15.4 15.5 15.6 15.7 15.8 16.1 1
16.2 16.3 1
17.1 5/28/97 6 0 0 17.2 5/28/97 0 0 0 17.3 5/28/97 0 0 0 l 17.4 5/28/97 0 0 0 l l
18.1 5/28/97 1 1 0 X X X l 18.2 5/28/97 14 0 6 X X X l l
18.3 5/28/97 8 0 1 X X X 18.4 5/28/97 29 0 1 X X X 18.5 5/28/97 5 0 0 X X X 18.6 5/28/97 5 0 5 X X X 18.7 5/28/97 6 0 0 X X X 18.8 5/28/97 10 0 6 X X X 18.9 5/28/97 10 0 9 X X X l 18.10 5/28/97 17 0 2 X X X 06:3B AM.WPF/M ay 28.1997 7
l l
FSER Last Total Action W Action N FSER STATUS Section Update OITS
)
items Start Draft DRPM DRPM '
with w/o l O! O! l summmmmmmmemummmmmmmmeummmmmmmmmm-mummmmmmunesummmmm .
mummmmmmemumimmmu l
18.11 5/28/97 8 0 1 X X X 1 18.12 5/28/97 1 0 0 X X X 1
18.13 5/28/97 2 0 2 X X X 19 20 Total 5/28/97 .A [ [ g [ 6
[ 24 J 1.,
/377, / 2-7 13& 68't 6*
l l
l l
l l
l 0613B AM.WPF/May 28,1997 8
2 l I
) i FSER Last Total Action W Action N FSER STATUS Section Update OITS !
. items Start Draft DRPM DRPM with w/o OI 01
- mmmmmmmmu 18.11 5/28/97 8 0 1 X X X 18.12 5/28/97 1 0 0 X X X 18.13 5/28/97 2 0 2 X X X i
19 20 Total 5/28/97 [ [ JW / 6 [ 2d J% -
2
/3fft /L7 2. s e 6 *( 6*
- 1 i
i !
l i
i l
l 1
l l
1 J
0613B AM wPF/Miy 28.1997 8 ;
i i
l I
Winters, James W. . . _ _ _ __ ._ _____ _
I From: Winters, James W.
Sent: Friday, May 30,199710:56 AM To: ms3 nrc. gov; trq@nrc. gov; Haag, Cynthia L.
Cc: iAA igor.wesmail.com; WINTERJW@igor.wesmail.com; dtj@nrc. gov
Subject:
RE: OITS uestion on CHAPTER 42 What's the latest on this request from Cindy?
Jim
> From: Haag, Cynthia L.
> Sent: Wednesday, May 28,199712:59 PM
> To: jms3@.nrc. gov; trq@nrc. gov
, > Cc: HAAGCL@igor.wesmail.com; WINTERJW@igor.wesmail.com; dtj@nrc. gov
Subject:
OITS Question on CHAPTER 42
> Joe / Ted -
i >
> This following question pertains to the status of severalitems in the
> OITS
> that Diane Jackson usually folew However, as I understand she is
> on
> vacation until June 2, I would appreciate it if you could follow up on
>this
> message.
> Last week Jim Winters received a letter from NRC with changes to the
> OITS
> NRC Status column. There were 6 items (#706,1482,1485,1888,1975.
> and
> 3271) that Westinghouse considered to be Closed, since the response
> hos been
> provided, however, the latest info in the NRC letter to Jim states
> these 6
> should be " Action W' and are tied to the closure of #3268. Since
> #3268
> remains open as Action W, I think we should either place these 6 back
> to
> Action N waiting approval of #3268, or if that's the only reason why
> these
> are still open, then close them with an appropriate note to see #3268.
> Otherwise, this is more than a double-counting of open items and goes
> against the process of how we've been trying to track open item
> closure.
Please provide me with your feedback this week.
> Thanks much.
> Cindy Haag
> 412 374-4277
> haagcl@wesmail.com Page 3
Winters, James W. _ _
From: Winters, James W.
Sent: Friday, May 30,199710:53 AM To: 'trq@nrc. gov' Cc: Winters, James W.; McIntyre, Brian A; Lindgren, Donald A.
Subject:
FW: Section 3.9 open items Ted, Here are things that drive us nuts. The PMs should know where the items are (just like you expect our licensing engineers to know). They shouldn't be just a conduit for old information with no value added.
Jim From: Lindgren, Donald A.
sont: Wednesday. May 28.199710:12 AM To: ' Jackson, Diane' Cc: McIntyre. Bnan A: Winters, James W.; Johnson, Edward R.
Subject:
Section 3.9 open items.
Diane, 4
. The open items update provided by Kenyon in your absence shows a few items in Section 3.9 as open that i 1
thought were closed weeks ago.
782 and 783 - 3.9.23 and 3.9.2.4 of the SSAR were revised in Revision 1I to clarify that the AP600 is considered a prototype for the purposes of vibration testing. We removed text that said reference plant and prototype meant the same thing. These items should be closed.
2 1797 was in reference to additional information on the Japanese CRDM seismic testing, We resolved this issue i by deleting the reference to the testing in the SSAR and by providing clarification about the tests that do support the seismic response of the CRDMs. This items should be closed.
1801 states that the staffis waiting for revision to WCAP-13054. The SSAR and WCAP-13054 match and both match Appendix 1 A and the commitment in the c, pen item tracking system, - This item should be closed.
., Shou Hou told me a while ago that we are done on internals and CRDMs. I do not know why these popped open 4
again.
Also on 3.9 have the IST folks confirmed that Revision 12 closed or resolved the IST and valve qualification
- items? Of course we do have to resolve the ADS test frequency exemption.
Don Lindgren Page 2
Winters, James W._ _
j From: Winters, Jame.s W.
Sent: Thursday, May 29,1997 9:58 AM To: 'trq@nrc. gov' Cc: Winters, James W.; McIntyre, Brian A; Vijuk, Rotert M.; ' mms @nrc. gov'; Gresham, James A.;
Rarig, Bruce E.; Haag, Cynthia L.; Cummins, Ed; Cruschi, Howard J. ,
Subject:
Progres 09 Open Iteins j y
Ted, You have taken an active, interested role in managing the remaining open items against our application for AP600 Design Certification. I and others at Westinghouse appreciate your efforts. It is obvious that some branches at
, NRC are following your lead. Thank you.
, Today is Thursday, the day we run our reports, and I think i owe you some observations. Right now, NRC shows
~
, that Westinghouse owes about 1500 responses. That is within a few of what NRC said we owed on the 23rd of Rnuary. By this measure we have made no progress in four months and by projection, we will never finish.
On the other hand, Westinghouse believes that the total number of open items it had answered by the middle of May is more than the total number of open items that existed at the beginning of the year. In the same four months that appear to have no progress, Westinghouse shows it nas answered over 550 open items and NRC has acknowledged receipt of over 850.
Of the 1500 that NRC currently shows Westinghouse hasn't answered, about 400 are in the category that NRC hasn't acknowledged receipt of Westinghouse submittals. The bulk of these are related to questions on the plant
, codes (WGOTHIC, LOFTRAN, NOTRUMP and WCOBRATTRAC). Of the remaining 1100, over 650 are i
containment related, most of which have been received since January, and they still are arriving (90 were logged in last week alone).
Again, thanks for your help across the board. Please let me know if 1, or anyone else at Westinghouse, can help 4
manage closure and completions in the few remaining " big numbers" areas.
i Jim 3
i p
.i Page 31 i
- /#7 W
Westinghouse FAX COVER SHEET RECIPIENT INFORM ATION SENDER INFORM ATION
- A7E. L #, /96 ' N AME. Sh jfacy YO; TN ku,AA rfa s
LOCATION. gj ,, g, PHONE: 30;-9)f-jggf PHONE: 4;g y h_ g, g COMPANY: g)[(
FAX: (412) 374,50g9 LOCATION:
C n.e oages ,-
y y; i
k REMOVE ALL STAPLES PENCIL WILL NOT TRANSMIT USE BLACK PEN PLEASE MAKE COPIES OF TWO SIDEO PAGES l
]
0 t f WA h Y$c. lb (. ItY1&{ LA ll
)
0 Lk &$ $ (bla$ St 671 flL b o I5 !)fl A Ohe +hth Oc td hbc. L irn irriu <'irit en h l ha> bela ayfto Ve9 i LltYC hld tS, S h r1 Al % dVIf f fl'1C$f Cb Abt On 6(L t th $ $-
a: Fens ura a))J k theJo s)flah a ap<m# cAa s~, b , eep*hace w < Ad rra4 e e 3 p , W ss.< Q , M et o. w um.es he If %& if ons iuru
?l%e O '"' '
ajyrofroaf< Y(lx}[h i f- h-- # S . IIo d dC f [ A. !Cf jj b Phonel$((4.5,$ / dd d (, I be d/f X S
/
Number f of Receiving Ecutoment: 36/ - f/f- 22 2.L g
Certified Design Mat:rias
]
4 HUMAN FACTORS ENGINEERING Revision: 3 l Effective: 5/16/97 i l
Table 3,21 (cont.)
Inspections, Tests, Analyses, and Acceptance Criteria l
- Design Commitment Inspections, Tests, Analyses Acceptance Criteria
- 3. The HSI design is performed An evaluation of the A report exists and concludes that in accordance with the HSI implementation of the HSI design the HSI design was conducted in design implementation plan. will be performed. conformance with the implementation plan t.nd includes the following documents:
- Operation and Control Centers System Specification Document 9
- Functional requirements and design basis documents for the alarm system, plant information system, wall panel information system, soft controls, and the qualified data processing
- system
. - Design guideline documents for the alarm system, displays, controls, and anthropometrics
- Design specifications for the alarm system, plant information
~
system displays, qualified data processing system displays, l wall panel information system l 4
displays, and controls (soft an !
dedicated) 2
- Man-in-the-loop ...-r eft l reports / l ahh'no, SWla<)s' x n/ yr ok,'yJu ,
4 1
3.2-5
[ W8Stifigh0080 oNTAACSvev:Nt0302.wptit>C51397 i
Certified Design Meterial a
3 PROTECTION AND SAFETY MONITORING SYSTEM Revision: 3 Effectivo: 5/1WW7 l
Table 2.5.2-8 (coat.)
in ::"- , Tests, Analyses, and Acceptance Criteria Desiga a==a*==* I 7 ::" -- . Tests, Analyses Acceptance Criteria 6.c) "the PMS provides manual An operational test of the as-built i) The reactor trip switchgear l initiation of reactor trip and PMS will be performed using the opens after manual reactor trip selected engineered safety features PMS manual actuation controls. controls are me=A as identified in Table 2.5.2-4.
ii) Appropriate PMS output signals are generated after the manual initiation controls are actuated.
7.a) The PMS provides process Type tests, analyses, or a A report exists and concludes that signals to the PLS through combination of type tests and the isolation devices prevent l
isolation devices. analyses of the isolation devices credible faults from propagating l will be performed. into the PMS.
7.b) The PMS provides process Type tests, analyses, or a A report exists and concludes that signals to the DDS through combination of type tests and the isolation devices prevent i isolation devices. analyses of the isolation devices credible faults from propagating will be performed. into the PMS.
8.a) The PMS provides for the i) Inspection will be performed for i) The selected plant parameters
! mimmum inventory of displays, retrievability of the selected plant can be retrieved in the MCR.
visual alerts, and fixed position parameters in the MCR.
controls, as identified in Table 2.5.2 5, in the MCR. ii) An inspection and test will be ii) 'Ihe selected parameters are performed to verify that the used to generate visual alerts that l selected p s;es are used to identify challenges to critical generate visual alerts that identify safety functions. 'Ibe visual alerts !
challenges to critical safety actuate in accordance wic. tacir I functions. correct logic and values.
iii) An operational test of the as- iii) For tes)/of each as. built fixed built system will be performed position control, an actuation M
using each MCR fixed position signalis generated.~7Gh f'd control identified in Table 2.5.2-5. gdubh dd h the a d u a.
8.b) The PMS provides for the An operational test of the as-built Actuanon of th'e transfer switches b ai< ( ,
transfer of consol capabihty from system will be peiformed to results in an alarm in the MCR m the MCR to the RSW. demonstrate the transfer of control and RSW, the activation of -
, gi capability from the MCR to the operator control capabdity from 4 ;
RSW. the RSW, and the deactivation of I l
operator control .apabdity from 13 k i the MCR. g .gg.r- '
h yetts h his+,
ON $$ gn 1 Aud)hcr u.% i, I
I l 2.5.2 13 O m6ap00(NTAACSVoca020602.wyt.i t@61497 l
Certified Design Material
('
e DATA DISPLAY AND PROCESSING SYSTEM -
. Revision: 3 Effective: 06/16/Ir1 i 1
Table 2.5.4 2 Inspections, Tests, Analyses, and Acceptance Criteria De' sign Comadtment InsWa. Tests, Analyses Acceptance Criteria 4 1. De DDS has distributed Inspection of the as-built system ne as-built DDS has distributed
! computer processors and video will be performed. computer processors and video display units to support the data display units to support the data i processing and display functions. processing and display functions.
- 2. He DDS provides for the i) Inspection will be performed i) The selected plant parameters minimum inventory of displays, for retrievability of the selected can be retrieved in the RSW.
visual alerts, and controls, as plant parameters at the RSW.
identined in Table 2.5.4-1, at the
, RSW. ii) An inspection and test will be ii) ne selected parameters are performed to verify that the used to generste visual alerts that selected parameters are used to identify challenges to critical
- generate visual alerts that identify safety functions, ne visual challenges to critical safety alerts actuate in accordance with functions. their correct logic and values. l lii) Appropnate output signals
- iii) An operational test of the as-built system will be performed for each control function in Table are generated "Tes4-5 inJj.4o g ygg r o w1 t)1' Cuf y
j '
2.5.4-1. a t .>rrfa wlef A6 <> 1 r F .f.)
. 3. ne DDS provides Tests of the as-built system will ne as-buift system provides gg information pertment to the status be performed. displays of the bypassed and /
of the protection and safety operable status of the protection P UEA monitoring system. and safety monitoring system. hi
, in
- 4. ne DDS provides nonsafety- See Certified Design Material of See Certified Design Material of gt, related displays of parameters other systems. other systems.
originating in other systems.
drM M As utl Art *
' (nkH IL ,
4 2.5.4-4 6 ovrAAcsvov:weoso4.weitros1597
p W l Westinghouse m$
S&OYO(
JUN W M997 I
ox e Brian A. Mc Intyre FAX COVER SHEET RECIPIENT INFORMATION SENDER INFORMATION DATE: Wednesday, May 28,1997 NAME: Earl H Novendstern TO: Bill Huffman LOCATION: Westinghouse PHONE: x1141 PHONE: (412) 374 4790 COMPANY: NRC FAX: (412) 374-4011 Cover + Pages = 1 + 30 3
i Comments:
i Bill, 4 Attached is spreadsheet I've been using to track our informal correspondence on RAls/Ols, etc. Please let i me know if this of use to you and if you can suggest other columns that should be added.
l l
l cc: B. McIntyre (NRC Informal File), S. Fanto i
fd'E J - 0 9 FAX DOT
O r A
A B C D E F G H I J l K L OITS 8 Type Descripeton W St Code Eng Suhmit Sedunit Draft to toleRC(ltr OITS s Action E Code Draft (Dele) F6iel(Dele) NRC(Dete) s) (YAtlin
~ ~ ~
4G39 MTGO RAI WCAP i4i71IREV.'1'WCOBRA/TRACIM'TY TO AP600 A'tm c l5UT) Novendstem\WCTWen[ 164Aa[ 19 May '4639 LBLOCA W Retrance t. L E.Hodvener,et al_,WCOBRA/ TRAC AppbcatWy to AP600Large4heekLoss<stCooters Acadarit WCAP 14171P,Rev.1 Odober 19EL 2 .
NOTE: The spashans are teed on t .__ _, _ _. _ __ _
4180 KEYISSUIKey issue Nisnhor 17. Code Documertanon and am==t (V&V of __
Actm_GreshamPyhcG. 4 ..%_ _ ___ _ . _ _ _4180_ _ _ _
Codes) Review himrporasmg Tesang Date Resuas (SCS8/SRXB) W The supplemert to sie DSER on Codes and Tesang idennhed 3 _.
aPPmmenasesy 120 cpen esues concanne tte AP600 nes , __ . _ _ _ _ . , _ _ _ , , . ,,_
3134 DSER O 21.6 7-2 Weslmpiouse needs to idertfy sie hionnehon ponnded n RAI Adian LOFTRAN, _ _ _ _LOFTRM4Carin 4 .
response lhat we tie hmeportand reo the LOFTRAN Insi v&V or CAD W _ _ .___ ._ _ _ __
3222 DSER O 216 5-27 Washnghouse needs to demonalrale tie an=ptahany of LOFTRAN_ Achon LOFTRAN LOFTRAN/Cartn_ _ _ _
ior ee os she MSLB mas and energy release lor the AP600 DBA W
- ' ~ ~ ~ ~
si49 ~ MTGUI ius MeehngOpennem Adson LOFTRAN LOFTRANICa5I~~ ~ ' 5149'
. 3) include mpes of apprN RAls and the W summary a the W
_$_ _. _MTGO. . Meeung _ _ _nnat versaan of the LOFTRAN .&V Report and Adsonsie LOFTRAN CAD.
5135 Open nent LTC LTC/Kernper __5135 Mgart Presentahan on WCIT Long Term moing (LTC) to the NRC W MTG O e1:
Westmpiouse needs to descnbe the trealmert of mass and energy rahum rahdah=1 by GOTHIC out of ADS 4 lor LTC mre bod <ill rahaahans j I -.- .. - - - . . - . . . . - - - -
Achon LTC -_LTC/Keroper 5136 5136 MTGO Meehng Open tient Sutged. Presortanon on WC/T Long Term mohng {LTC) to tie NRC W MTG O #2.
Determne apphcabesy of Reguiasory Gum 1.1 tor DBA LTC Chapter 15 a awaammis .
_ _ _ ._ _ _MTGO Mesang Open lient Adnan LTC LTC/Kemper 5137. _ _ _
5137 Sidged: Presortahon on WCIT t ong Term cochng (LTC) to the NRC W MTGO #3 Are the died valves from the accumulator sutWapartmart to the surrp 1 - _
safety grade W operable 6 sing LTC.
Achon SAR0115 SARCh15/Carin 3084 3064 TELO_ . _ Adeon
_ _ irorn 4/10516 phone caN between Weshnghouse and NRC Reactor Systems Brandt (NRC Reviewer - Norm Laubham, et. ai ) W NRC requests informahon on the sterfams terween salsty analysas computer codes for the NSSS (NOTRUMP, LOFTRAN, WC/T, SATAN) and t 10 OIIS wk312.57 PM PageI
_. . . - _ .m . . . _ _ - . _ . . . . . _. .- - _ - - .m_ -.- __ _ _ ._
s r A
A _B C D E F G H I J K L OITS 5 Type Descrtpeen W St Code Eng Subet Subadt Draft to OITS 8 to IWIC(ur Acmen E Code Draft (Dese) Final (Dese) NRC(Dete) 8) (YAgin 3132' DSERO 25U6-1 ~ Adion 5ARO15 S5iUtiSU
~ ~ ~~
'3132 ~
Westinghouse needs to desate,in Chapter 15 of the SSAR, the PRHR heat W transser cpean a has ==mre=a tar eam analyus m etwh LOFTRAN a spphed ;
1I and enj*sm why me opson is conserveave for mat WM _ _ _ _ _ _ , _ ,_,_ _
3172 DSERO 21.6 4-2 ._Adion
_ _ _SAR O15 SARO15Menper_ _ _ _ _ _ . _ _ , _ _ _ _3172 ._ _
weshnghouse needs to psWy se ladure of one ADS 4 vahe as me worst- W case smgle tadure for an LTC analyes of a double 4nded cxud leg gueatne
_I2 .. . jDE_CLG} break. __ __
3173 DSERO 21 6.4-3 Achan SAR O15 SARO1Wemper. _ _ _ _ . _. _ _ _ , 3173 Wesen@ouse needs to personn analyss of coremnment and vessel pressure W versus lone in to evolimon of me LTC sceneno to justly pressure values for 33 .
anLTCanalyssof aDECLGt:eelt __ _ _ _ . _ _ __ _ _ _ _ . _
3174 DSER O 21644 Achon SAR O15 . _ _ ___SARO1Werrper 3174 Westeghouse needs to provide a dntaded arman of the presswo vanahons W m the vessel and me pressure Ir- due to me now in the vessel to sipport I4 me LTC analysis of a DECLG tweak.
3175 DSERO 2164-5 Adeon SAR O15 SARO15Memper 3175 Weshnghouse needs to address a decrepancy between me total miechon W tow and total owtow korn the vesse! m as LTC analyss of a DECLG break.
15 3176 DSERO 21644 Adion SAR O15 SARO15Memper 3176 Wesem@ouse needs to dardy the vow! kachon praer*aris used in as LTC W 16 analyssof aDECLGbreak.
3177 DSERO 21.6.4-7 Adson SAR O15 SARO1Wemper 3177
. . _ J - must adeess me peak cladeng teniperature and pressure W '
esenbweans i the weser m the sump is saturated esnng LTC and me void ,
17 kachon was higher m ts LTC analyss of a DECLG tweek. __ __ __ . _ _ _ _
3178 DSER O 21.6.4 4 Adion SAR O15 SARO15Menper 3178 Wesenghouse needs le Moose addeonal undows for the DECLGereat W i LTC analyses to demoneerste me eNeceveness of the posesve cootng systent
~~~ ' ~ ' ~ ~
315-~ DSERE 2164-9 Achon SARO15 SARO1Wemper 7 179 Westeghouse needs to address boron prar1*hno o is Chapter 15 LTC W E . _ _
SSAR analyss __ __
SARO15 SARO1Wemper 3180 3180 .DSER O 2164-10 Adnan Westeghouse needs to address the eNed of waler holdup or diversaan m W awitanment water loss through contanmerd leakage, or lhe need to replenish any water tost form cordanment because of ha aga to sipport the 20 LTC analysas 1
OllS wk312.$7 PM Page 2
- ~ -
.. _ . . ,. .- - . . - - --.. ~ _ _ . . - ~ _ . . . . . . ~ .~. w-- -. ~ . ..
e r A
A B C D E F G H I J K L OfTS S Type Descripelen W St Code Eng Subadt Subadt Draftto to NRC(nr OITS S Acelen E Code Orsft(Date) Final (Dele) NRC(Dele) f) (Y4llin A5'
^ ~ ~ ~- ~~
216 4 ti ~
- ~ '~
3'181 - ~DSERUI ShidiS~WO15Meniper " 3181 Wes.mghouse nMds to adeess me a*9aq ci me unndows seiscled as W 23 _ . .represensabue alme LTC overs. __ __ ___._ , ._
3182 DSERO 21.6 4-12 Achon SARO15_ _____ . _ _SARO15Memper 3182
_ f . - needstoleerefyhowheperhon of a LBLOCA-LTC1ranssent W between me end of an UILOCA anssynes and me start of an LTC analysis we UUUM~
' ~ ~ '
3184 'DSER O Acton SARCI 3f84 Weem@ouse needs to intsyste me cortammerd response into me AP600 W '
23 .
-'*******'*M- - . . _ . - - . _ -. - - . . . . . . . - . -_- - . .
3423 -.RAIO. . _ 440 583 The seeA squaes admonal mionneton about me corripuler codes Acton SARO15 SARQ15/Kemper -..3423 bang used tor the AP600 LOCA anespees and how moes codes intertece an W reerad. For example, h me case of me SILOCA me NOTRUMP code is l E . _ . ..
used tor me analyss of me shmtle . _ _ _ _ _ . . _ , _ _ _ _ _ _ _ _ .
_ _ .4181 41S1 ___KEYISSUI Key issue Nwieer Acton_SAR O15 SARO15Cathn
- 18. Chapter 15 Accident Analyss(SRX8 lead) W Ashoup a preimnery Chapter 15 antarit analyses was stdimmed by WC__ , -^ me Inst sowisson to me SSAR is not ampartant sed i Febnsory 25 1997. The stallcoriemuss to rev - _ _._ _ ._ _.. - --
4461 MTGO
SUBJECT:
NRC COMMENTS ON THE AP600 STANDARD SAFETY Acton SAR O15 SARQ15Cartnf 4461 ,
ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W i
- 1. Ducuss me NRC mview stelus of at me congador aides used in the transsent and accidert analyses decisnented in AP600 SSAR. For those A __
_ . . _ _ _MTGO___co8852a 4462 SuluECT. NRC COMMENTS ON THE AP600 STANDARD SAFETY Achon._SAR O15 SARO15Cartn 4462 ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W
- 2. Provute a het of sngle ledwes canadored h your analyses, and perform a syseemenc assessmere lor secti transeers and aa:6dere and psefy why 27 Acton SAR O15 SARO15Cartn 4 4463 MTGO SUBJECT. NRC CC4dMENTS ON THE AP600 STANDARD SAFETY ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W 3 GDC 17 m 10 CRF Part 50 Appenda A requires,in part: "An onsde electnc power system and allsee elecinc power system shed be prouded i 28 Achon SAR DIS SARO15Carin 4464 w 4464 MTGO SUIDECT: NRC COMMENTS ON THE AP600 STANDARD SAFETY ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W
- 4. In seeral Chapter 15 analyses runsalsey4eleted equipmere was credeed kw accident mageson. The equement svheas the man teedwater 29 pump i
+
OIIS wk312.57 PM Page 3 I
~
s p.
A A B C D E F G H 1- J K L OITS e Type Descr$nen W St Code Eng Seemdt w Draft to toIWIC(Isr OfTS 8 Acton E Code Dradt(Dese) Final (Dete) IIRC(Dues) 8) (VAI)he
^ ~
MTED AA EE55"
~
4465
SUBJECT:
'NRC COliMENTS CETHE AP600UANDARD' SAFETY ~ 'SAR O15 4E5 ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W
- 5. Chapter 15 shedd techste a latdo or sendar summary docunordaten of j
syssem aauman ensa, woes cienue one and syseems paramesers
~
4467' ~MTE6
' ~
T: NRC maahaFNTS ON THEEtIODITAND'ARD"S EETY Aa5 SARO15 SARO15/Cartr[ ~ ~ 'E467' ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W Increase in Feedesem Flow (SSAR Seann 15.12)
,3I _ _ _ _ _
steam generator pues 4468.__._MTGO SUEWECT: NRC COMMENTS ON THE AP900 STANDARD SAFETY Achon__SARO15_SARQ15Cartn_ _ _ _ _ _ _ 4468 ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W Inadvertent Openng of a Sesam Generator (SG) Rehof or Salsty Vahe (SSAR Seann 15.14)
....._m . _\ . _ , _ . . . - . . -,. -
w..-..._ .
.....e. , . 4 , _ ~ .
4471 MTGO_. SUEUECT:NRC masaaFNTS ON THE AP900 STANDARD SAFETY Acton SAR O15 SAF. Ch15Carin .4471 i' ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W E _ _ _ . _ .. _ . _ _8. Pade me DNBR cwwe mihe SSAR secton for me tranment . _ _ . . _ _ _ , _ _ , , _ . _ _ , _ _ . . _ _ _
4472 MTGO SUEUECT: NRC maahaFNTS ON THE AP600 STANDARD SAFETY Acton SAR O15 SARO15Cartn . 4472 ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W Sloam System Ppng Faswo (SSAR 15.1.5)
E 9 _Pmde me DNBR cune m me SSAR lot me tranmort , _ _ _ _ . __.._
. . . _ _ _ .MTGO_ - .SUluECT:
4473 _ _ . _ NRC madaaFNTS ON THE APtiOO STANDARD SAFETY Aamn SAR O15 SARO15Cartn 4473 i ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W
- 10. The review sesN udi nsed me fotousi0 adatonalinformaton to corgiste es review of me steamane tweadt analyst 1 _ [a) ToconAnn __ ._.., ___ , _ _ _ . _ _ _ _ _ _ _ .. _ _. _ _ , . _ _ _ _ . ._ _ _
4475 _MTGO_ . _ . _ _ .SUEUECT: NRC COMMENTS ON THE AP600 STANDARD SAFETYAamn SARO15 SARO15Cartn 4475 ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W
- 11. Eglam why the engas todwes such as todwo of me MSiv to close m the 36 visact SG, and lodwe of leedmaser nahsen to close are not consule 9
Oils wk312.571.a Page 4
- _ .m.-_-_ _:_-.- __ . _ _ _ _ . . _ _ _ _ - _ _ _ _ _ _ _ _ . _ _ - _ _ _ _ _ - _ _ _ - -- - - - . - + - _mu- w - _ _mm-_ __
~ . . .
A A B C D E F G H I J K L OITS e Type Descalpelen W St Code Eng Satuult Sedsma Dren to toIRC(nr OITS 8 Action E Code Dreft(Dele) Final (Dete) NRC(Dese) f) (Y/tgin
~ ~~' ~ ~
4'476' - MTG'O 'SIUEUECT. NRC C'OMMENTS ON T5E APtiOO STAf0IRd'UAFETY Adeon SARCh15 Shi d 15 M ~ 4476 ANALYSIS MPORT (SSAR) CHAPTER 15 ACQDENT ANALYSES W Inadverters Oposenhn of sie Panerve Rosadual Heat Removal System (SSAR 1511.6) 37 12. Provide a hwan of sie hpad of me most si ~ ~ ~ ~ ~ -
Achon i UIR C iti -5Ui2556uin~ ' ^44f7 4477 MTGO SuluECT: NRC COMMENTS ON THE AP600 STANDARD SAFETY ANALYSIS MPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W
- 13. Eglam how the zeropmeer case a boeded by ihe nadvertent operung 1 d a SG rebelor safety value.
Adson SAR O15 SARO15Cartn 4478 4478. _ _MTGO_ . _ _SUEUECT: NRC COMMENTS ON THE AP600 STANDARD SAFETY ANALYSIS MPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W Turbme Trip (SSAR 15.2.3)
- 14. Thss analyses does not address comphance wth me GDC 17 39 .requremeres. TosatsfyGDC17,m_eenactsof alo . . _ _ _. __ __ _ . .. .
___SAR Q15 4479 MTGO SUEUECT: NRC (X)MMENTS ON THE AP600 STANDARD SAFETY Adnan SARO15Cartn_ _ _ _ _ _ 4479 ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W Loss of ac Power to the Plert Aushenes (SSAR 15.2.6)
S 15. Provide a DNBR transsert curve for a loss of ac power event.
Adion SAR O15 Sana 15Cathn_ _ _ _ _. _ _
4480
__. . . _ .MTGO 4480 SUluECT:NRC COMMENTS ON THE AP600 STANDARD SAFETY ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W Loss of normal Feedweser Flow (SSAR 15.2.7)
~ ~ ~ ~ ~
~ ~
~Achon SAR-Ch15 S5 Q15Cadn ~~4481' 4481 MTGO SUEUECT:NRC COMMUiT50N THE AP600 STANDARD SAFETY ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W
- 17. The analyss does not address carrybencs use me GDC 17 requrements. To sehsfy GDC 17.me afinds of a toss of olesas power on the
~ ~
- ~
~CT[NFiC'CMT505 T15~UaTAf0AR5 SUETk Adnan SARO15 URCh15Carhn U82' ~
4482 M'TGUt' ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W Feedwater Systern Pye Break (SSAR 15.2.8)
- 18. The loss d offsde power, resubog in a RCS lion coastdown, is assumed 43 at the tune of ibe reac OliS wk312.57 PM Poge 5
. . _ . _ . . _ . - m . . . _ , ..
s a A
A B C [D E F G H I J K L OITS # Type Des @ W St Code Eng Submit Submit Draft to to NRC(Isr OfTS # Acelen E Code Dren(Dele) Final (Dete) NRC(Dese) 8) (YAl)in i .
OITS 4483 MTGot
SUBJECT:
NRC COMMENTS ON THE AP600 STANDARD SAFETY Acton SARO15 SARQ15Carin 4483 ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W 19 Trus analyes (page 152-17) assumes a doidneiruled neture occurs aber a reador Mp on me tour 4sw steem generator level sqpal Ttus is nco
~' ~ -- - '~
4484 MTGd I SUEDUdT NRC COMMENTS ON THE AP600 STANDARD SAFETY hkn-SARdtI5- SAFU25iSIUAnn~ ~4484 ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W !
20 The staff noted mal me nonsafely seisted stark, feedwater system
($FWS) and the posewuer spray (PS) were aedged (page 152-19) lor heat
- - ~ ~ ~~ - ~
4485 ' MTGd SUB5CT: NRC COMMENTS ON THE AP600 STANDARD SAFETY E5AR2h15 ShiCrii5Cartn 4485 ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W
- 21. The DNBR resues for sus event should be innentert n the SSAR. The calctdated trunenum OfeR should be grosser man the salsey emit DNBA for
~ ~' ' ' ~ ~ ~ ~ ' ~ ' ~ '
4486'~ MIGOI SUCT: NRC COMUI iiiON THEh600 STANDARD SAFETY Achon 55U:15 NO15 4486 ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W i
. 22. The Samscale test data for leedmeter kne breaks (as rheasant n Secton 413.1 of NUREGCR4945, deled July 1987) showed met me steam U genera _
t Acton SAR O15 SARO1SCartn 4487- _ _ _ . , ,
4487 MTGO SUEUECT: NRC COMMENTS ON THE AP600 STANDARD SAFETY ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W
- 23. Figure 152.84 shows mat the weser level reaches me top of me pressuruer dunng a penod of 6000 to 20000 seconds aber an FLB evert
- ~~ ~ ~ ~
4488
~
MTGU 5UEUECT: NRC CdMMENTS ON THE AP600 STANDARD SAFETY 'Aden SAR Q15 ERQiSCartn ~I88' 4 ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W Partel Loss of Forced Reedor Coolard Flow (SSAR 15.3.1)
- 24. The staff lound that no rhmnant Wes provided lor me events wilh loss
~ ~ ~ - ~
~
4489 MTGU CIINUCOMMENTS ON THE AP600 STA5DARD SAFETY Acton SAR O15 SAR Q15 5 ~ '489 4 ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W Reador Cociart Pump Shat Break (SSAR 1514)
- 25. No transaart DNBR curve was induded in the documertaton, and the I
50 bases tor assumng 18 pe r
OtIS wk31257 PM Page 6
=
b I A
A B i C D E F G H I l J K L [
OITS e Type Descripeten W St Code Eng Sedunit Satuut Dndt to to NRC(br OITS e Acelen W_
Code Dradt(Dees) Fhiel(Dete) NRC(Dele) f) (TAI)in
~ ~~
4490 ' MTGO~ SUEdECTi5AC iiOMMUdTS'ON THE AP600 STA5DARD SAFETY EOT55
~ ~~ -
Aden' SAR O15 '4490 ~
ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W SRP Semon 4.4 sestes tiet t the DNBR taas betoo the safety Imt DNBR, E . _ . . _ _ ._ . _ - _ .M tailure must be assioned for M moisse tie safety hmn ..
4491 MTGO
SUBJECT:
NRC maanaFNTS ON THE AP600 STANDARD SAFETY Aden SAR O15 SARO15Cartn 4491 ANALYSS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W >
- 27. The coresat red asidramel analyus does not address comphence weh E _. To sanely GDC 17, tie oseds of a toss of onsee
_ _ .._MTGO.
4492 SUEUECT:_ _NRC
_ ..the ODMMENTS GDC ON THE 1.]In_
AP600 STANDARD SAFETY Achon SAR O15 SAR Q15Cartn 4492 ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W 28 DNBR scenas are not presorted for sus everies usi a dropped or I nasabyted ACCA (the ongnal Agne 15.4.3-5 mes dan =amd). The hgure
~ - ~ ' ' ' ~ ~ ~ ~
4493 ~MTGO SUEME TINRCCOMMENTSONTHE AP600STANDARDSAFETY Acton SAR Q15 SAR O1 U ' '~ 44'93' s ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W ,
Uncxweromed Rod Clusser Cordret Assently Bert, Wahdramel at Power (SSAR 15 42)
. i 54 29 The wahdrawal at power analyss does not address compha 4495 MTGO SUEUECT: NRC COMMENTS ON THE AP600 STANDARD SAFETY Achon SARO15 SARO15Cartn 4495 ANALYS:S REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W !
Rod Chaser Control Assembly
- i - _ (SSAR 15.4.3)
- 30. The sequence of tie everts is not provided lor the rod assembly drop
~ - ~ ~ ~ ~ ' '~
4 96 MTGO~~ -SUEMECT COMMEN'T ION THE AP600 STANDARD SAFETY Achon SAR O15 SARO15Cartn 4496 ,
ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W Rod Clueber Corerol Assembly Maahymners (SSAR 15.4.3) 56_ __ _
__MTGO 4497 SUEUECT: NRC COMMENTS ON THE AP600 STANDARD SAFETY Adian SAR O15 SARQ15Cartn 4497 ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W ,
RodClusterControl Aseantly"- . _.._; (SSAR 15.4.3)
- 32. The stas nosed that for tie smgle assembly uWidramel event, an ,
i 57 .
ridrequent evert, _ _ '
4498 MTGO SUEUECT: NRC COMMENTS ON THE AP600 STANDARD SAFETY Adion ^4* M SAR O15Carin 4498 ;
ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W ,
SRP Sedon 4 4 stases that d the DNBR taas below tie safety hmt DNBR, ,
58 fuel lailwe must be assumed lor as rods that violate vie salmly hme ,
i T'
OllS wk312.57 PM Page 7
. _ . . . .~ . . ~ - - , . . = . _ . .. - - . . - ~_ .. ._~-
~
s A
A B C D E F G H I J K L l OITS e Type Descr$een W St Code Eng N Seemit Draft to toIWIC(nr OfTS t Acelen W_
Code Drest (Dese) Final (DM ) NRC(Dese) f) (V49in j
~
i ~ ~ ~
~~ ~ ~~ ~
ORTS 4500' - MTG OSUBJECTINRCCOMMENTSONTHE AP600ST'A DARDSAFETY Aden UdO15 SARU15Cartn~ 4500 ANALYSIS REPORT (SSAR) CHAPTER 15 ACODENT ANALYSES W l Stad@ of an inactive Reasser Cooient Pung at an incorsed Temperature ;
(SSAR 15.4.4)
S _ _ _
MTGO_34
. Ths anMyou does not edeces meghants aim me . _ _ _ _ _ __ _. , _
_,_4502 4502 SUEUECT: NRC maahaFNTS ON THE AP600 STANDARD SAFETY Aden SAR O15 SARO15Cartn_ _ _ _
ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W Bomn Deden(SSAR 15.4.6)
- 35. Recent non-consonagens use iderehed at Comanch Peak rolded to 60 .
m.ee gid assesepeans and beimdery canem _ . _ _ . . _ _._ _ _ _ _ . _ _
4506 MTGO SUEUECT: NRC COMMENTS ON THE AP600 STANDARD SAFETY Aden SAR O15 SAR O 15Cartn 4506 ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W Baron Deumon(SSAR 154 6)
- 36 Decuss me ladinsal bases for tie thergng Now of 200 gen assumed n 61 m_e_analyss._ ___,_ ,_ ____ _ , _ , ,_ _ ___ . _ _ __ .. _
4508 MTGO
SUBJECT:
NRC COMMENTS ON THE AP600 STANDARD SAFETY Aden SARO15 SARO15Cartn 4508 ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W L
Baron Deuhon(SSAR 15.4.6)
- 37. The value of the sepomi(60 penant enesee/10 nun) of sie source 62 range nudeer Muinsnerdemon used m .._ _ _ _ _ _ ., . _ , _ _ _
_ _ _ .4509. _ _ , _ _ _ _
4509 MTGO SUEUECT; NRC COMMENTS ON THE AP600 STANDARD SAFETY Anson SAR O15 SARO15Cartn '
ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W Boron Demon (SSAR 15 4 6)
- 38. Ducues me amo a noidd lebe kom sie samt of me dhoon to me loss of S
i
_ _ _ . _ _. . _ - _ _ .shaddoun eneren and men to rearm _ , _ . ,,,_n _ , _ , _ . _ . _ _
4510 MTGO SuluECT: NRC COMMENTS ON THE AP600 STANDARD SAFETY Adian SARO15 SARO15Carin 2744ay__ _ _ _ _ 4510 ANALYSIS REPORT (SSAR) CHAPTER 15 ACODENT ANALYSES W ;
inadvenerd Landmg and Opershon of a Fuel Assently m an improper
[
Poemon(SSAR 15.4 7)
S _ _ _ . _ _. _ . _ _ ,39. The $hesromenedtewee<luencesof to Aden WlO15 SARO15Cartn
. , , , , _4511 l
4511 MTGO SUEUECT: NRC COMMENTS ON THE AP600 STANDARD SAFETY ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W Rod Egeden Accident (SSAR 15.4 8)
- 40. Pronde me analyss to shoe how 15 percert of me fuel empenmcing 65 DNB was ch Also, a losso Page 8 [
OIIS wk312.57 PM
, s A
s A B C D E F G H I J K L OITS e Type Descripelen W St Code Eng Sedunit Sedunit DraR to OITS s to NRC(nr Action E Code Draft (Dete) Final (Date) Imc(Dete) #) (YM)in
- ~
~ ~' ' ~ ~ ~ ' ' ~ '
'4512'~
~
45'12 MTG"O~ SUB5CT: NRC COMUNTS DN THE APdSTANDARD SAFETY Aden SAR O 15 SAR O15G Er~ ~~
ANALYS!S REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W Grover/Sdwiz LOCA outude carmeevnert
- 41. Desome me swupam to answe met me antamno valves a the CVS OO _ .
_ _ . _ - . _ _disdmje hne and me suple h ad be gLaa_l_ , _ _ _ _ _ _ _ _ . . _ _ _ , , _ _ _ , ..
4513 MTGO
SUBJECT:
NRC maataFNTS ON THE AP600 STANDARD SAFETY Achon SAR O15 SARO15Carin_ _ , . _4513 . , , . _ _
ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W Steam Generator Time Rtgiture (SSAR 15.6.3)
- 42. The ster notes mal for the APG00, me caste power mes assumed to be 67 available alho SG overt 4514 MTGO
SUBJECT:
NRC COtmaENTS ON TE AP600 STANDARD SAFETY Adm SARO15 SARO15Cartn 4514 ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W Steam Generator Time Rtgiture (SSAR 15.6.3) 43 The rahd%d D8NR curwe shondd be included in the SSAR lur this
_00 . .
.. _.analyss,_ _ _ _ _._ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ . , _ _ . _ _ _ _ _ . . _ , . _ _ . _
4515 MTGO
SUBJECT:
NRC COMMENTS ON THE AP600 STANDARD SAFETY Acton SARO15_ _ _ , _ _SARO15Memper
_ 4515 ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W Loss d Coolart Acaderts (15.6.5)
- 44. Provide a lodrucal basm for delnng :he break d 1.0 R2 as the largest !
69 SB s 4516 MTGot SUEUECT: NRC COMMENTS ON THE AP600 STANDARD SAFETY Acton SAR O15 SARO1Wer@er 4516 ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W Loss of Cociars Aaidores (156.5)
- 45. Espand me break sue spectnsn study to cover me fut range of the 70 SBLOCA w t _ _ _ _ _ _ ___ ..__ __. _ _ .. __
4517 MTGO SuluECT: NRC COMMENTS ON THE AP600 STANDARD SAFETY Acton SARO15 SARO15Eemper_ 4517 ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W Lossof Cooient Acadents(15.6.5) ,
- 46. Provide me tess $or the " judgment" that determned the ladure of one of A me ._ _ _ _ _.____,,
Adion SAR O15 SARO15Eemper
__ _ __ n___ _ __ _ _
4518
.._MTGO_ _ _ _ _
SUBJECT:
4518 _ hRC COMMENTS ON THE AP600 STANDARD SAFETY ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES VJ Loss of Coolant Acadents(156.5)
SBLOCA(SAR 15 S.5) 47 The steam sotahan valves are asstaned to closs one second after the 72 reactor 1r OSIS wt312 57 PM Page 9
________.._.__.m.__.___--._m_ _ _ _ _ _ _ _ _ _ . _ _ _ _ - _ _ _ _ . _ _ _ - _ - - _ - _ _ _ _ m __ _ _ _ _ =_m- -. __.
~* #
A A B C D E F G H I J K '
L OITS S Type Description W St Code Eng Sulmoit haamit DreR to to PWIC(nr OfTS 8 Actlen R Code DraR(Date) Final (Dese) NRC(Dele) #) (Y#1)in
~
~
' ~
MTGO SUBJECT.NRCCOMMEETSINT'E 4519 H P600ST NDARDSAFETY Acton SARO15 SUIdhi5Kemper~ 4559 ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W Loss d Coolers Acddards (15.6.5)
~~'
4520 'MiUO SUEUE NRC COMMENTS ON THE AP600 STANDMUSAFETY Acton SAR O1 SARO15Kemper 450 ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W Loss of Ceciert Acddents (15.6.5)
Large Break LOCAs
- 49. Provide seducal bases for me tweak sue of 1.0 R2 mal was used as the
~ ~ ~~ ~ '
4521 ~~MTGO~ CT: NRC COMMENTS ON THE AP600 STANDARD SAFETY ' Action SARO15 55Cf555Kempi 4521 ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W Loss of Coolard Acciderts(15 6.5) tage Break LOCAs
- 50. Fgures 156.5A-1 through 64 lor the anefyecal resuas of a LBLOCA weie
~ ~ - - - ~" -' ~ ~~
4522 MTG U T NECOMMUdSONTHE AP600 STANDARD 5iFETY Adon SARO15 SMidht55rnper ~4522 ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W Loss of Cociant Acadents (15.6.5)
Large Break LOCAs
- 51. hem (a)(1)(i) of 10 CFR 5046 requaes that
- ECCS coolry 76 . .
pomanance anust be cal _ , _ _ __ _ _ , _ , . _ _ _ _ _ _ _ _
4523 MTGO
SUBJECT:
NRC COMMENTS ON THE AP600 STANDARD SAFETY Acton SAR GIS SARO15Cartn 4523 ANALYS:S REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W ATWS(SSAR 15 8)
- 52. Pretorm an ATWS analyss and relude me results mihe SSARio
_77 . . . _ .. . _ . _ .demoruerale fut the AP600 response is wemm me bounds to 4524 MTGO SUEUECT: NRC COMMENTS ON THE AP600 STANDARD SAFETY Adon SARO15 SARQ15Kemper 4524 ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES W Shukban Rism Assessmord 53 To address Open hem 1002 m the DSER regardng the need of 70 880'"88'c contemmerd % W msalsty related _
Action TRUMP TRUMPK)stemeder_ _ _ _ _ _ _ _ _ , _ _ , _ 22-May _ ___22-May 2612 2612 RAIO WCAP 14206(NOTRUMP CAD) 440.339 On Page 4-16, som 2. it a stated that smaa rm anange to the W numercal sdiame has been made to NOTRUMP mal no nodmg nor trne step studies are needed. The INEL dsagrees adh the stasemert. Sece me 79 -shd per 005 wk31237 PM Page 10
_ . _ m __ _ _ _ , _ . . . . . _ _ m. . . . _. - -- . . _ . . . . m _
'. r
^
A A B C D E F G H I J K L OfTS s Type Deectlpalen W St Code Eng Susandt Seemt DreR to toImc(IIr OfTS s Acelan E Code Druit(Dees) Fhiel(Dete) leRC(Dele) 8) (Ytlllin
~ '
~ ~ ~~~ ~~
'RAld '
- ~~ '
$138 RAi NOTRUMP'FNAL'V4V EPORT.WCAPI 1480 Aiton T'R U5dP ~TE.AIPiOsterred ' ~ 5U0' 440 599 W The report needs to doosnart me spar
- pudgemeras:riado by the Wesanghouse anesynes of me veney of eacn moeted code model.
80 _,
Adda Lamy. men moup Weeanghouse a mahog an Apperwha K samma __ __ .__ .._ __. _ _ ._ _. ;
5139 RAIO RAI NOTRUMP FMAL V4V EPORT, WCAP 14807 Achon TRUMP _ _ _ ___TRUMPOslemeder___ 2744ay 274 day 5139 440 600 W Seckon 322 ema== the vehday of me Yeh awrelahon used m the < flus modellor cose Goodng. It b*anaa stat the valusty of me model s shoum in 8I 5140
,RAIO._RAL _f*88'eru NOTRUMP 34FNAL Retsience MWCAP V4V EPORT, was 14807 set _Adeon
_ , _ _ .-_ TRUMP TRUMPOstemeder 27 May _ , , _27-May 5140 440 601 W Sechon 3 2.5 states that * ..CCFL s awredly predicted by NOTRUMP ' tw.d men a amtmuss to say met * . NOTRUMP we tend to presa more Imkhe of O2 _.Iqmd; man mecated_by data [ Phnase rna _ _ _ _ _ . _ _ , _ _ _ _ . _ _ , _ _ , _. .. , _ .__
5141 RAIO RAL NOTRUMP FNAL V&Y EPORT, WCAP-14807 Achen TRUMP TRUMPostameder__ 2744ay 27-May _ _ , , _ .5141 440 602 W
%*nn 3.34 stales mat the Aow reversal posit preertad by NOTRUMP occurs at a lower vapor Row men s*anad by its data. Does tus
_03 consagers decepancy kukcale met me W $4 Aux . , _ _ _ _ _ _ _ _ , _ . , _ _ , _ _ _ _ _
__ _.__RAIO 5142 RAL NOTRuhr FNAL V&V EPORT, WCAP 14807 Achon TRUMP TRUMPOstemoder 5142 440.603 W These are two apparenNy intxinselert references to Figure 3.4-11 m Sechan 3.4. The frst referencs is at me bouom of page 3.4-2 and I appears to refer 88 . _ _ _
to a t ipre mal has been omdled. The sec _ _ _ _ _ _ . , _ , _ _ _ _ , ._ _ _ _ ._ _ , _ , _
5143 RAIO RAL NOTRUMP FNAL V&V EPORT, WCAP-14807 Aden TRUMP TRUMPCssemeder 5143 440 604 W 85 ~
Please add cordanwus to earenn 3.4.
5144 RAIO RAL NOTRUMP FNAL V&V EPORT,WCAP-14007 Achon TRUMP TRUMPCstemeder S$44 440.605 W Figure 5 4-18 shows a step change m me PE5W desa uhrti appears erroneous. Tha was not dan = cad m sie text. Inclueng the step mange
_8$ _ _ _ _ _. . . _essorts me scale of me peat. _Pl_ ease redraw the plot e .__
5145_
5145 RAIO RAL NOTHUMP FNAL V&V EPORT, WCAP-14807 Achon TRUMP TRUMPOslemeder 440 606 W t The Weshnghouse response to RAI 440 440 states that," thermal strevvi efieds o the CMT are not odertshed as a specshc thermal hydrauhc 87 yb. on the fnal smal tweak LOCA PIRT mart
- r 1
Oils wk312.57 PM . Page 11
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _____ _-__-__- - -_=-___- ___-_
~. r A
A B C D E F G H I J K L OITS e Type Deecstpeten W St Code Eng Sespit Siemit DreR to loImc(nr OITS # AcdonN.
Code Draft (Dese) Final (Date) NRC(Dete) a) (WN)in
~ --
~- ~ ~
5146 '~'RAIO~ RAll NOTRUMP F54AL'V&V REPORT,'WCAPA480i ~ Achon' TRUEIP T' RUMP U ~ 514C 440 607 W None d tw NOTRUMP rhearis (CMT test, SPES, nor OSU) pread the CMT tenewalure destiellon oliserved a the test dele. In Ine integral faciety E senulatens tus has caused delays e to saast __. ____ _ , _ , _ , _ __ . _ _ _ , _ , .
.__MTGO_ . _ _ _ RAl.
5147 . Mesen0 Open tem Action TRUMP TRUMPDslemeder 5147
- 1) Indues copes of appropnele RAis and lhe "badugrotar summary a the W Anal verson of the NOTRUMP V&V Report (to be issued m*==ymnt to the !
E __.MTG O_rat:. Moseng . _ ..ACRS meseng) _ , _ _ _ , ._ _ _ _ _ .__. _ . _ , _ _
5148 Openitem Adon TRUMP ._TRUMPostemeder $148
- 2) inarporate RAI 440.480 and 440.481 riso tie text of the Inal V4V report W 90 (lo be ==d **iaarr=re to tie ACRS mostmg) - _- - --- - - - - - - - - - -
$170 __RAIO. _ _ _ .RAl: NOTRUMP FINAL V&V REPORT,WCAP-14807 Achon TRUMP TRUMPOstemsoor_ . _ _ _ _ ..__ _ _.. 5170 440 608 W lt appears that the NOTRUMP model of tie SPES tacahiy may interestrnese to ambers losses and overesamese to heet ransfer bsNeen the primary and tie secondary. This shotAd be ihmmend in more d ,
~ ~~ -
51 [1 ~50 ANOTUEE.VSV REPORT,WCAP-14807 Adon TRUMP TRUMPkEarr$ der- 5171 ,
440 609 W The Weshnghouse response to RAI 440.489 ndicales met twvtahrainvi studes would be performed Ic assess ways olinpovmg PAHR host transfer E . . _ _..._ _and the resues would be preserved a to Anal v&V report
_ TRUMP Achon TRUMPCssemeder_
5172 5172 RAIO RAl- NOTRUMP FINtLV&V REPORT WCAP-14807 440 610 W The ? J_ e - response to RAI 440.504 pomis att mal using a dieck valve conneded between sie ADS 13 ine and i ;26 pressure to E _ _ . _ _.regenert sie wecuwn breeler was ineNedee A more accurat RAl. NOTRUMP FINAL V&V REPORT, WCAP-14807 Acton TRUMP TRUMPOslemeder _ ,_ __5173 5173 RAIO 440.611 W RAI 440 $10 asks for an explanshon for why te NOTRUMP code overpredds the tRWST rigochon now rases dunng the early part of IRWST 94 rigadon. Theii 64 - response ruscales that ths is caus _ __ __ _ _ _ _ _ .._
RA!: NOTRUMP FINAL V8V REPORT, WCAP-14807 Achon TRUMP TRUMPOstemeder 5174 5174 RAlO 440.612 W The OSU model does not victuds ambent losses from the steam generator secondary An explanahan shouh! be provided to justdy why thes is 95 = vable OIIS wk312.57 PM Page 12 i
4 A
A B C D E l F G l H l t J l K L oft 5 s Type Descripeon W St Code Eng Sutset Simmit Dren to to NRC(Igr OfTS e Action H.
Code Drift (Oste) Final (Oste) Mtc(Dese) s) (Yaq hi
~ ~
5175 R40 ~ RAI NOTRUMPIINUV&V MPO5T.WCM714807 Acd TikMP TRUMPCstemader '5175 440 613 W On page 731-3," ._ ; stales that me NOTRUMP calculahan robes !
cacesswely on steem generoser host transfer twam of kra PAHR heat 26,,, tr.ansler _ Onpage 731-7 in me re-em el Fgu_res 7. _ __ _ _ _ _ _ _ _
5176 _.RMO, _ , , RAL NOTRUMP fetal V&V REPORT, WCAP-14807 __,_
AdenTRUMP TRUMPOstemoder_ _ ._ _ _ _ 5176 440 614 W At the bottom of page 731-5 and for endi of me SPES test analyses, J. , - says met me y head dose not dram properly a me 17 . ._..NOTRUMP model ha d (Memnoes h me mihel upper head _ __ .
5177 RMO RAl NOTRUMP FINAL V4V MPORT. WCAP-14807 Aden TRUMP TRUMPCstemoder_ , _ _ _ 5177 440 615 W As of the SPES and OSU NOTRUMP red *=u have a protAwn that !
whenever any weler ereers me cota legs a passes y me balance knes. The l M . 8'*'Ph ucaer Y a urase. Is the due to detonncias 6 _ _ _ _ _ __ _,__ _ __ ___. _,_ . . . _ _
5178 RMO Ri< NOTRUMP FINAL V&V REPORT. WCAP-14807 Adion . . . _ _ _ _ TRUMP TRUMPostemoder_ __ 5178 440 616 W Fagures 733 27 and 28 show that NOTFIUMP conuderably underpredds me ADS Sow bd on page 73 34 the test says lhet he agreement a reasonsbie M . . .. . . __.
.Please reevaluate thshdyment __ .___ _
5179 RNI rat NOTRUMP FINAL V&V MPORT, WCAP 14807 Aden TRUMP TRUMPostemoder _ - .5179 440 617 W i On page 733-7 me decuesson of Figure 733-39 says met me secondary level for steam generator B m me test is not avadable. However, me steam 100 generasor B level does appear on the plot. Pio
.__$180__
5180 R,*JO RAL NOTRUMP FINAL V&V REPORT, WCAP-14807 Aden TRUMP TRUMPCstemoder ,
440 618 W ,
On page 73 4 2 Weese@ouse merely says met me cold leg terigerature is t ^ '^- There is no mam of why. Piones proude me reason 101 why_ , _ _ , _ __ __
Achon TRUMP TRUMPOslemeder 5181 5181 RNO RAL NOTRUMP FINAL V&V MPORT, WCAP-14807 440 619 W t On page 73.4-4 Weste@ouse stales mal the portormance of accumulator B e unemportant However. 4 appears that an ovesprenden of the amumulator E . . _ __ ...
_.B A____w o causes CMT_ B h to be unduly h RAL NOTRUMP FINAL V&V MPORT, WCAP-14807
,_Aden TRUMP TRUMP!Ostemeder,__,__ __.
5182 5182 RAIO 440.620 W t
On page 73 4-4 Westinghouse states mat the dowmcomer level s overpredded wehod explanatxn Then i is staled that the preddions are 103 ** The seemert to data ====s to be meumal N l I
OtIS wk312.57 PM Page13
A i r
A i B C D E F G H I J K L [
OITS s Type Desc4elen W St Code Eng Seemt Saeedt Draft to toINIC(nr OITS e Acelse E Code prest (ones) Final (Om) 951C(Om) s) (Y4flin
_I_ __ _ . . __ ..
_ _____ _ . . _ _ _ _ _ _ _ _ _ . __. OITS , ;
RAIO 5183 RAI. NOTRUMP FINAL V&V MPORT, WCAP-14807 Acton TRUMP TRUMPOslemeder 5183 440 621 W On page 73 4-5,m to h==siof Fepse 73 4-21 Westrighouse pomis om some consolerable petisen usi to agreemere of to NOTRUMP :
1,04 .. ,_ _ _ . .
pr=*r==i and the test dose he does not esciss the cause o RAIO 5184 Acton TRUMP RAl. NOTRuhr FedAL V&V REPORT.WCAP 14807 TRUMP [Ostemoder SiU ;
440 622 W I in Fagure 73 4-24, the speemere bedueen to NOTRUMP preechan and tie l
test data appears to be scenet. Pinese provide en espionston ansor a now
~~
51Il5 RAU)I RAI RUMP FINAL Vav MPORT,WCAP-14807 Adon TRUMP TRUMPOsterneder 510'5 ~ r 440 623 W At sie top of page 7.3 44. Woolmghouse says tot NOTRUMP underpredicts the douncomer vouang. Thz is only true lor sie heuler part of the 106 doumcom_er Voenng in the armular part of to donnameri _ _ _ _ ,__ _. _ _ . _ _ . _ _
_ _ _ .RAIO_ . . . _ RAl: NOTRUhr FINAL V4V REPORT, WCAP-14807 5186 Achon TRUMP TRUMPOslemeder 5186 440 624 W '
On page 73 44 Westeghouse says lhet Figure 7.3.4 32 compares the PRHR heat transfer but proveles no **=a===ri. Please Ana== to reeuts E ..
shoun c tus_lgure. _ .
_. _RAIO 5187 RAL NOTRUtr FINAL V4V MPORT,WCAP-14807 Acton TRUMP TRUMPOssemeder___ _ .,_ _ _ .5187 ,
440 625 W The resuas shown m Figure 735-11 are ques dearert kom osier tests. !
105 __ _
$188 RAIO_ .RAl. _ _NOTRUMP
_ _PIsame FINAL VSVprovide MPORT,an capimeon WCAP- 14807 d twee h Aden TRUMP TRUMPOslemoder 5188 440 626 W t in as of Wie NOTRUMP cahasamris for OSU tie estreuhon of Sted n Wie vessel a shamed when congiesed to tie test desa_ The enariamanneareloves M. _ . , _ _. _ _ s consealerely low and sie domncomer level is ____. _ __ .. - - - - - -
5189 RAIO RAL NOTRUMP FINAL V&V REPORT,WCAP-14807 Aden TRUMP TRUMPOslemeder ---5189 440 627 W in Figure 8 3.1-22. NOTRUMP 1 ' = the CMT 2 recsculehng Row ,
raie. Ths could be en sted of Bis leaky diedt seine m to NRHR system.
~ ~ ~ ' ' ' ~
5150~RAIO NO FINAL V4V REPORT,WCAP-14807 Aden TRUM/ TRUMP M ~ ' 5190 440.628 W 6 in the escussen of Figure 8 31-27,'l f ~ sayslhetno mrv b unns can be draurt ADSt-3 Row s a teghly<arted PIRl som lor stud: the abety 111 of NOTRUMP must be assessed f._;1== pom i
OIIS wk312.57 PM Page 14 F
A A B C D E F G H I J K L OfTS 8 Type Desc@elen W St Code Eng Seems seemit Draft to toImc(br OITS s Acelen E Code Draft (Date) Final (Dele) ImC(Dele) t) (Yag ht I._ . . _ .. _ - _ _ __._. _ . _ ___ _ _ _ _ .__ _ _ _ .
. _._O_I_TS _ ,
. _ _ .. . .RAIO- - .RAL NOTRUMP FINAL V&V REPORT, WCAP-14807 5191 Acton TRUMP TRUMP!Ostemoder_ _ _ . . . _ _ _ _ _ . __5191 440 629 W in Fagure 8.31-29. gio preessed teenk 80s a quae maccurale. t Wu, - esplebis Otet Ods is becoues actasmdelar weser reaches me '
.I.I.2 RAlO_ _RAL _ NOTRUMP
_ tweak. Pleene snet. e p of Rio NOTRUMP atWay AdentoTRUMP pr 5192 FWGAL V4V REPORT, WCAP-14807 TRUMPKhtsmoder 5192 440 630 W Please emptom tie sudean drops in Wie chamad secondary temperatures si 113 Fgure 8 31-38. i 5193 RAIO RAI NOTRUMP FINAL V&V EPORT,WCAP-14807 Acton TRUMP TRUMP /Osterreder 5193 440 631 W Pteese saw some cor=Mwws ham Figures 8.3.1-42 and 43. Why s the D ...
. . _ ..r*w tesgerature fuWi? Condd pas cause tie low cose levet?
Adon TRUMP 5194 j
5194 RAIO RAi. NOTRUMP FINAL V4V EPORT, WCAP-14807 TRUMP /Ostemoder 440 632 W For OSU test $823 lhe tweak area was not the area ollhe instaged orthca How ed Bus happen? What was the tweak aree? Is tus rotated to tie
$ pmMern weh sie break area e sia ,_^ -- of les _ __ _ _ .. _ _ _ _ , _ _ . __ , _ _ _ . , _ _
5195 ._RAlO__ RAL NOTRUMP FINAL VSV EPORT,WCAP-14807 Adon TRUMP TRUMP /Ostemoder 5195 440 633 W .
in wie rennervi of OSU test SB23 on page 8.32-3, Weserqpiouse manhons t
that tie test dela appears to have toimd a source al vapor fiel tems Sie i
.I.I$ . . _.. . _ . _ _ _ ..tihas 61 steam generator 1. Is the feel? Could et 5196 5196 RAIO RAi: NOTRUMP FINAL V4V REPORT,WCAP-14807 Aden TRUMP TRUMP /Outomoder 440.634 W These is some cordueson other m the tout or m sio Figure labets tor Figures 83.24 Viroupt 9. Steam generator 1 and steers generator 2 may be I17 swecfied -
5197 519E5AIO rat NOTRUMP FINAL V4V REPORT, WCAP-14807 Acton TRUMP TRUMP /Ostemoder 440.635 W The,e are many proMan. wan OSu Met Ss23 pan e. Me nses ar,i t.
redsarwi). CredtWay of Wie knel V&V is danmehod by tie "J_ _-Jz
_I I.8 _
__RAIO_ _RAL _ ..ctmen tiet V4V there is resenneMe agmement tndween N NOTRUMP FINAL REPORT, WCAP 14807 Acton ,. TRUMP TRUMP /Ostemoder 5198 5198 440 636 W ,
119 Please provide an esplanason of sie poor agreement in FsDure 8.3.3- 40. ,. _ .
RAl NOTRUMP FINAL V&V REPORT,WCAP-14807 Adon TRUMP TRUMP /Ossemeder_._ _ . _5149 5199 RAIO 440 637 W in Fagure 8.3 4-5 the tiow Irom aaumulator 2 allects the Row tram CMT2 lar 120 more o the NOTRUMP red =sen stan in the test. Please T-m OliS.wk31257 PM Poge 15
. . .. _. _ . _ _ . . . _ . . . _ _ _ _ .m . m_.m .- .- .__ . . . _ -- . . __ .. _ .m
. . . . . ~ . < _ . _
- . t t
A
- A B C D E F G H I 'J K I L 0115 t Type Dee@ W St Code Eng- Satunit hahans ' Dren to to emC(nr OITS 8 Acmen R.
Code Draft (Dese) Fleel(Oste) IIRC(Dees) 8) . (VA$ in +
~ -
5200' RAIO RAiNOTRUMP}M&V EPO5T WCAP 14807~ khon TRundP UEIPostemoder ~'5200 440 638 W i On page 8 3.44 at sie and of parayaph 1 and to begmng of paragraph 2 ;
no condumens mese teen agoning ADS 1-3 Row. Please documers anal causes sie docupandes in ADS 1-3 Sow. tweak Bow.
' ~ ' '" ~ ~
5201 RAIO ~ RANUTkAF FINALV4V EPNWUP 14807 ~Acton TRUMP 5 EMP U 5201 440 639 W These a a permetent problem m boti SPES and OSU NOTRUMP chdahnq$
caused by weder ereenng Bio cold legs uhen viere is to weser tiese m sie 3 . _ .
. . . _ . _ tests Whydoesseshgpen? Canyoupresortconpan _
,, _ , _ , ,TRUMPCssemeder_ _ , , . _
$202 RAIO RAL NOTRUMP FINAL V4V REPORT, WCAP-14807 Acean TRUMP 5202 440 640 W On page 8.3 5-4 Wesempiouse h- Flpees 8.3.510 and 11 and posts out Stat the ceded behauor of tie beience kne loved is inong beyond 123 1500 s Yet 7. _ ___ j -- states pial NOTRUMP pseet . _ __ _ _ _ _ , _ ___ . _ _ .
Adion TRUMP TRUMPCstemoder_ , _ _ 5203
$203 RAIO rat NOTRUMP FINAL V&V KPORT, WCAP-14807 440 641 W On page 8.3 6-2 m tie somnd paragraph, tie c* dan =d behawor of CMT16s ;
very ddlerent from tio lost dela Why? What does tes say about 124 NOTRUMP? t 5204 RAIO rat NOTRUMP FINAL V&V EPORT. WCAP-14807 Aden TRUMP TRUMPOstemoder 5201 440 642 W 5 in Rio last paragraph on page 8.3.6-3. 55 somnds a wrong Perhaps t ,
L25 ___
should be 5.5 seconds _
.RAIO RAL NOTRUtr FINAL V4V EPORT, WCAP-14807 Aden TRUMP TRUMPOstemoder 5205.
$205 440.643 W The mmmeras cortamed m RAls 440XXX tvouWt 440.YYY ase amarnpies of I
areas m sie Anal V&V unsre henvis do not appear to be adata*
3 __ . . _ _
Please 1. _ _ __ lhe analyses psesented m Sie Anal V&V Acton TRUMP TRUMPCstemoder 5206 5206 RAIO RAL NOTRUMP FINAL VSV EPORT.WCAP-14807 440 644 W !
For each case whose pie quandt model was used, a musure level plot should be gwerkwi tial shows tio cahdahno seguAs weh and uWiotd tie quench 127 model Please ear
- Wie guidehnes tial shotAd i
OllS wk312.57 PM Poge 16 i
A A B C D E F G H l I J K L OITS 8 Type Desc@elen W St Code Eng Sdet Sutuait Draft to 1o NRC(br OITS 8 Action E Code Droit (Dete) Final (Dete) NRC(Dete) f) (YAI)in 1 OITS 4634 MTGO RAI WCAP-14171, REV.1 WCOBRNTRAC APPUCABEUTY TO AP600 Achon WCT WCTKemper 16&y 19Wy 4634 LBLOCA W Returance 1. L E. Hodweser, et al, WCOBRNTRAC Appar**y to AP600 Largellreek Loes<if Cosient Accelert, WCAP 14171P, Rev.1 Odotww1996.
128 .
The losong_9e reisiolo t _ _ . _ _ _ _ _ _ _ _ _ _ _ _ __ . _ _ .. _ _ . _ _ _ _ _ _ . _ _ . _ _ _ _ _ __
4635 MTGO RAL WCAP-14171 REV.1 WCOBRNTRAC APPUCAB4UTY TO AP600 Achon WCT _.WCT*anper_ _ _ _ _ _ . 16-May 19my 4635 taLOCA W Referenz 1. L E. Hodvener, et al , WCOBRNTRAC Apreeddy to AP600 Largelbreak Loesd Cocient Aoddert, WCAP-14171P, Rev.1 Odober 1996 M _
NOTE: The quashons are based on t
__MTGO._
4636 RAL WCAP-14171, REV.1 WCOORNTRAC APPUCA84UTY TO AP600 Adeon WCT WCTMerrper 16 May 1SMay 4636 LBLOCA W Reference 1. L E. Hodweder, et al, WCOBRNTRAC Anpr**y to AP600 Large Break Loesd Coolers Arxadent WCAP-14171P, Rev.1, Odote 1996.
I.E NOTE;_The questens are based on t -
- . _ . . -MTGO. _ _ _rat 4637 _ WCAP-14171 REV.1 WCOBRNTRAC APPUCABluTY TO AP600 Adion WCT WCT*emper 16 M y 19May 4637 LBLOCA W Reference 1. L E. Hodvener, et at , WCDBRAfTRAC Apped*y to AP600 Large4hreak Lossd Cooiert Acudent, WCAP-14171P, Rev.1 Odober 1996.
_I.3.1 ._. .
NOTE: The 9% are based on t __ __ _ _ _ . ____ _
4638 MTGO_._ RAI WCAP-14171, REV.1 WCOBRNTRAC APPUCABluTY TO AP600 Adon WCT WCT*enper 16-May 19 % y 4638 LBLOCA W Redesence 1. L E. Hodweser, et at, WCOBRA# TRAC Apphcabmy to AP600 Large4hreek Loesd Coolert Aazdort WCAP-14171P, Rev.1, Odober 1996.
132 NOTE: The quashans are based on t_ _ _ _ _ _ _ _ _ _ _ . _ , _
4640 MTGO RAL WCAP-14171, REV.1 WCOBRNTRAC APPLICA84UTY TO AP600 Acton WCT Novendstern\WCTweroper 16&y 19&y 4640 LBLOCA W Reference 1. L E. Hodvener, et at, WCOSANTRAC Appr**y to AP600 Largelbreak Lossd Caolart Aazdort, WCAP-14171P, Rev.1 Odober 1996.
133 Relerence 3 B Boysi.et a!,
Oils wk312 57 PM Page 17
, m . 1 - _
~
. , 2 A
A B C D E F G H l 8 J K L OfTS 8 Type DescW W St Code Eng w Sedunit Draft to to 85tC(ser OITS # Acelen E Code Draft (Dees) Final (Dete) leRC(Dele) f) (Y20)in
~~ - ~~
EWCT
~
" ~ ~
4641 'MTG'O ' RAl[ WCAP 541E1,'REV.1 WCOOFWTfUdAPPUCAIEUETO AP600 WCTs h ~~ - ~76hy~ tiu[ 4641 LBLOCA W Relerenm 1. L E. Hoovener, et at, WCOBRA/ TRAC Appheawy to AP600Large&eekLosedCoolard Acadent,WCAP-14171-P,Rev.1, Odober 1996.
3 .__
. NOTE: The quashons are bened on t _ __ _ ._. ., ,_ _ _ _ _ _ _
4642 MTGO- . . .RAL
. _ WCAP 14171, REV.1 WCOBRA/ TRAC APPUCABE.!TY TO AP600 Adon_.WCT WCTMemper _, , , _ , _ _ , _ 16&y 19 May __4642 LBLOCA W Reference 1. L E Hochroter, et at, WCOBRA/ TRAC Aprer=wy to AP600Large-BroekLoesdCoolard Acadent,WCAP-14171-P,Rev.1, s October 1996.
3 . _ . .. _ _
Reference 4. B. Boyedt, AP600 L _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ __
4643 MTGO RAL WCAP-14171, REV.1 WCOBRA/ TRAC APPUCA81UTY TO AP600 Adson WCT WCTMemper 16&y 1944ay __4643 LBLOCA W Reference 1. L E. Hodweser, et at, WCOBRA/ TRAC Apg*cawy to AP600 Large-Break Lossd Coolard Aamdert, WCAP-14171-P, Rev.1, Odober 1996.
3 NOTE: The questions are based on t RAL WCAP-14171, REV.1 WCOBRA/ TRAC APPUCA8luTY TO AP600 Aden WCT WCT*emper 16-May 19 May 4644.._____
_ _ _ _ .._MTGO 4644 tsLOCA W Referenm 1. L E Hodweser, et at, WCOBRA/ TRAC Appbrewy to AP600 Largeereak Lossd Cooient Aaadert, WCAP-14171#, Rev.1 Odober 1996.
337 NOTE: The rpms=vis are based on t ._ _ _ _ _ _ _ _
4645 _MTGO__ rat WCAP-14171, REV.1 WCOBRA/ TRAC APPUCASIUTY TO AP600 __.WCT Aden WCTAemper 1644ay 19&y _.4645 LsLOCA W Reference 1. L E. Hodvener, et al,WCOBRA/ TRAC Apg*cewy to AP600 Largeereak bassd Coolant Aasdort, WCAP-14171-P Rev.1 Odober 1996.
IM NOTE: The rpasnvis are based on t _ _ _ _ _ ._
4646 MTGO RAL WCAP-14171, REV.1 WCOBRA/ TRAC APPUCABiUTY TO AP600 Achon WCT WCT*emper 1644ay 19 & y 4646. _ _ _
LBLOCA W Reference 1. L E. Hodreder, et at, WCOBRA/ TRAC Apg*cawy to AP600 Largeereak Lossd Coolart Aaadert, WCAP 14171-P, Rev.1 October 1996. !
l39 NOTE: The questons are based on1 Oils wk312 57 PM Page 18 1
r
.- . . . - - ._ _ _~ . . --
~. . +
. A A B C D E F G H I J K L OITS e Type Doncription W St Code Eng Siende Seemit Draft to toIRC(nr OfTS s Action E Code Draft (Dele) Final (Dete) MRC(Dete) s) (YM)in 5;T
~
4647 MTGO ~ 'RAliWCAPIUI7[HEVlWC00EVERAC bhLICAikUNTO AP650 Amon WCTM 25da'y' E5hy ~~d 46 '
LBLOCA W Reierence 1. L E. Hodneter, et at, WCOBRNTRAC Appbremy to AP600 Large4 beek Loesd Coolant Amrennt. WCAP-14171P, Rev.1, Orenhar 1996.
3 _
NOTE: The questens are bened on t __ __ _ _ ,_ _
4648 MTGO. . . _RAL WCAP-14171 REV.1 WCOBRNTRAC APPUCABIUTY TO AP600 __.WCT Achon WCTAsmper _ _.16 % y 19-May _,. _ _ .4648__
LBLOCA W Reierene 1. L E. Hodneter, et at, WCOBRAfTRAC Apphr*my to AP600 Large4heek Loesd Coolard FM WCAP-14171-P, Rev.1 Odober 1996.
M . _ _ .. _ _ _. NOTE: The quesmans are based ont . .__ __. ___ _ __ . _ _ _ .
4649 MTGO RAL WCAP-14171, REV.1 WCOBRNTRAC APPUCABlulY TO AP600 Achon WCT WCTKamper 25&y 25&y 4649 L8LOCA W Reference 1. L E. Hoduoder, et at, WCOBRA/ TRAC Appbrahmy to AP600 Large-8reak Loesd Cooient Amreart,WCAP-14171P, Rev.1 Ornahar 1996.
30 NOTE: The quashons are Won t ___ . _ _ _ _ _ _ , _ .. .__
4650 _MTG O. _ _ _rat WCAP-14171, REV.1 WC00RAfTRAC APPUCABluTY TO AP600 Amon WCT WCTMemper 25My 25%y 4650 LBLOCA W Reference 1. L E. Hodvener, et at, WCOBRATIRAC Apphr**y to AP600 Large4 reek Loss 41 Canaart Amre=rit WCAP-14171P, Rev.1, t Orenhar 1996.
NOTE: The trashmis are hased onI RAL WCAP 14171, REV.1 WCOGRNTRAC APPUCA8luTY TO AP600 Adion WCT WCT*emper 16my 19 May 4651 4651 _ _MTGO
- L8LOCA W Reierence 1. L E. Hodweder, et at, WCOBRNTRAC Apphr**y to AP600 Largnereak Loesd Coolert Acxadert, WCAP-14171P, Rev.1, h 1996.
3 .
NOTE: Thequestersarebasedont _ ___ _ _ __ _ . _ .
4652_MTGO RAL WCAP-14171 REV.1 WCOBRNTRAC APPUCABiUTY TO AP600 Acton WCT WCTKamper 16 & y 19&y 4652 LBLOCA W Reference 1. L E. Hoctreser, et at, WCOBRNTRAC Apphremy to AP600 Largsereek Lossef Coo' ant Amstart, WCAP-14171-P, Rev.1 Odober 1996.
845 NOTE: The questaans are based onI i
oitS wk312.57 PM Page 19
~ m_. m. _. _ . . . . . - - .- . m _ __ .- -
s A
A B C D E F G H I J K L i OITS s Type Desc411em W St Case Eng Sutaset Siendt Drento Action y_
seImc(nr 08T5 s ,
Code DreR(Dese) Final (Dete) IIRC(Dete) 8) (Mlle l._ . . _ _ . _ . _ _ _ . . _ _ _ _ _ _ _ _ . _ . . . . . . _ _ ._ _ _ _ . . _ _ _ .. . OITS j 4653 _.MTGO._ __ RAI WCAP-14171, REV.1 WCO8AAfTRAC APPUCA8luTY TO AP600 WCT Achon .._ WCTA(arnper 16-May -. 19&y
____ . _ . . . _. _ _ _ _ _ .4653 L8LOCA W Referena 1. L E. Hodueser, et at, WCOBRA/ TRAC Anper=M*y to '
AP600 Large-8 seek Laced Coolut Acadert WCAP-14171-P, Rev.1 ,
Ocsotier 1996.
le NOTE: The gsgebens age heaed ont
~
WCTh~
~
~
4654 MT52)I RAi~WCAP-14171, REV.1 WCOBRA/ TRAC APPUCABUTY TO AP600 Amon WCT 16 & y 59 k ' 454 {
L8LOCA W i Reierence 1. L E. Hodwater,et d.WCOBRArTRAC f er; to AP600 Large-8 seek Laesd Coolers Acadent WCAP 14171-P, Rev.1 ,
Orinhw 1996.
.I.i? NOTE: The 9mears are bened oni _ __ __
4655. __.MTGO. . _ _ RAL WCAP 14171, REV.1 WC00fwTRAC APPUCA00TY TO AP600 Amon WCT WCTACersper 16 % y 1944ay _,4655.__
L8LOCA W !
Roterence 1. L E. Hodweser, et al , WCOGANTRAC Apreraway to AP600 Largellreek Lonsd Cociert Acadert, WCAP-14171-P, Rev.1 October 1W6 I# _....._4NOTE: ThequashonsarebasedonI _ _ ___ . ___ ___
4656 MTGO RAI WCAP-14171 REV.1 WCO8fWTRAC APPUCA80TY TO AP600 Acton WCT WCTA(emper_ _ _ _ 16-May _ . _194Aay 4656 L8LOCA W Reierence 1. L E. Hodweser,et at, WCO8fWTRAC W to AP600 Large&eak Leesd Cocient Aazdant, WCAP-14171P, Rev.1 r
October 1996.
If NOTE: The ganskonsare bened ont
_ _ _ _ ...MTGO 4657 RAL WCAP-14171, REV.1 WCOBRAITRAC APPUCABUTY TO AP600 Acton WCT WCTA(emper 16-May 19%y 4657_
L8LOCA W Rotarance 1. L E. Hodvener, et at, WCO8fWTRAC Appar=May to i AP600Large&eakLoesdCooient Acdded WCAP-14171P,Rev.1 IM.
150 _
NOTE: The 9mstarts are bened onI 4658 WTGO rat WCAP-14171 REV.1 WC00RNTRAC APPUCA80TY TO AP600 Acton WCT WCTA(errper 4658 L8LOCA W Reterence 1. L E. Hodweser,et at,WCOBRAITRAC W to I
AP600 Large-Bseek Lossd Coolant Acadert WCAP-14171-P Rev.1 Odober 1996.
151 NOTE: The questens are based on t t
OIIS wk31257 PM Poge 20 i
_ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ __.__________.__________.______..__._.__.__._._____m_ .___
A
- A B C D E F G H I J K L OsTs s Type Desc1 peen W St Code Eng Subet Sdek DrsR to to NRC(nr OITS 8 Acton E Code Draft (Dees) Final (Dete) NRC(Dele) #) (YJN)in
~ ~
~ '~ ~ ~
MTGO 4659 'RAl- WCAP-14171 REV.1 WCOBRNTRAC'APPU' CABILITY TO A.P600 AIEon WCT UCTidnper 4659 tetOCA w Reference 1. L E. Hodweser, et al., WCOBRNTRAC f A ye**y to AP600Large&edlaesdCootent Accusert,WCAP-14171-P,Rev.1 October 1996.
I.52 4660 MTGO. RAl:
_ _WCAP-14171,
., NOTE,_The 9mhansTRAC REV.1 WCX]8RA/ se based APPUCABE.lTY onI TO AP600 WCT
_4660 _ , _ _ _
Actum WCTMemper 2iMay 254Aay LBLOCA W Referenz 1. L E. Hochreeer, et al., WCOBRA/ TRACf A skw*y to AP600 Large&eek Loesd Coolers Acadert WCAP 14171P, Rev.1 October 1996.
153 NOTE: The 9mmans are based ont _ .
4661 MTGO RAl WCAP 14171 REV.1 WCOBRNTRAC APPUCABluTY TO AP600 Achon WCT WCTAernper 25-May 25-May 4661 taLOCA W Referenm 1. L E. Hodvener et al., WCOBRNTRAC Apf***y to AP600 Large-Break Lossd Cc w i Acx*sent, WCAP-14171P, Rev.1 Odober 1996. !
.I.$4. .
NOTE: The rpmeans are based on t ___ _
+
4662 MTGO RA!: WCAP-14171, REV.1 WCOSANTRAC APPUCASILITY TO AP600 Aden WCT WCT*emper 16-May 19-May 4662 LBLOCA W ;
Reterenz 1. L E. Hoctueder, et at, WC00RNTRAC Afy*=he*y to l AP600Large-BreakLoesdCoolart Acadent,WCAP-14171#,Rev.1 Odober 1996.
155 _
NOTE: The 9mmans are based on t . _ _ , _ _ _ _ _ .. _ _ _
_ ._MTGO 4663 RA!: WCAP-14171 REV.1 WCOBRA/ TRAC APPUCABIUTY TO AP600 Achon WCT WCTEamper 1&May 19-May_ _ . 4663 LBLOCA W Relerance 1. L E. Hoctuener, et al., WCOBRNTRAC Apphcabdty W AP600 Large&eek Lossd Coolant Aassent WCAP-14171P, Rev.1, Odober 1996.
N ._ .._ _ _ NOTE: The 9mmans are based on t _ __ __ _. _ _ _ _ _ .__ . _ _ _ . ___
46M MTGO rat: WCAP-14171, REV.1 WCOBRA/ TRAC APPUCA81UTY TO AP600 Acton WCT WCT*emper 1&May 19 May 4664 LBLOCA W Reference 1. L E. Hoctroner, et at . WCOBRNTRAC Appfr**y to AP600 Large&eak Lossd Coolart Aandert WCAP-14171-P, Rev.1 Odober 1996.
157 NOTE: The 9-anns are based on t 0:IS wk312 $7 PM Page 21
. . . . . . ~ - . . . . . . _ . . .-. . - . - .-
A A B C D E I F G H I J K L OITSe Type Donatpelen W St Code Eng Submit Seemit Draft to toIIRC(Isr OIT18 Action H_
Code Draft (Dele) Final (Dete) teRC(Dele) #) (YAI)bt i
- OtTS-4665 'MTGO RAI WCAP-14171,REV.1 WCOBRNTRAC APPUCABILITY TO AP600 Amon WCT WCTAenper 25iay~ 25y 4665 LBLOCA W Reference 1. L E. Hodvaner, et at, WCOBRNTRAC Appicatnity to AP600 Lage4heek Loosd Coolant Acadert WCAP-14171-P, Rev.1 i Odober 1996.
3 NOTE: The quessons me based on t Aden WCT WCTMarnper 25 & y _ . _ _25%y
. _ _ _ _4666 4666 . . _ _ .MTGO. _RAL _ _ WCAP 14171, REV.1 WCOBRNTRAC APPLK:ABIUTY TO AP600 LBLOCA W Reference 1. L E. Hodweder,et at,WCOBRNTRAC M10 AP600Large-Broek LoosdCociert Acddert WCAP 14171-P Rev.1 Odober 1996.
M NOTE: The gestens are based ont _ _ _ _
WCT WCTAemper _ __ _.__ _25 May 25&y_ . _ _ _
4667 4667 ._MTGO. . _ _ . RAL WCAP-14171, REV.1 WCOBRNTRAC APPUCABluTY TO AP600 Achon LBLOCA W Reference 1. L E. Homreser, et at, WCOBRNTRAC AppicatWy to AP600 Large Break Lossd Coolers Acadert, WCAP-14171-P, h 1, Odober 1996.
160 NOTE: Tyheare based on t __ ,. . _. _ , _ _ _ _ , __ . _ _ . __.
4668 MTGO RAl- WCAP-14171, REV.1 WCOBRATRAC APPUCABluTY TO AP600 Achon WCT WCTEemper 25my 25&y 4668 LBLOCA .W Reference 1. L E. Hodweser, et at, WCOBRNTRAC Apparna*y to AP600 Large4 reek Lossd Coceant Acadert WCAP 14171P, Rev.1 Odober 1996.
3S1 _ . _ _ _._ _
NOTE- The rpm are bened on t __ .___.
4669 WTGO rat WCAP-14171, REV.1 WCOBRNTRAC APPUCA81UTY TO AP600 Achon WCT WCTMenpur 16&y 19 May 4669 LBLOCA W Reierence 1. L E. Hoereser, et al, WCOBRNTRAC Appicat!dfy to AP600 Larger 8 reek Loesd Coolant Acamard, WCAP-14171-P, Rev.1 Odober 1996.
162 NOTE: The speehons are based onI _
__4670 4670 MTGO rat WCAP-14171, REV.1 WCOBRATTRAC APPUCA86UTY TO AP600 Acton WCT WCTEemper 25%y 25%y
- LBLOCA W Reference 1. L E. Hodwener, et at , WCOBRNTRAC Appicabdry to l AP600Large-BreakLossdCoolard Acadert WCAP-14171f,Rev.1 Odober 1996 163 NOTE
- The queshans are based oni OllS wk31257 PM Page 22
~
A A B C D E F G H I OfTS 8 Type I J K L Description W St Code Eng Suennit Schmit Draft to to NRC(Ilr OtTS 8 Action E Code
~ ~ ~
Draft (Date) Fhal(Dese) NRC(Date) 8) (YAf)h 4671 MTGO RAI WCAP-1417I,REV 1'WCOBRNTRAC APPLICABluTYiO AP600 Mon WCT' 'WCTAiemper' ~
~
16Ay~' ~19dy
~
LBLOCA '4671' W
Heterence 1. L. E. Hodvener, et at, WCOBRNTRAC Appiubey 10 AP600 Large4heek Lass 4f Coolant Aamdent WCAP-14171-P Rev.1 Odober 1996.
34 .
, NOTE: The questons are basedonI 4672._MTGO RAL WCAP-14171, REV.1 WCOBRNTRAC APPUCABiUTY TO AP600 Adon WCT _ _ _ . _ . _ _ _ ._
WCTA(emper 25-May 25 May LBLOCA 4672 W
Relerance 1. L E. Hoctuoiler, et at, WCOBRNTRAC Appbcabety to AP600 Large&eak Lossef Coolant Acddent. WCAP-14171-P, Rev.1 Odober 1996.
I65 _ .. _ _ _ .NO3 Therrmarebasedent MTGO 4673 , _ _ _
RAL WCAP 14171 REV.1 WCOBRNTRAC APPUCABluTY TO AP600 Adon WCT WCTA(emper 25-May 25-May _ _ _ .4673 _ _ , _ _ _ .
LBLOCA W Reference 1. L E. Hoctweder, at al, WCOBRNTRAC App 6cabddy to AP600 Large&eak Loss <f Cootard Aaaded, WCAP-14171-P Rev.1, Odober 1996.
366 ._ . _ _ _ , NOTE (The pssions are based onI 4674 MTGO RN WCAP-14171, REV.1 WCOBRNTRAC APPUCABluTY TO AP600 Acton WCT WCTA(emper_ _ ,
4674 LBLOCA W Referenu 1. L E. Hoctvesar, et at, WCOBRNTRAC Apphcabey to AP600 Large&eak Lossef Coolart Accident,WCAP-14171f, Rev.1 Odcher 1996.
167 .
NOTE: The questens are based oni _
4675 MTGO RAL WCAP 14171 REV.1 WCOBRA/ TRAC APPUCABluTY TO AP600 Achon WCT WCTA(emper 16-May 19 May _.4675 LBLOCA W Reierence 1. L E Hodvener, et at,WCOBRNTRAC Appecabey to AP600Large&eak Lossef Cootart Actsjent WCAP-14171-P,Rev 1 Odober 1996 168 NOTE: The quashons are based on t 4676 MTGO RAL WCAP-14171 REV.1 WCOBRNTRAC APPUCABluTY TO AP600 Actxn WCT WCTA(enper 25 May 25-May 4676 LBLOCA W Relarenm 1. L E. Hodreder, et at, WCOBRNTRAC Apphcabey to AP600 Large-Break Lossef Coolant Acodont, WCAP-14171-P, Rev.1 Odober 1996.
169 NOTE: The questons are based on t OIIS wk312.57 PM Page 23
. A A B C D E F G H I J '
K L OITS # Type Description W St Code Eng Sutunit Stemit Dredt to to NRC(llr OITS t Action E Code Draft (Dete) Final (Dete) NRC(Dete) s) (YJN)ln MTda ' RAl'WCAP fil5REV71 WCOBRNTRAC APPLEduTY TU~id600
~ ~ ~
4677' Adon WCT WCT5emper-~ - ~~~ ~2544ay~'~ 25 May [677' LBLOCA W Reiersics 1. L E.Hoevener,et al WCOBRNTRAC Appirdmyto AP600 Large-Break Loosd Coolant Acadert, WCAP 14171-P, Rev.1 Odober 1991L
.I.70 Referena 6. N J. Operuto, We _ __ __ __ ___ _
__WCT 4678 ._MTGO_ ,._.RAL WCAP-14171 REV.1 WCOBRNTRAC APPUCABiUTY TO AP600 . Adeon WCTKamper_ , _ _ _. _ _ _ _ _25-May _ _.__. _ _25_May _ 4678 LBLOCA W Reference 1. L E. Hodveder, et al, WCOBRAITRAC Apphcatuity to AP600 Large4treek Loesd Coolers Acaders, WCAP-14171-P, Rev.1, Odober 1996.
$ _ _ .MTGO.RAI. _ .. NOTE: The q=*wis are based oni __ __ __ _ __ ___ _ _ ____ _ _
_._ ,_4679 4679 WCAP 14171 REV.1 WCOBRNTRAC APPUCABiUTY TO AP600 Aden WCT WCTmemper 16-May 19 May LEs.OCA W Referenm 1. L E. Hoctreser, et al, WCOBRNTRAC Apphcahdty to AP600 Large-Break Lossd Coolant Acadent,WCAP-14171-P, Rev.1 Odober 1996.
I72 . NOTE i __The @estons are based on L . _,_ _ _ _ _ _ _ _ _ _ - __ _- ___
__WCT 4680 , , _ .MTGO. _ _ , . _RAI
. WCAP-14171 REV.1 WCOBRNTRAC APPUCAB4UTY TO AP600 Aden WCTMemper 16-May 19-May 4680 LBLOCA W Reference 1. L E. Hoctroner, et al, WCOBRA/ TRAC Apphcatnedy to AP600 Large-Brook Lossd Cooient Acadent.WCAP-14171-P,Rev.1 Odober 1996.
3 __ _ _ _ _ . _ _ _ _ . . _ _ _ . ..___ _
4681 .___MTGO.RAI_WCAP-14171, _ _ _ .. REV.1 NOTE: The 9=dans WCOBRNTRAC are APPL.T.ABluTY TO based AP600 on Actont_ .WCT _ WCTMemper 4681 LBLOCA W Reference 1. L E. Hodroser, et al., WCOBRAITRAC Apphcabday to AP600 Largellreek Lossd Cocient Acadent, WCAP-14171-P, Rev.1 Odober 1996.
M __
- 7. S. Balorek, et al., Code Oua RAL WCAP-14171, REV.1 WCOBRNTRAC APPUCABILITY TO AP600 Adson WCT WCT/Kemper 4682 4682 MTGO LBLOCA W Reference 1. L E. Hodreaer, et at, WCOBRNTRAC Appirat*y to AP600 Large-Break Lossd Cooient Acadent WCAP-14171-P, Rev.1 October 1996.
I75 NOTE: The eachnns are based on OliS wk312 57 PM Page 24
". .P A
A 8 C D E G F H I J K L OITS e Type Descrtpelon W St Code Eng Seemit Siemit Draft to to MC(nr OITS # Acelon R.
Cosle Draft (Dese) Final (Dese) NRC(Dete) f) (YAI)h
~'
~
MTGO ! 1'4571[REVII'WCOBRAITRAC APPLICABlufY WCfifwrper ~
4683 RAi WCAP A TO' rd' AA' WW- ~ 25 7 May~ ' '255ay ~- '"i683 ,
LaLOCA W Reisence 1. L E. hadveder, et al., WCOBRA/ TRAC ApphcabMy to AP600 Large&sek Lass <d Coolert Accidert WCAP-14171 P.Rev.1 Odober 1996.
E
_.MTGO_ RAL...._. _.. NOTE: The 96APPUCABluTY are bened oni 4684 WCAP-14171, EV.1 WCOBRNTRAC TO AP600 Achon WCT WCT*emper 16-May ISMay 4684 ,
LBLOCA W Retnrence 1. L E. Hodveser, et af , WCOBRA/ TRAC Apptcatasty to AP600 Large-Brook Loosd Coolert Acadert, WCAP-14171P, Rev 1 Odober 1996 377 . ~ . NOTE: The 9mehans are based on t
.._MTGO._ RAL WCAP 14171, REV.1 WCOBRA/ TRAC APPUCABluTY TO AP600 4685 Achon_.WCT ___WCTMerrper 4685 LBLOCA W Reterenm 1. L E. Hodweder, et al, WCOBRA/ TRAC Apphr=wy b AP600 LargeBreak Lossd Coolers Aandert, WCAP-14171P, Rev.1 Odober 1996.
I78 NOTE; The quashons are based on t _ ___ _ __
4686 MTGO RAL WCAP-14171, REV.1 WCOBRArTRAC APPUCABluTY TO AP600 Achon WCT WCTMemper 4686 LBLOCA W Reeerenz 1. L E Hoctuator, et al, WCOBRA/ TRAC Apphcabity to AP600 Large&eek Lossd Coolard Accadert, WCAP-14171-P, Rev.1 Odober 1996.
I79 NOTE: The queshons are based on t __ _ _ _ _ . _ _ .
4687 MTGO RAL WCAP-14171, REV.1 WCOBRNTRAC APPUCABILITY TO AP600 Adion WCT WCT*emper G87 LBLOCA W Reference 1. L E. Hochrader, et al, WCOBRNTRAC ApptcatuMy to AP600 Large-8 reek Lossd Cootert Axisent, WCAP-14171P, Rev.1 Odober 1996.
180 . __
NOTE The quashons are tmed on t . _ _ _ ___
[
4688 , _ _MTGO RAL WCAP 14171, REV.1 WCOBRA/ TRAC APPUCABluTY TO AP600 Achon WCT WCT*enper _4688 LBLOCA W Reference 1. L E. Hodveser, et al.,WCOBRA/ TRAC Apger=wy to AP600Large4reakLossdCootart Acudent WCAP-14171-P Rev.1 ,
Odober 1996.
181 NOTE: The questums are based on t OIIS wk312.57 PM Page 25
-__-___-_ _ ____-___-__ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __-__v- _ _ _ __a - _ _ _ - _ . - - _ _ - _ - _ _ _ __ - - - _
. p.
A -
A B C l D E F G H I J ,
K L OITS s Type Descrtpilon W St Code Eng m m ua mp me mg Code Draft (Dees) Final (Date) NRC(Date) (YAq in
- )
~
4689 MTG O'~ RAl'WCAP-145b,REU1 WCOBRNTRAC APP 5Edl6TO AP600 Aden WCT WCT*emper
~~ ~ ~~ ~
4689 LOLOCA w Reference 1. L E. Hodvenor, et al , WCOBRNTRAC Appbcabky to AP600 Large&eak Loosd Coolard Amdent, WCAP-14171P, Rev.1 Odober 1996. '
.I.82 4690 MTGO . _ .NOJ{The RAl: WCAP-14171, 9% areWCOBRNTRAC REV.1 based onAPPUCABILITY t _ _ _ _,TO, _AP600
~, _, _Achon
_ _ _WCT WCTMemper 4690 LBLOCA W i Reierena 1. L E. Hodreser, et at, WCOBRNTRAC Apphcabky to AP600 Large&eak Lossd Cociard Acadert, WCAP-14171P, Rev.1, Odober 1996 3 . . -
NOT1The gjestons are based on t
_ _AP600
___ ___. _ ,WCT 4691 MTGO- . . RAI WCAP 14171 REV.1 WCOBRNTRAC APPUCABluTY TO Adon WCT*emper __ _ _ _ _ _ _ __.254Aay _25-May 4691 LBLOCA W Reference 1. L E. Hodveser,et al,WCOBRA/ TRAC AppbcabMy to AP600 Large&eak Lossd CooWt Amdent, WCAP-14171-P Rev.1 October 1996 ,
184 NOTE: The questons are based on t 4692 MTGO RAI WCAP-14171, REV.1 WCOBRNTRAC APPLICABluTY TO AP600 Adon WCT WCTEemper 4692 LBLOCA W Reierence 1. L E. Hodveder, et at, WCOBANTRAC ApptcabMy 10 AP600 Large Break Lossd Coolant Acadert WCAP-14171P, Rev.1, Odober 1996.
3 . . . . _ .. . _ . . _
. NOTE i Thegsostonsarebasedg _ __ _ _ __ _ _ _ _ , _ , , . , _ _ _
4633 MTGO RAL WCAP-14171, REV.1 WCOBfwTRAC APPUCABluTY TO AP600 Acton WCT WCTMerrper 4633 LBLOCA W Referenz 1. L E. Hodveder, et at, WCOBRNTRAC AppbcabWy to i AP600 Largeareak Lossd Coolart Acadent, WCAP-14171P, Rev.1 Odober 1996.
186 , _ . ,
NOTE: The quashans are basad an t ... _ _ _. _ _ . _ _ ___._ _ _
4694 __MTGO RAL WCAP-14171. REV.1 WCOBRNTRAC APPUCABluTY TO AP600 Adeon WCT WCTAemper 4694 LBLOCA W Reference 1. L E. Hodveder, el at, WCOBRNTRAC AppbcabNy to AP600 Largeereak Lossd Coolars Acadert, WCAP-14171P, Rev 1 Odober 1996 187 NOTE: The questons are based oni OIIS wk312 57 PM Page 26
1 .-
A A B C D F G H E I J i. K L OITS e Type Desc$elen W St Code Eng Sdeelt Subedt DreR to to NRC(nr OITS 8 Action R Code Draft (Dete) Fhist(Dete) NRC(Oste) 8) (VAI)h I._
4695
___ _ _ .u _ .__ . OITS
. _ .MTGO. _ .. . _ . -RAI WCAP 14171.REV.1 WCOBRAITRAC APPUCABILITY TO . . .AP600.
. Achon _ _WCT_ . _ _ _ WCT*emper
..._.___ 4695 LBLOCA W Reterance 1. L E Hadesser,et al.,WCOBRA/ TRAC Apt *M to AP600 Large4 reek Laosd Cootent Accdsrd, WCAP-14171P, Rev.1, October 1996.
3 l 4696. _ . _ _ . .MTGO- _ _. NOTE: The quessons are bened oni ____ ___ ._ __ _. _ _ _ _
RAI WCAP-14171.REV.1 WCOBRA/ TRAC APPUCABluTY TO AP600 Achon WCT WCT*erger 4696 LBLOCA W Roterence 1. L E. Hooveser, et at,WCOBRNTRAC Apphed*y to AP600 Large4 reek Loesd Coolers Accadert, WCAP-14171P, Rev.1 October 1996.
3 ,Reierera 9 S M Beforek,Wes _. __ ._ _ _ _._. ._ . _ _ .
4697 _ . ..MTGot. . . _RAL _ WCAP-14171, REV.1 WCOBRNTRAC APPUCABluTY TO AP600 Achon WCT WCT*erger 25 Wy 25-May 4697 ,
LBLOCA W Reterena 1. L E. Hodveser, et at, WCOBRNTRAC Apperd*y to AP600 Large-Break Lossd Coctors Accsdent, WCAP-14171f, Rev.1 Odober 1996
- 190 , _ _ _ ..__Reierence 11. B A Mcirtyve,We _ .
_ ___ _ _ . _ _ s 4698 MTGO rat WCAP 14171, REV.1 WCOBRAITRAC APPUCABlUTY TO AP600 A mon WCT WCT*erger 25May 25-May 4698 i LBLOCA W Roterenz 1. L E.Hodvener, etat WCOBRAfTRAC Apphr**yto AP600 Large-Break Lossd Cocient Accadert, WCAP 14171f, Rev.1 October 1996.
191 When reneweig Wesenghouse's , _ _.._ _ ,
4699 MTGO RAL WCAP-14171 REV.1 WCOBRA/ TRAC APPUCABluTY TO AP600 Amon WCT WCT*emper _25 May 25-May 4699 LBLOCA W Retsrera 1. L E. Hooveser, et at, WCOBRNTRAC Apptcabety to AP600 Large-Break Lossd Coolant Amterd, WCAP-14171-P, Rev.1 October 1996.
M ,_.
Whde rousueig ^ ___ ims RAL WCAP-14171, REV.1 WCOBRNTRAC APPUCABIUTY TO AP600 Adon WCT WCT*emper 2544ay 4700 4700 MTGO 25-44ay ;
LBLOCA W Reestance 1. L E. Hodweber, et at, WCOBRNTRAC Apphcatuity to AP600 Large4 reek Lossd Cooient Antent, WCAP-14171-P, Rev.1 Odaber 1996.
193 Whde reviewing Weswighouse's i
i OtIS wk312 57 PM Page 27 i
. r A
A B C D E F G H I J -l K t i
OITS 8 Type Desc W W St Code Eng Submit Sedunit Draft to le NRC(Isr OITS s Achen E Code Draft (Dete) Finst(Dete) NRC(Dele) s) (MI) bi
'AWCT
~ ~ ~ ~ ~
4701 'MTG O' 'RAI WCAP 14U1IREVliifCOBRATRAC APPUUA81UTY TO AP600~ WCT5AgIsr~ ~ ~25May 2544ay ~^~ 4 f01 LBLOCA W Referenca 1. L E.Homener, et at, WCOBRATTRAC AppbcatWy to AP600 Lage-8reak Laced Coolant Acadent WCAP-14171#, Rev.1 Odotw 1996.
3 . - .
_M_ ule rewoongWesemgetme's _
5017 __MTGO .RAL WCAP 14171P, REV.1 WCOBRNTRAC APPUCABluTY TO AP600_ _ _ _ _Adon . _ _ _ _ _ _ _ .__WCT_ _ _ _ , _ ._WCTEemper _ _ _ .5017 LBLOCA W Reierences
- 1. B. Boyack, el at,OuenMyng Am=** Salary Margra, Appecaton of Code Scahng Apg**my, and Lkicadamty Erdmam Methodology to a E _.
.LargeBreaMossdCoo Aden_.WCT WCTMernper_ _ _ _ _ _ _ _
,_.___i___.5018 5018 MTGO. _ . _RAI . WCAP-14171#, REV.1 WCOBANTRAC APPUCABluTY TO AP600 ,
LBLOCA W
References:
- 1. B Boyack, et al,Quanwying Reador Salety Margns Apphcaton of Code Scahng Appbcatmy, and Uncertarty Evnesm Melhadology to a 1% Large-Break, LossdCoo ____ _ __ _ _ _ _ . _ _ _ _ _ , _ . , , _ . _ _ __ ._ _, _ _ _ , ,
5019 MTGO RAI WCAP-14171-P REV.1 WCOBRNTRAC APPUCABluTY TO AP600 Achon WCT WCTMemper 25 May 25-May _ _ _ _ _ ._5019 LBLOCA W References
- 1. B. Boyack, el at,QuanWymg Reador Safety Margns. Apptcalon of Code Scahng Apphcately, and Uncertarty Evaluoman Melhodology 10 a 197 Largeereak,LossdCoo _._ _ _
RAI WCAP-14171#, REV.1 WCOBRA/ TRAC APPUCABluTY TO AP600 Achon WCT WCTEemper 5020 5020 MTGO I LBLOCA W Reierences
- 1. B. Boyack, et al, QuanWymg Ra=*w Safety Margns, Appbcalen of Code Scahng Appbcately, and Uncedasty Evaluehon Melhadology to a IM _ . _ _ _ ..Large Break, LossdCoo _ , , , . _ _ . _
Acton WCT WCTAemper 25-May 25-May 5021 ;
5021 MTGO RAl: WCA9-14171P, REV.1 WCOBRA/ TRAC APPUCABluTY TO APS00 LBLOCA W References
- 1. B. Boyack, et al., QuanWyng Reador Caiety Margns, Appbcahon of Code Scahng Appbcatmy, and Uncertasily Evaluaton Melhodology to a 199 t.argeBreak. LossdCoo OIIS wk312 5/ PM Page 28 ,
. . - .-= - ... . . . - . - - -. _ . ..
s ,
. A A B C D E F G H I l J K L OITS # Type Descripeon W St Code Eng Subadt Subek Draft to lo NRC(hr OfTS 8 Achen W.
Code DraR(Dese) Finsi(Dese) ORC (Dele) 8) (YAI)in 1 OITS 5022 MTGO RAL WCAP-14171-P, REV.1 WCOBRA/ TRAC APPUCABluTY TO AP600 Adm WCT WCTMemper 2544ay 25-May 5022 LBLOCA W Reierences. i
- 1. B. Boyedt,et at,QuerelyinD eadorR Salsty Margns, Apphcahon of Code Scahng Agg@ahany, and Uncertasty Evaluahon Methodology to a E . _ _ _ _ _ .. _ _ . _
.Weait,LosedCoo _ _ _ _ _ _ _ _ _ _ _ __ _ _ , , . _ _ , _ _ _ _ . _ _ _ i 5023 MTGOI RAL WCAP-14171#, REV.1 WCOBRNTRAC APPUCABillTY TO AP600 Acta WCT WCTMemper 5023 LBLOCA W Roterences.
- 1. B. Boyadt, et at, Quartfying Reador Salsey Margns, Apteraem of Code Scahng Apgkahdey, and Urunstarey Evolunhan Methodology to a E _ . _ .MTGO.__.
jargeBreak Loosdh Amon WCT WCTMemper 5024 5024 RAL WCAP 14171 P REV.1 WCOBRNTRAC APPUCABiUTY TO AP600 LBLOCA W Reierences:
- 1. B Boyack, et al,Quarsdyng Reador Salsty Margns. Apptcalm of Code Scahng Apptcabety, and Uncartardy Evalualm Methodology to a 202 _ _ _ _ _
,Large45reak,Losseh 5025 MTGO RAL WCAP-14171-P REV.1 WCOBRA/ TRAC APPUCABluTY TO AP600 Achon WCT WCTMemper 5025 LDLOCA W ;
Roterancas
- 1. B. Boyadt, et al, QuanMyng Reactor Salsty Margns Appbcaban of Code Scahng ApptcatWey, and Uncmetardy Evenem Methodology to a E ._. _ _ .
Large-Break Lossh _ _ . _ _ _ _ _ _ _ _ _
RAL WCAP-14171-P, RIV.1 WCOBRNTRAC APPUCABluTY TO AP600 Achon WCT ECTMemper 5026 5026 MTGO LBLOCA W Reierencas:
- 1. B. BA et at, Quartfyng Reacect Safety Margns, Appbcahon of P Code Scahng Apgkahday, and Uncgggggsy Evem Methodology to a 204 Large4leeak,LossdCoo ~~
RAIO REQUEST FOR ADDITIONAL INFORMATK)N ON THE WCOBRNTRAC Achon WTC WTCMenper ~ 5'I'3' 5 5113 OREGON STATE UNIVERSITY (OSU) LONG TERM COOUNG (LTC) FINAL W VAUDATION REPORT,WCAP-14776 440.589 The trends n the WCOBRA, TRAC analyses of the OSU S810 test E show an gWm of alredsong_ __ __ _ _ __ . __ . ___, _ , _ _ _ _ _ . , __ . _ _ _ _ _ , - , . __ _,_
Achon WTC WTCMemper 5t14 5114 RAla. _ _ _REQUEST FOR ADDITIONAL INFORMATION ON THE WCOBANTRAC OREGON STATE LWIVERSITY (OSU) LONG TERM COOUNG (LTC) FINAL W VAUDATtON REPORT, WCAP-14776 440.590 Page 5-34,5th paragraph states that the discrepancy shown n the 206 ieper pienum r*w pressure (F Oils wk31237 PM Page 29
= _ - _ _ _ _ _ _ _ _ _ _ . -- _ _ _ _ _ _ _ - _ _ - _ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ - _ _ _ _ _ _-.
w -.
A l A B C D E F _G l' H I J K l L ORTS s Tye esecrtyeen W St Code . Eng SeemR Subek Drak to to MRC(br OITS f Acton]L Code DreR(Oste) Final (Dees) NRC(Dele) f) (YK,in 3 _OtT,_S ,
5115 RAIO REQUEST FOR ADDITIONAL INFOMATION ON THE WCOBANTRAC Acton WTC WTC*emper . . _ _ _ . .5115 OREGON STATE terVERSITY (OSU) LONG TEM COOUNG (LTC) FINAL W VALIDATION REPORT.WCAP-14776 440 591 The cahW mandow kr S8-10 swip ryecmon now (Fgures52-207 .. .
5 and 524] scope as 142 som __. _ _ _ _ _ _ _ _ _ , _ . _.. _ ,_ _ ._ , _ . _ . , . _.
5116 RAIO REOGST FOR ADDITIONAL INFORMATG ON THE WCOBRATTRAC . Action
. _ _ _ _ .WTC WTC*emper_ _ _ _ _ _ 5116 OREGON STATE UNNERSITY (OSU) LONG TEM COCUNG 'LTC) FINAL W VAUDATION REPORT.WCAP-14776 440 502 Wesinghouse asessemerW of the OSU SB-12 test states on page 5-20e 66 that *. the sep knr mes WWWeed __ _ . _ _ _ _ , _ - _ _ _ _ . , _ _ _ _ _ _ . . _ , _ _
5117 RAIO REQUEST FOR ADDITIONAL INFORMATK)N ON THE WCOBRNTRAC _,_Adon WTC WTC*emper 5117 OREGON STATE UNNERSITY (OSU) LONG TEM COOLFa (LTC) FINAL W VAUDATION REPORT.WCAP-14776 440.593 in Figure 64, sie measured and cahdan=d tales of the inRow and 209 odtow are a funden of tms.
Oils wk312.57 PM Page 30
7__._._.._._.__.__._._______.__
s T \' yOe O' (t[ \). MV\ :
(
[ 3!/
Ecorn - Obn 9 es
( . 0($ Y D'kk fQl f3 Mye_(vce'rtS$ti F n m N As,3,s.i).
fi E 9f l
4
.c.
RTS Instrumentation 3.3.1 i
3.3 INSTRUMENTATION
- 3.3.1 Reactor Trip System (RTS) Instrumentation
, l 4
.LC0 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 l shall be OPERABLE. '
j APPLICABILITY: According to Table 3.3.1-1.
4 i .i ACTIONS l i --------------------------------------NOTE------------.--*--------.--....--.... l i Separate Condition entry is allowed for each inoperable Function. l
! CONDITION REQUIRED ACTION COMPLETION TIME -
A. One or more Functions A.1 Enter the Condition Immediately i with one or more referenced in
- required channels Table 3.3.1-1 for the i inoperable. channel (s).
1 s
1
- ed 375
- B. One manual initiation B.1 Restore manual initiation 7/ hours 5.
I device inoperable. device to OPERABLE status.
0.8 Verify manual initia on devices, equivale to -72 he.c; he control r devices, i he Remote utdown Work tion re OPERABLE and a 'cated operator who is n tinuous c ication ith the co rol room is ationed the devices.
OR Q
Sy l B .J .1 Be in MODE 3. pdhours' AND (continued) h AP600 3.3-1 08/96 Amendment 0 l mn. m.omat,o im
RTS Instrumentation l 3.3.1 !
ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME z ss sn B. (continued) B./.2 Open reactor trip 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> 5 j breakers (RTBs).
.es s 75 \
C. One manual initiation C.1 Restore manual M hours C-
! device inoperable, initiation device to
{
i 0PERABLE status. '
0_B M
C.2 Open RTBs. Jf hours s z. S75
, D. One required Power D.l.1 Reduce THERMAL POWER to # hours #
l ,
Range Neutron s 75% RTP.
i Flux-High channel inoperable. AND
- 4 D.l.2 Place inoperable <*. J 2' hours channel (s) in bypass.
'( -Am 0.1.3 Liters 3 ef ? channel 3 100 heers t: OPEIa L ;t;t;;.
OR c, 1 D.2.1 Place inoperable ghours channel (s) in bypass.
AND 9
............-N0TE-------------
Only required to be performed when OPDMS is inoperable and the Power Range Neutron Flux input to QPTR is inoperable.
D.2.2 Perform SR 3.2.4.2 Once per (QPTR verification). 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND (continued) t Y-I h AP600 3.3-2 08/96 Amendment 0 AP01stestmees\10030301.r06&1 tse
l' RTS Instrumentation 3.3.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME s rs D. (continued) 0.2.3 Restore 3 of 4 di mich 100 heu,3 #
iv GFEiv E E status.
~
I t.
D.3 Be in MODE 3. Ptfhours 4 575 E. One required channel E.1.1 Place inoperable / hours E inoperable. channel (s) in bypass.
ANB 4.1.2 Roster; 3 ef 4 J .m cl2 100 h;;r; t: OPER"0LE :t;t;;r.
0.8 12.
E.2 Be in MODE 3. Ptfhours-I L so 1 F. THERMAL POWER between F.1.1 Place inoperable ghours #
P-6 and P-10, one channel (s) in bypass.
required Intermediate
- l Range Neutron Flux -AND-, l channel inoperable. l T.1.2 R;; tere ; ef 4 diennels 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />s--
t: OPEPM LE statur. I OR 2.
F.2 Reduce THERMAL POWER to ghours i
< P-6.
OR i 2 l F.3 Increase THERMAL POWER ghours to > P-10.
l (continued)
(%
h AP600 3.3-3 08/96 Amendment 0 e n. u.u noi m e.o m
! RTS Instrumentation 3.3.1 l'
l ACTIONS (continued) l CONDITION REQUIRED ACTION COMPLETION TIME 575 G. THERMAL POWER between G.1 Suspend operations Immediately G P-6 and P-10, two involving positive l required Intermediate reactivity additions.
Range Neutron Flux channels inoperable. AND 1
G.2 Reduce THERMAL POWER to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
< P-6.
1 573 H. THERMAL POWER < P-6, H.1 Restore 3 of 4 channels Prior to N one required to OPERABLE status. increasing Intermediate Range THERMAL POWER Neutron Flux to > P-6 channel inoperable.
I. On ired Source I.1 Place inoperable Range Neu Flux channel (s) in bypass.
I channel inoper W #
CON #1W8d I I.2 to ore 3 of 4 channels 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> RABLE status.
0_B I.3 Increase THERMAL P0 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to > P-6.
J._ than one J.1 Suspend operations Imm ly ource Range involving positive fff/AC6 g Tequi deutron Flu nnel reactivity add .
peu) inoperable.
R
.2 Ope s. Immediately Required Action associated p etion AND Time ondition I l met.
l tinued)
\ ,
l .
h AP600 3.3-4 08/96 Amendment 0
i, INSERT LC0 3.3.1 i
STS '
i I. One required Source I.1 Suspend operations Immediately I Range Neutron Flux involving positive channel inoperable. reactivity additions.
B
$75 l
J. Two required Source J.1 Open RTBs. Immediately J Range Neutron Flux channels inoperable.
l l
(
l l
I l
e I
l l
E
RTS Instrumentation
- 3.3.1 i
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME
, J. ntinued) J.3 Close unborated water ur i source isolation valves.
J.4 m SR 3.1.1.1 (SDM 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> verific n).
AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> eafter sr5 K. One required channel K.1.1 Place inoperable 8' hours M inoperable. channel (s) in bypass.
-ANO,
[ i( .1. 2 P_e:te e ? Of 0 unanneis t: OPEPACLE at ts.
los nours OR l 2.
K.2 Reduce THERMAL POWER to I?tihours
< P-10.
S75 4 #
L. One required channel L.1.1 Place inoperable Jif hours inoperable. channel (s) in bypass.
AND-
-L.1.2 Restera 3 of i donnels 166 huws -
--te OPERABLE st&ta:.
/0 L.2 Reduce THERMAL POWER to }?tihours
< P-8.
(continued) h AP600 3.3-5 08/96 Amendment 0 miu si.uwei.,o.o.on.
. ~ - . . = . = . . . . . - ~ . . - . . .- . . . .-.
RTS Instrumentation 3.3.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME 575 M. One required M.I. Plec inug ..v'i. S 5: r: 95 channel / division eheaael(s)/d!"i ica(s) inoperable. in bypese.
MM>~ l C
M.I.2 Restore 3 of 4 +60 hours channels / divisions to OPERABLE status.
98
/2. '
M.2 Be in MODE 3. 4f6-hours 575 N. One required channel N.1 Verify the interlocks 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 5 sii I inoperable, are in required state for existing plant conditions.
OR 7 .
N.2.1 Place the functions Jf hours '
associated with inoperable interlocks in bypass.
--ANB.
N.C.2 "; ster 3 cf 4 -
, 4 0 h;;r:-
46teried s to OPC"a"LE
- t:tus.
~
/3 N.3 Be in MODE 3. 49Tr hours (continued)
(!)AP600 3.3-6 08/96 Amendment 0 mi-isomoim m
l RTS instrumentation l 3.3.1 l
i
, ACTIONS (continued) t l CONDITION REQUIRED ACTION COMPLETION TIME
$75
- 0. One required channel 0.1 Verify the interlocks I hour T*E I l inoperable. are in required state for existing plant j conditions.
l l
OR l
~
7 0.2.1 Place the functions g hours i associated with i inoperable interlocks in bypass. l
-ANB-1 ne o om,+m.. o ca ice u-...,
interlocks to OP:PXLC tto.
~
13 0.3 Be in MODE 2. Hfr hours i
ANou P. One required division P.1.1 Open inoperable RTB in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> W inoperable. one division. NN
-AN&~ m Y.7 . 0 P.I.2 Restore 3 4 4 - MS haurs- e' divisions to OPEPf E E-status.
0,8 l 'f P.2.1 Be in MODE 3, 4, or 5. .lN hours AND P.2.2 Open RTBs. hours Q . 7" 0 KE @'<C 0 q,2 gssnei= RaQe460 ; y (continued)
M moas waps(Aaes. p g ,yy w OPEgA&E STA7ws . S5 (2
R&
L. e.2..I se w mese s, +, or S. 7MS AWD 4,2. 2. 0/Ex/ RT8s . 7 #0u4 OW AP600 3.3-7 08/96 Amendment 0 AP01 generweesti 003030 t .#06400294
l RTS Instrumentation 3.3.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME ,
i Q. trip mechanism Q.l.1 Open inoperable RTB in 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> )
inop le on one one division.
required AND
.2 Restore A3 4 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> divi ds to OPERABLE s.
. 176 hours0.00204 days <br />0.0489 hours <br />2.910053e-4 weeks <br />6.6968e-5 months <br /> Q.2.1 Be in MODE 3, 4, .
AND 17 urs !
Q.2.2 Open RTBs.
l 5 73 R. One required channel / J! .1.1- Piece inoper:b'c- O hegrs-. c;. i division inoperable. channel /divis;un hi I
(, byp:::.
Aun
~
48 R.l.2 Restore 3 of 4 LM(hours channels / divisions to j OPERABLE status, l
l l
OR M
R.2 Open RTBs. )?$ hours l 1
i M
I LIS ER.T NEd co*>o mo#s s A 7 (h)AP600 3.3-8 08/96 Amendment 0 AP014es%>estl e030301.r06000298
. - . . . . - .. - ~ - . . . . - . _ .. - ..
b i
INSERT LC0 3.3.1 i l
! S. One required Source S.1 Restore required 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> K i Range Neutron Flux channel to OPERABLE channel inoperable. status.
i OR l
S.2 Open RTBs. 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br /> i STS T. Required Source T.1 Suspend operations Immediately L Range Neutron Flux involving positive channel [(s)] reactivity additions.
AND f T.2 Close unborated water 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
\ source isolation
- valves.
3 AND T.3 Perform SR 3.1.1.1. I hour 3 AND Once per 12 haurs thereafter d
RTS Instrumentation 3.3.1
, 4 SURVEILLANCE REQUIREMENTS
NOTE-------------------------------------
Refer to Table 3.3.1-1 to determine which SRs apply for each RTS Function.
I SURVEILLANCE FREQUENCY
. I ~L. 573 SR 3.3.1.1 Perform CHANNEL CHECK. 24' hours SVt15. l l
! SR 3.3.1.2 -------------------NOTES-------------.-
- 1. Adjust nuclear instrument channel in the Protection and Safety Monitoring System (PMS) if absolute difference is > 2% RTP.
12.
- 2. Required to be met within hours after reaching 15% RTP.
- 3. If the calorimetric heat balance is
^
< 70% RTP, and if the nuclear instrumentation channel indicated
( power is:
- a. lower than the calorimetric measurement by > 2%, then adjust the nuclear instrumentation channel upward to match the calorimetric measurement.
l
- b. higher than the calorimetric measurement, then no adjustment is required.
Compare results of calorimetric heat 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l balance to nuclear instrument channel in PMS output.
(continued) 1 1
(s.
(!)AP600 3.3-9 08/96 Amendment 0 AP01\isormeest100M301.ro6400294
l RTS Instrumentation 3.3.1 a
SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY f SR 3.3.1.3 -------------------NOTES---------------
- 1. Adjust nuclear instrument channel in PMS if absolute difference is 2: 3%
l AFD.
jg.
- 2. Required to befdet within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after reaching 50% RTP.
Compare results of the incore detector 31 effective measurements to PMS AXIAL FLUX full power days DIFFERENCE. (EFPD) l SR 3.3.1.4 -------------------NOTE-----------------
Required to be met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after reaching 50% RTP.
Calibrate excore channels to incore 92 EFPD l
[ detector measurements.
SR 3.3.1.5 Perform RTCOT. 24 months SR 3.3.1.6 Perform TAD 0T. 92 days SR 3.3.1.7 -------------------NOTE'---------------
This test shall include verification that the time constants are adjusted to the prescribed values.
Perform CHANNEL CALIBRATION. 24 months (continued)
(!)AP600 3.3-10 08/96 Amendment 0 AP01uesteses\10030301.r00400294
RTS Instrumentation
, 3.3.1
. I j SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY.
1
' SR 3.3.1.8 ------------
'-----NOTE-----------------
The neutron detectors may be excluded
. from the CHANNEL CALIBRATION.
Perform CHANNEL CALIBRATION. 24 months
.)4 I
i l . SR 3.3.1.9 Perform CHANNEL CALIBRATION. 24 months i e i
SR 3.3.1.10 Perform TAD 0T. 24 months
.i l SR. 3.3.1.11 -------------------NOTE-----------------
l Neutron detectors are exempt from response time testing.
Verify RTS RESPONSE TIME is within 24 months on a limits. STAGGERED TEST I BASIS .
a 1
l 1
1 1.
i 1
4 1
1 i
i
!k.
i h AP600 3.3-11 08/96 Amendment 0 mw u.omoim4.om
RTS Instrumentation 3.3.1 Table 3.3.1 1 (page 1 of 5)
Reactor Trip System Instrunentation ,
. REQUIRED APPLICABLE CHANNELS / SURVEILLANCE NOMINAL TRIP FUNCTION MODES DIVis!ONS CONDITIONS REQUIREMENTS SETPolNT l
- 1. Manual Reactor Trip 1,2 2 8 SR 3.3.1.10 N/A 3(a) 4(a) 5(a)
, , 2 C SR 3.3.1.10 N/A
- 2. Power Range Neutron Flux l
- a. High Setpoint 1,2 3 0 SR 3.3.1.1 [s 118% RTP) l 4 SR 3.3.1.2 SR 3.3.1.5
- b. Low setpoint 1(b) 2, 3 E SR 3.3.1.1 [s 35% RTP)
. 3. Power Range Neutron Flux 1,2 3 E SR 3.3.1.1 (s 5.0% RTP High Positive Rate SR 3.3.1.5 with time constant d
a 2 sec*)
- 4. Intermediate Range Neutron 1(D) 2(c)
, 3 F,G SR 3.3.1.1 [s 25% RTP*)
y Flux SR 3.3.1.5 2(d) 3 H SR 3.3.1.1 [s 25% RTP*)
- 5. Source Range Neutron Flux 2(d) 3 1,J SR 3.3.1.1 (s 1.0E5 cps *]
+
High Setpoint 3('), (a) $(a) -.y
,3 , 3 SR 3.3.1.5 3(e) 4(*),5(*)
, 1 /7" SR 3.3.1.1 N/A i
(
(continued)
(a) With Reactor Trip Breakers (RTBs) closed and Plant Control System capable of rod withdrawal.
(b) Below the P 10 (Power Range Neutron Flux) interlocks.
(c) Above the P 6 (Intermediate Range Neutron Flux) interlocks.
(d) Below the P 6 (Inter 1nediate Range Neutron Flux) interlocks.
(e) With RTBs open. In this condition, Source Range Fation does not provide reactor trip but does provide indication.
[ Reviewer Note: The values specified in brackets in the Nominal Trip Setpoint colunr1 are the SSAR Chapter 15 safety analysis values and are included for reviewer information only.
The values specified in brackets followed by " * " in the Nominal Trip Setpoint colum are typical values f or the Fmction. No credit was assumed for these Fmetions (typically diverse trips /actuations) in the
- $$AR Chapter 15 safety analyses and no safety analysis value is available.
In all cases, the values specified in brackets aust be replaced, following the plant-specific setpoint study, with the actual Nominal Trip Setpoints. Upon selection of the plant specific instrumentation, the Nominal Trip Setpoints will be calculated in accordance with the setpoint methodology described in i WCAP 14606. The plant specific setpoint calculations wlLL reflect the latest licensing analysis / design basis and may incorporate NRC accepted improvements in setpoint methodology.]
b h AP600 3.3-12 08/96 Amendment 0 m neomonoeoeos.e
i j
RTS Instrumentation 3.3.1 j Table 3.3.1 1 (page 2 of 5) ,
Reactor Trip system Instrumentation i
.. I REQUIRED i I
APPLICABLE CHANNELS / $URVEILLANCE NOMINAL TRIP FUNCTION MODES DIVis!ONS CONDITIONS REQUIREMENTS SETPOINT
- 6. overtenperature AT 1,2 3 E sR 3.3.1.1 (Refer to l sR 3.3.1.3 Note 1
$R 3.3.1.4 (Page 3.3 16))
st 3.3.1.5 SR 3.3.1.9
- 7. overpower AT 1,2 3 E sR 3.3.1.1 (Refer to SR 3.3.1.3 Note 2 st 3.3.1.4 (Page 3.3 16)]
st 3.3.1.5 st 3.3.1.9
- 8. Pressurizer Pressure
- a. Low setpoint 1(f) 3 K SR 3.3.1.1 Im 1785 psig) st 3.3.1.5 st 3.3.1.7
- b. High setpoint 1,2 3 E st 3.3.1.1 ts 2445 psig) st 3.3.1.5 st 3.3.1.7
- 9. Pressurizer Water Level - 1(I) 3 K st 3.3.1.1 [s 92%*)
Nigh 3 SR 3.3.1.5 SR 3.3.1.7
- 10. Reactor Coolant Flow - Low
- a. single Cold Leg 1(8) 3/ cold leg L $R 3.3.1.1 ta 87%(I)]
SR 3.3.1.5 st 3.3.1.7
- b. Two Cold Legs 1(h) 3/ cold leg K st 3.3.1.1 (= 87%(I))
$R 3.3.1.5 SR 3.3.1.7 (continued)
(f) Above the P 10 (Power Range Neutron Flux) interlock.
(g) Above the P 8 (Power Range Neutron Flux) Interldek.
(h) Above the P 10 (Power Range Neutron Flux) interlock and below the P 8 (Power Range Neutron Flux) Intertock.
(i) Percent of thernet design flow.
N-h AP600 3.3-13 08/96 Amendment 0 APot uestueesit eo3o3o1.soecao2ee
-. . __- . - . -._ . .-- . . . ~ - -. .
RTS Instrumentation !
3.3.1 l 8 l l
l l
2 Table 3.3.1 1 (page 3 of 5) l Reactor Trip System Instrunentation l
z l REQUIRED .
APPLICABLE CHANNELS / SURVEILLANCE NOMINAL TRIP l FUNCTION MODES Divisl0NS CON 0lfl0NS REQUIREMENTS SETPolNT
- 11. Reactor Coolant Puip l (RCP) Bearing Water Terrperature - High
- a. Single Purp 1(9) 3/RCP L SR 3.3.1.1 [t 320*F*]
SR 3.3.1.5 SR 3.3.1.7
- b. Two Ptaps 1(h) 3/RCP K SR 3.3.1.1 (1 320*F')
SR 3.3.1.5 SR, 3.3.1.7
- 12. RCP Speed - Low IIII 3 K SR 3.3.1.1 (1 90%1 SR 3.3.1.5 SR 3.3.1.7
- 13. Steam Generator (SG) 1,2 3/SG E SR 3.3.1.1 [a 45000 th,3 Narrow Range Water SR 3.3.1.5 Level - Lou SR 3.3.1.7 K
- 14. Steam Generator (SG) 1,2Y) 3/SG E SR 3.3.1.1 ( s95%)
Narrow Range Water $R 3.3.1.5 Level High 2 SR 3.3.1.7 f 15, Safeguards Actuation input from Engineered Safety Feature Actuation System
- a. Manual 0 SR 3.3.1.10 N/A b, Automatic
, M SR 3.3.1.10 N/A (continued)
(f) Above the P 10 (Power Range Neutron Flux) interlock.
(g) Above the P 8 (Power Range Neutron Flux) interlock.
(h) Above the P 10 (Power Range Neutron Flux) interlock and below the P 8 (Power Range Neutron Flux) interlock.
N
(/) Above the P 11 (Pressurizer Pressura) interlock.
b.
h AP600 3.3-14 08/96 Amendment 0 m iu. aeoaoaoooe o m
RTS Instrumentation 3.3.1 s
Table 3.3.1 1 (page 4 of 5)
Reactor Trip System Instrumentatim ;
1 l
REQUIRED i
APPLICABLE CHANNELS / SURVEILLANCE NOMINAL TRIP l FUNCTION MODES DIVis!ONS CON 0lil0NS REQUIREMENTS SETPOINT l
-16. Reactor Trip System
)
Interlocks
- a. Intermediate Range 2 3 N $R 3.3.1.5 (a 1E 10 anos]
Neutron Flux, P*6 q
- b. Power Range Neutron 1 3 0 $R 3.3,1.5 (s 48% RTP)
Flux, P 8 l l
- c. Powr Range Neutron 1,2 3 N SR 3.3.1.5 (10% RTP) l Flux, P 10
- d. Pressurizer Pressure, 1,2 3 N st 3.3.1.5 (s 1970 psig)
P 11
- 17. Reactor Trip Breakers 1,2 3 divisions with 2 RTBs PA $R 3.3.1.6 N/A 3(ll,4(l) 5(l) per division
- 18. Reactor Trip Breaker (RTB) Undervoltage and 1,2 1 each per RTB
/f1h SR 3.3.1.6 N/A
$ hunt Trip Mechanisms 3(l) 4(I) 5(l)
, , mechanism for required RTBs
- 19. Automatic Trip Logic 1,2 3 M SR 3.3.1.5 N/A 3(j) 4(,5(l)
, 3 R st 3.3.1.5 N/A f ADS MN 0>2
- 20. t !" = "_.'.'.*.,_ S )
1,2 3 M SR 3.3.1.10 N/A Kfj" sf647/0V 3(j) 4(j) 5(l)
, , 3 a sa 3.3.1.10 N/A
- 21. Core Makeup Tank 1,2 3 M SR 3.3.1.10 N/A Actuation 3(I) d l) 5(I)
, , 3 R $R 3.3.1.10 N/A (j) With Reactor Trip Breakers closed and Plant Control System capable of rod withdrawal.
I h AP600 3.3-15 08/96 Amendment 0 uen. aaomai.,o on.
. . _ ._ _ _ . ~ _ . _ _ _ _ _ _
RTS Instrumentation 3.3.1 s Table 3.3.1 1 (page 5 of 5) Reactor Trip System Instrunentation Note 1: Overter.cerature AT gy (1 +r s) , y; K,,K,d (1 y,s)
+ r,s)(T -T'l+K,(P -P') -f,( A I )
(1 + r,s ) $ Where AT is measured RCS AT, 'F. 1 AT, is the indicated AT st RATED THERMAL POWER, 'F. s is the Laplace transform operator, sec'. T is the measured RCS average teoperature, *F. T' is the indicated T, at 100% RTP, 'F. P is the measured pressurizer pressure, psig.
, P' is the nominal RCS operating pressure, 2235 psig.
K, s 2.1 K, = 0.03/*F K. = 0.002/psig r, a 33 sec r, s 4 sec r, = 0 see r, = 0 see f,( A!) = 0.0% / % when g g < 11 RTP 4.915% / %((g - g) + 1) when g - g a 1% RTP Where g and g are percent RTP in the upper and Lower halves of the core respectively, and g + g is the tqtal THERMAL POWER in percent RTP. Wote 2: Overoower AT AT sATi K,-K,d'* T -K,[T -T")-f,( A! )
- ( 1 + r,s) 1 + r,s Where AT is measured RCS AT, 'F.
AT, is the indicated AT at RATED THERMAL POWER, 'F. s is the Laplace transform operator, sec4 . T is the measured RCS average toeperature, 'F. . T is the indicated 7, at 100% RTP, *F. K, s 1.145 K, a 0.02/'F for increasing T. K. = 0.00219/'F when T > T
- 0/'F for decreasing T , 0/'F when T s T'8 r, a 10 see r, = 0 sec r, = 0 sec d
f,(AI) = 0% of RTP for all AI. h AF600 3.3-16 08/96 Amendment 0 APo1 westessett a0303o' .,o60eo294
i Suggs, Chip From: Nydes, Robm To: Suggs, Chip
Subject:
FW: Shutdown Report Steamline Btesk in Mode 3 Date: Tunday, February 11,1997 8:53AM Hi. Potential Tech Spec change O'll keep you posted). Mike and I welcome any thoughts you have on this. Robin From: Corletti, Mike To: Vijuk, Ron Cc: Cummins, Ed: Nydn, Robin: Schdz, Terry: Bachrach, llriel X.: Carlin, Edward L.: Novendstern, Earl H.
Subject:
Shutdown Report Steandine Break in Mode 3 Date: Monday, February 10,1997 5:52PM During the invatigation of steandine breaks t' et could occur in Mode 3, the f allowing scenario has developed: in mode 3, per the tech specs, the primary signals that provide ernergency boration via the CMTs Oow steamline pressure, low RCS pressure, low T cold) can be blocked below P 11 Gow pressurizer prusure ~2000 psig), The problem is that currrently, our most lirniting SSAR SLB events are at 0 power (hot standbyl. Therefore it would appear that with these primary signals removed (which can occur at T noload and pressure slightly reduced), the results of a GLB analysis will be worse than the current SSAR analysis. For such an event, the CMT would not be actuated intil the low pzr level setpoint was reached (which would occur due to the shrink in the RCS due to the cooldown). Furthermore, the CVS makeup pumps could be postulated to operate and delay CMT actuation. There appears to be two issues:
- 1) The ruults of this analysis could be acceptable, however more limiting than the SSAR case. This could impact cost and schedule for the SSAR.
l 2) Whwas the most lirniting stb accidents for the AP600 are the zwo power cases, AND we have protection logic designed to accomodate these 0 l poww stb cases, the Tech Specs allow then to be blocked at the time when they are needed most. This does cet appear to be the right thing to do. 1 in past plants,it has been the W position that these lower mode SLBs were not limiting because of the additional shutdown margin at lower moda. Howevw, the TS do not require additional SOM to block thus isolation signals designed to mitigate SLB. An option that seems to make sense is to tie the ability to isolate these automatic signals to additional SDM (via baron). I spoke with Bob Berryhill of ARC regarding typical opwating practices at shutdown and he confirmed our undwstanding which was that plants do borate prior to cooldown, to me'u sure they maintain sufficient SDM. He didn't newn to feel that a requirement of additional SOM prior to blocking thus signals would be onwous. I think wa should try to go in the direction of/Iacing higher SOM requirmnents before blocking these SLB siunatDThis would address both above. Please advise. ! Mike 1 L Page1
PAM Instrumentation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Post Accident Monitoring (PAM) Instrumentation I 4 LC0 3.3.3 The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE. I APPLICABILITY: MODES 1, 2, and 3. ACTIONS i
---------------------------NOTES-----------------------------------------
- 1. LCO 3.0.4 not applicable.
1
- 2. Separate Condition entry is allowed for each Function.
f CONDITION REQUIRED ACTION COMPLETION TIME I l A. One or more Functions A.1 Restore required channel 30 days with one required to OPERABLE status.
- ( channel inoperable.
B. Required Action and B.1 Initiate action in Immediately associated Completion accordance with a Time of Condition A Specification 5.6.7. not met. C. --------NOTE------ C.1 Restore one enannel to 7 days Not applicable to OPERABLE status, hydrogen monitor channels. One or more Functions , with two required j channels inoperable. (continued) 1 (!)AP600 3.3-45 08/96 Amendment 0 AP01wastesest10030303 t04400704
PAM Instrumentation 3.3.3 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME D. Two hydrogen n:onitor D.1 Restore one hydrogen 72 hours channels inoperable. monitor channel to OPERABLE status. 1 E. Required Action and E.1 Enter the Condition Immediately associated Completion referenced in Time of Conditions C Table 3.3.3-1 for the. or D not met, channel. F. As required by F.1 Be in MODE 3. Ihours Required Action E.1 and referenced in AND Table 3.3.3-1. *
/ 2L-F.2 Be in MODE 4. 74' hours
(. SURVEILLANCE REQUIREMENTS
..................................---NOTE-------------------------------------- ,
SR 3.3.3.1 and SR 3.3.3.2 apply to each PAM instrumentation Function in Table 3.3.3-1. SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL CHECK for each 31 days required instrumentation channel that is normally energized. SR 3.3.3.2 ------.--------NOTE---------------- . Neutron detectors are excluded from CHANNEL CALIBRATION. Perform CHANNEL CALIBRATION. [ 4 months (!)AP600 u.uo m ,o. m m 3.3-46 08/96 Amendment 0 m n
PAM Instrumentation 3.3.3 I Table 3.3.3 1 (page 1 of 1) i Post Accident Monitoring Instrunentation i CONDITION REQUIRED REFERENCED FROM CHANNELS / REQUIRED FUNCTION DIVIsl0NS ACTION E.1
- 1. Neutron Flux (Power, Intermediate and Source Range) 2 F
- 2. Reactor Coolant System (RCS) Mot Leg Tenperature 2 F
, (Wide Range)
- 3. RCS Cold Leg Tenperature (Wide Range) 2 F l
- 4. RCS Pressure (Wide Range) 2 F
- 5. Pressurizer Pressure and 2 F I RCS Subcooling Monitor (s)
- 6. Contairvnent Water Level 2 F
- 7. Containment Pressure 2 F
- 8. Containment Pressure (Extended Range) 2 F
- 9. Contairment Area Radiation (High Range) 2 F
, 10. Hydrogen Monitors 2 F
- 11. Pressurizer Level and Associated Reference Leg 2 F Temperature e 12. IRWST Water Level 2 F k
j 13. PRNR Flow and PRMR Outlet Tenperature 2 flow & F 1 temperature
- 14. Core Exit Tenperature ouadrant 1 2(b) ,
- 15. Core Exit Temperature--Quadrant 2 2(b) ,
- 16. Core Exit Temperature -ouadrant 3 2(b) ,
- 17. Core Exit Tenperature -ouadrant 4 2(b) p
- 18. PCS Storage Tank Level and PCS Flow 2 level & 1 flow F
- 19. Remotely operated contairment Isolation Valve Position 1/ valve (c) ,
- . _ _ . - _ - . . . . . . . . ,. . _ = . - - - _ - . - . . - _ . - . _ -
,, 20. g,jgy 3 ggfg gescnoat v4tn g reyug & F (a) RCS Subcooling calculated from pressurizer pressure and RCS het leg temperature. (b) A channel conalsts of two thersocoteles within a single division. Each quadrant contains two divisiana. The minisun requirement is tw operable thermocouples in each of the two divisions. ' (c) Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind vetve, or check valve with flow through the valve secured. TUmt i h AP600 3.3-47 08/96 Amendment 0 mm aannu ososone
Remote Shutdown Workstation ) 3.3.4
'a 3.3 INSTRUMENTATION I 3.3.4 Remote Shutdown Workstation LC0 3.3.4 The Remote Shutdown Workstation (RSW) shall be OPERABLE. l l
l APPLICABILITY: MODES 1, 2, and 3. 1 ACTIONS
, .......................................N0TES------ ------...---.-.............
- 1. LC0 3.0.4 is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. RSW inoperable. A.1 Restore to OPERABLE 30 days status. ( s:
- B. Required Action and 8.1 Be in MODE 3. )(hours
, associated Completion Time not met. AND
/E-B.2 Be in MODE 4. JWIhours 3
l l l t 4 t. (!)AP600 3.3-48 08/96 Amendment 0 , uen. n.nm .+=in. i l l
6 Remote Shutdown Workstation 3.3.4 5 SURVEILLANCE REQUIREMENTS SURVEILLANCE ,4 FREQUENCY.
/
SR 3.3.4.1 Verify each required tra'nsfer switch is 24 months capable of performing 'the required function. , SR 3.3.4.2 Verify that the RSW communicates 24 months indication and controls with Division A, B, C and D of the PMS. SR 3.3.4.3 Verify the OPERABILITY of the RSW 24 months hardware and software. l l SR 3.3.4.4 Perform TAD 0T of the reactc urip 24 months breaker open/ closed indication. { le. (!)AP600 3.3-49 08/96 Amendment 0 m, . s, --- ,
h Westinghouse FAX COVER SHEET W I l i I RECIPIENT INFORMATION SENDER INFORMATION l OATE: kf 2-) _ ( #1II '[ NAME: he;vE h b ui $ TO: LOCATION: ENERGY CENTER - d f., M M Sit y EAST 3263 )
. PHONE: FACSIMILE: %-l-301-Llls-220L PHONE: Office:(Qrth 379 -6310 i COMPANY: Facsimile: win: 284 4887 i h outside: (412)374-4887 j LOCATION:
p A (TE FL gd7 i
~ '
Cover + Pages 1+ l The following pages are being sent from the Westinghouse Energy Center, East Tower, Monroeville, PA. If any problems occur during this transmission, please call: , WIN: 284 5125 (Janice) or Outside: (412)374 5125. COMMENTS: 7 JcE , i i I T C R 27_;Lo D o/L O G 4 6 ( 4 h t_. 5 0o/L afni2]nic fite.. % % " sn e K w. 4.rr fLso Tevr l lh IND D3 NAN' [1, E t' 15 4 t} (O h T 1 hl$ @ T .D d * (Mi LL $N MT 55 wL I sa,ua em w <.ny vw A r-oauw tme tv
'-TT V00 N d T Lv M L Mk
.-. l v e
\
Mmn , i l l L l-( l 14.2.10.4.2M Remote Shu'tdown Workstation . l Objective I l-Demonstrate the ability of the operators to conduct a remote shutdown of the plant during a simulated main control ro'om evacuation. l l - Prerequisites l l Approved operating procedures for performing a remote shutdown is available. l Communication exists between the control room and the remote shutdown location. Procedures for transferring control back to the main control room is available if an emergency or unsafe condition develops during the testing that cannot be managed by the shutdown crew. The plant is operating in a steady-state condition at 10-20% of power. Test Method Using the appropriate operating procedures, the operators transfer control of the plant from the main control room to the remote shutdown workstation. From the remote shutdown workstation, the operators bring the plant to hot standby, and maintain hot standby conditions for at least 30 minutes.
< From the remote shutdown workstation, the operators lower the reactor coolant system i pressure and temperature to the appropriate conditions, and place the normal residual
, heat removal system into service. The normal residual heat removal system, in I conjunction with the component cooling water system and service water system are )
'used to cool the plant at least 50"F without exceeding prescribed cooldown limits.
Performance Criteria j., The operators successfully demonstrate the ability transfer control of the plant to the remote
- shutdown workstation, shut down the reactor, maintain hot standby, and the demonstrate the
- ability to transition to cold shutdown conditions, while performing these operations from the j remote shutdown workstation. , ;
i i i
oec e' #'- g# $' 1s1%
, @f at.Y4 'g60 AP600 Open Item Tracking System
.tf## gu B p' sill Project Status Report 1'
C
$N
$ ,,s
- Selection: Full Selection cp WY
/ Status as of: [ 6/387 l e.s
- Resolution Status (W / NRC)
E# Dropped Confrm-W Confrm-N Audit N Action W Action N Resolved Closed Total DSER-01 0 / 0 15 / 17 9 / 1 1 / 0 67 / 185 41 / 300 5 / 495 1114 / 254 1252 / 1252 DSER - Confirmatory 0 / 0 0 / 0 0 / 0 0 / 0 1 / 17 1 / 2 0 / 27 78 / 14 80 / 80 DSER-COL 0 / 0 0 / 0 0 / 0 0 / 0 2 /. 6 1 / 37 0 / 62 162 / 60 165 / 165 DSER - 0150 62 / 62 0 / 0 0 / 0 0 / 0 0 / 0 0 / 0 0 / 0 0 / 0 62 / 62 RAl - OI O / 0 5 / 1 4 / 2 0 / 0 752 / 915 47 / 639 0 / 217 1295 / 329 2103 / 2103 RAl-Confirmatory 0 / 0 0 / 0 0 / 0 0 / 0 0 / 0 0 / 0 0 / 0 0 / 0 0 / 0 Meeting - OI 1 / 1 3 / 6 2 / 1 0 / 0 253 / 324 40 / 204 3 / 171 624 / 219 926 / 926 Teleconference- OI O / 0 0 / 0 4 / 0 0 / 0 5 / 22 6 / 10 0 / 15 41 / 9 56 / 56 Key lssue 0 / 0 0 / 0 0 / 0 0 / 0 34 / 43 5 / 1 0 / 1 6 / 0 45 / 45 Total: 63 / 63 23 / 24 19 / 4 1 / 0 1114 / 1512 141 / 1193 8 / 988 3320 / 905 4689 / 4689 e
W umb Westinghouse PAX UOVER bhtci RECIPIENT INFORMATION SENDER INFORMATION OATE: Lug / /997 NAME: y, aj Q),y TO: LOCATION: Im EMod ENERGY CENTER - EAST PHONE: FACSIMil.E: PHONE: _ Office: th2- 374- 5 29o COMPANY: Fecsimite: win: 204 4867 U S A.!/2 C outside: (412)374 4887 , LOCATION: 8 Cover + Pages 1+3 The following pages are being sent from the Westinghouse Energy Center East Tower, 4 Monroeville, PA. If any problems occur during this transmission, please call: WIN: 284 5125 (Janice) or Outside: (412)374 5125. COMMENTS:
$rn acu au rw a sw_ rx w as .
i N 9 h
.I.
e
. a
! s ai l
- - x .. ... . G. . .
- . .
4 i 4
' . umun nur
-l, LOW POINT EL 100'-0' 4
m .. .. .. . .. .. I' 1 f-is0 TON CRAE
!' [l t MAIN NOOK -"T RAIL sTOP EL. lsr-O'N; evns l' m
g g dp"Avi ~ }3! , TOP W RAD. a IsP-4* i iTON- rp '. l JIB CRAE as ,l 4 " rw J t m = , _ _ _ .. I, ,i i l l8 p i i li / !. ww rua marrne CONTAnans i . A g ira , &m4.
~- M .
bd t r= a l . l ll a ,3,.y I - /-'*
- C " $ ik" !
. st.__$$lh Anna 9
- I
<-o'v x r e N s'aan o00RTNIcK suons s
l
! + + fvi I i nuevAaLE II CASK
/ f'L W XsuDDs 74' N 000R l
L.L.J COVER Nl \ 4 p/ glI , p.0'acK s' D t . I I oIse0s4 '4 o 4 l PENT REM TAMS I vss-m o A %. l l l l'" CONTADeR a no..o.
- \ t' Q k p., etm L .,,-
g ,' l AIR TIONT DOOR ir-Ov x is-em
- wss-s -ols % .f. y j g j 1 saTHIca suo't-w 7y .
T, ,,
" ** d ij l
. i t !
i I dN /M M"'"' \ l. l l l . ! srs a , srs ru m . srs a as rum r = l- sano wAu. j E-Olt l W-Cl3 l E -01A W otA l i 4 $ . k i $ I i.j qi yl e I a ar-so i a ! l i k ! l Jd W l' N , ar-e' i Ern.uerr ) I ! errundr l E !
- I1' I(f. f' 9 " Tant .]
{ a w4'
' )$ k -[ l-- notaur ""^ .
Tp---[--) :! l , a w4' i ' i Ii a sa-e- I' I i ! 4 ii a sa4' w e ! p? w
-- -2 4'
_ ie4' ar-o' ar-O' -su er e' g-(oup-ANE X BLoG ar-s'i a . f Hs ' h L2 p f' Os2 J-i
@H p v4 po4 ;p f N
p4 gg@/J [HECTION C-C Y y L ooK .m NOAM V yuO 5 g1
__ _ _ _ _ _ . _ . _ _ . _ . _ _ _ . _ . . _ . __.__.__._..___m.____ = _ _ _ _ . _ _ _
.\
1000 P2 903 1000 P2 903 1000 P2 909 l i f C f H fI l REMOVABLE FUEL HANDLING ! COVER MACH. MAST LIMITS U. CRANE RAIL TRANSFER CANAL l i
}
l 2'-3' NEW FUEL ELEVATOR f l AND TOOL STORAGE AREA l l n ,n y g -- f-- , f-- . y N y' EL 98'-l" t h / T-o s .(.1 --
} h '/ s N ' N
/'h .-
.I, -_..-. . . .- -. . . _ . . _ . . _ ']. ,
p .,
,. ... , _ i i
'/
~
l TON JIB e
,/ I, l !
- bi CRANE -- - " l A' ,
I . / l 1 - [ Jk A h CRANE i
' I-STOP3 I I
, 1000 P2 901 '
- nnmm nunn m unnu m :i : 'I -
l h ] .p - - . . - . - . _.( _ . . . _ . _ . I VI
._. j ._g. ._g yg l
. I.
w i ! '
) ! ! R4TCW d, i 4 h i w
= '
l j [s-s<= i, REMOVABLE l
=7,~- ' =emen
, m.
l l w i l J-2 -- {phlCH ,, ___ ,,gn _ _i__________ l l -l- ' l f%d /' 'g_ _ . M HAPOt.ING ' l j jg 9 i iREMOVAN.E! J j hyAg[! l MACHINE l 8'-O'_ , j
~
! 1000 P 909 V_'___ _ Th~5 gog i _p! N .L LIMITS l EL.153' LN
$A T 'l l3 ;l l ;
JkG i.
\ !
1000'P2 904 1 " o I .\
' / .y' m- . . - . + . .
~ -
i . . g
*. ' CRANE RAILU.
H h , ew C H I ANNEX BUILDING (REF. COL. LIPO 3f 1000 P2 909 JLM 1000 P2 908 t Mf [$
# 1000 P2 903 1000 P2 903 L , d" 22'-0* 22'-O' 22'-0*
3 t-s D'> 137'-O' I 2 3 4
1000 P2 903 1000 P2 903 1000 P2 909 4 C H I I - 1 i' REMOVABLE FUEL HANDLING l COVER MACH. MAST LIMITS ! { R CRAE RAIL TRANSFER CANAL l f I l 2'-3' . NEW FUEL ELEVATOR 1
= -
AND TOOL STORAGE AREA l l
@v .c
?
- y. --i g-- ',- ,' i l] N y' EL W -l' t--- - - -
A A , ._ N N
/ f. ;,
/s ! 7 N - -
- L2 r r/ i 3y-3 ___ -lj , i i - t' ,
. u, I TON JIB\[e
CRANE - -
/ ! /
l j , g l j( i dL A h CaAaE STOPm i l i,a - 1 1 1000 P2 901 :iiiiiiiiii llllllllllllllllillll
- l l
9 j l :1 , l .4 . _ . ._ _. . . q ...
.. . J ._ . g. . _ . . l.
..3 l l ! l' g__EEMi3Vil 8
Pi N j
~
9 l liM lNhsATCp- Q M__u i , , 9 _ k k w w D ; i I j g I N lREMOVA8LE
/r- I m. l h
e l 4 l J-2 -- f tphb-jl -- -- - - J - -- i [sis r - s_._ _ _ _ _ _/,,
. -FUEL. HANDUM ' '
I
. 'I o j i iREMOVABLEI I
'l'
' REMOVA8LE
pl' MACHINE l: s'-O i J LR .T l l I
=l I
.J'
< e . i "AL.TC.H
. L ._ g- HAT.C(M .1 i
! 1000 P2 909
~
l V N~ V -- . .I. I N MAIN HOOK l I i CRANE N
?'*. "
t g.-- E 153'Q.%. ______ri
.L LIMITS LADDER
- i l
STOP ll g l DN 4 9
"?
' !i 6 l %
. I '
II / l' ' i J LG i \ il ' il l 1000'P2 904 o " 1 I '\ _._.Q'._._
,/
_ . . _ ._.._._. ._ . .j. .1 l q ' ' CRAE RAILh i .' = 2'-0* H N = i y ANNEX BUILDING U+ C H I (REF. COL. LINE) tM [w d
# 1000 P2 903 1000 P2 903 1000 P2 909 d LM p, $p ; 1000 P2 908 d" i
i pG i i L , ,P 22*-0* 22'-0* 22'-0* U o t- - l b> 137'-O' 4 1 2 3 4 L W
1* t f1l97 70 : 6 W M u fftnem Nom: kobin /l)fchs
& 816wn In NSs 73 3,3./ tharky ,1his 5 how & w?/' acWress 1}te ~3 v.s y chansch ~
isso e , d j Omrlm n
& markup faxed presos/y this bd)aAr (sx7 (w the everif s s.z s// .
g dr lh3en/, Ivhen an inoperob/e s chann& elis placed in lypass, fk bp MH ensure ha inop mregd chsnnl is bypsssed . Z b e D e e f) v s addresses be cuern . tot cAn h/k mee abat H Jw 9. f l6f ll Wepm l l '
s. RTS Instrumentation 3.3.1 i 3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation LC0 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 I shall be OPERABLE.
)
i 1 APPLICABILITY: According to Table 3.3.1-1. ACTIONS !
\
-..-----------------------------NOTE--------------
Separate Condition entry is allowed for each inoperable Function. l CONDITION REQUIRED ACTION COMPLETION TIME I A. One or more Functions A.1 Enter the Condition Immediately , with one or more referenced in I required channels Table 3.3.1-1 for the ! inoperable. channel (s). 44 575 B. One manual initiation B.1 Restore manual initiation 5. J'[ hours device inoperable, device to OPERABLE status. J 0_R Verify manual initia on 4 devices, equivale to -72 hours he control ro devices, i he Remote utdown Work tion re OPERABLE and a 'cated operator who is n tinuous c ication ith the co rol room is ationed the devices. OR
- 2. 59 B .A .1 Be in MODE 3. pdhours AND (continued) h AP600 3.3-1 08/96 Amendment 0 w iu o.u moi m oei m
- l RTS Instrumentation i i
3.3.1 l
- ACTIONS (continued)
CONDITION REQUIRED ACTION - COMPLETION TIME
- 2. SS 575 i B. (continued) B./.2 Open reactor trip 96 hours 5 breakers (RTBs).
l A S TS C. One manual initiation C.1 Restore manual T hours C-device inoperable. initiation device to OPERABLE status. OE
+1
, C.2 Open RTBs. Jf hours
, z. S 75 D. One required Power D.1.1_ Reduce THERMAL POWER to # hours #
Range Neutron s 75% RTP. Flux-High channel i inoperable. AND 1 rdie G \ D.1.2 Place inoperable s a' hours channel (s) in bypass. SL.A ( %
- 0. 1. 3 E N S'utt 'dA f . -> I" N'*#
mAtowded 0.1.3 R 5torm cf ? channel; ISO hevr5 WS#E444tE tc OPEPAOLE st:tus. l l cd4ws/. c j PL4cE0 W OR m PA5T. 6 O.2.1.J Place inoperable ghours gannel(s)inbypass. D2I pgy9 6M 4
...........--N0TE-------------
Only required to be performed when 0PDMS is inoperable and the Power Range Neutron Flux input to QPTR is inoperable. 3 ' D.2.2 Perform SR 3.2.4.2 Once per (QPTR verification). 12 hours AN6--- (continued) b AP600 h.3-2 08/96 Amendment 0 miu si.euci ,o. aim.
RTS Instrumentation i 3.3.1 i
' ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME l l
5 75 l D. (continued) -0.2.0 100 hce, a D i Resi. ore [ of 4 domiah ] cv vrceout statu w OR
~
I 2. j D.3 Be in MODE 3. Utfhours 575
. E. One required channel E.1.1 Place inoperable g/, hours E l inoperable, channel (s) in bypass.
E. I. 2 M f. H>nts 1 l R.. ;.2 cf : a... . b 100 h = 2 4[. ; ^# t: 0"E"JOLE :t tus. me
'^'b"ME #E neuanw 0R
,z is 71529 t^> 8Yn4SS S E.2 Be in MODE 3. Ptihours 1 s is F. THERMAL POWER between F.1.1 Place inoperable ghours F P-6 and P-10, one channel (s) in bypass. ,
required Intermediate y Range Neutron Flux channel inoperable,
- 2. MouRS
- r. /.2 4 tcOPIP^.LEeat OR
~--
2. F.2 Reduce THERMAL POWER to ghours
< P-6.
2 F.3 Increase THERMAL POWER ghours to > P-10. (continued) k< h AP600 3.3-3 08/96 Amendment 0 APolitesmeses\18030301.ro6400M4
1 RTS Instrumentation 3.3.1 l ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME srs G. THERMAL POWER between G.1 Suspend operations Immediately G P-6 and P-10, two involving positive required Intermediate reactivity additions. Range Neutron Flux channels inoperable. AND 1 G.2 Reduce THERMAL POWER to Jfhours l
< P-6.
s 7.5 , H. THERMAL POWER < P-6, H.1 Restore 3 of 4 channels Prior to # ! one required to OPERABLE status, increasing Intermediate Range THERMAL POWER Neutron Flux to > P-6 ' channel inoperable. 1 I. On ired Source 1.1 Place inoperable ; Range Neu Flux channel (s) in bypass. ' ( channel inoper . AND W coasdatysd I I.2 ore 3 of 4 channels 168 hours to RABLE status. 1 0_B I.3 Increase THERMAL P0 8 hours to > P-6. J._ than one J.1 Suspend operations Imm ly 0p equi ource Range involving positive fi//AC8 keutronFlu nnel reactivity add .
' pgg)dg p jinoperable.
.2 Ope s. Immediately Required Action associated pletion AND Time ondition I tinued) h AP600 3.3-4 08/96 Amendment 0 mi. o.cowimame
INSERT LC0 3.3.1 GTS I. One required Source I.1 Suspend operations Inunediately I Range Neutron Flux involving positive channel inoperable, reactivity additions. STS J. Two required Source J.1 Open RTBs. Immediately J Range Neutron Flux channels inoperable.
e RTS instrumentation
- ,. 3.3.1 ACTIONS i CONDITION REQUIRED ACTION COMPLETION TIME t
J. ntinued) J.3 Close unborated water ur ~ source isolation valves. J.4 m SR 3.1.1.1 (SDM 1 hour l* verific n). AND Once per
- 12 hours eafter
] a ET5 K. One required channel K.1.1 Place inoperable thours M inoperable. channel (s) in bypass. A&
- k. I .2_ 6M
( t.1.* .e: tere 3 ef ? uiannels los nours-te OPEPa0LE atats . i OR
/ 2.
#N #"#@ K.2 Reduce THERMAL POWER to 17tf hours
*WW #N' # < P-10*
ft.Acse o D G1ht%. c sn L. One required channel L.1.1 Place inoperable A' hours # inoperable. channel (s) in bypass. A , 4./.z 6 hu6
-L. I . j Rester; 3 cf 4 channeis 166 iivui 5 -
-te OPERABLE 5tet;;.
OR
/0 L.2 Reduce THERMAL POWER to )?ti hours
< P-8.
(continued) h AP600 3.3-5 08/96 Amendment 0 miu emoime.om
RTS Instrumentation
,. 3.3.1
-ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME STS M. One required " 1.1 . P' ec n~pe, .Li e - S 5:=: 9 channel / division 92nne!(s)/d!"icir,(3) inoperable. M by ese. C M.1 / Restore 3 of 4 Me hours channels / divisions to OPERABLE status. M
/1 M.2 Be in MODE 3. +7fr hours k
575 N. One required channel N.1 Verify the interlocks 1 hour 5 sf. inoperable, are in required state
, for existing plant l conditions.
( E y . N.2.1 Place the functions 5 hours associated with inoperable interlocks in bypass.
-ANB.
N.2.2 Rcstore 3 of 4 - '00 heart 46terle ds te OPERAOLE
- t:tus.
OR
~
. /3 N.3 Be in MODE 3. Wfr hours (continued) h AP600 3.3-6 08/96 Amendment 0 Ap01w10000301 s00400204 u .
s. RTS Instrumentat' ion * ' 3.3.1 ( .' l ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME srs
- 0. One required channel 0.1 Verify the interlocks 1 hour T*E inoperable. are in required state for existing plant conditions.
OR
~
7 0.2.1 Place the functions g hours associated with inoperable interlocks in bypass.
-ANB-A $ *) Dnctawa S at A if0 Lai..
int ^rlock: t: OP ra"LC st;tus, i OR
~
I
/3 0.3 Be in MODE 2. 4f6 hours Aftco P. One required division P.1.1 Open inoperable RTB in 8 hours 08544 inoperable. one division. ME<FA<Ec
^ 'l
%.f
- r. PE"fS'.E -
.s u t u .
08 ff P.2.1 Be in MODE 3, 4, or 5. R6 hours AND P.2.2 Open RTBs. hours Q . Tw o RE Gk4:4E d Qjgt!!i.S'rO48 8 @ U # o.J>so ons wapstAda. p,yss,o,vs to 1 M (Continued) OPERA &E STAM5 - 9 i l 9.& l . Q.2..I 86 14 M*eE 3, 4, CA S. 7MS 1 us g AP600 Q ,2. 2. O/EA/ RT8s . "7 #dM3 3.3-7 08/96 Amendment 0 AP01sterenees\10030301.#06460294 .
~ "' ' _. ._ - ^
o l l RTS Instrumentation *'*#' 3.3.1 l ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME 1 i trip mechanism Q.1.1 Open inoperable RTB in Q. 8 hour inop le on one one division. ; required ' AND t
.2 Restore 3 4 168 hours l l
divi s to OPERABLE l s. l I 176 hours ! Q.2.1 Be in MODE 3, 4, . AND 17 urs Q.2.2 Open RTBs. S TS R. One required channel / 41. 1 . 1 Piece incper d h 0 hcur; c division inoperable, rh: nacl /divisiun hi (.. lypar:. Akin. g R.1.2 Restore 3 of 4 lhtfhours channels / divisions to OPERABLE . O tus. OR 49
~
R.2 Open RTBs. J M hours s l 1U35LT NED co*J o mons SA7 1 k h AP600 3.3-8 08/96 Amendment 0 AP01ueshoes\10030301.r0HIS0294
INSERT LC0 3.3.1 i
)
l 5 725 One required Source Restore required
)
S. S.1 48 hours 6C l Range Neutron Flux channel to OPERABLE I channel inoperable, status. -l OB S.2 Open RTBs. 49 hours STS T. Required Source T.1 Suspend operations Immediately z, Range Neutron Flux involving positive channe1[(s)] reactivity additions. inoperable. l AND T.2 Close unborated water 1 hour ( source isolation valves. AND T.3 Perform SR 3.1.1.1. I hour AND
. Once per l 12 hours thereafter f
kw
?' i.W
\
- W851lngh0VS8 th UUnn SHEET ' ' ~
- t. l i
l RECIPIENT INFORMATION SENDER INFORMATION I DATE: T'o c e 3 /99 7 NAME: _n (2,g,w TO: LOCATION: ENERGY CENTER - Tm Ee ov'o A/ _ EAST PHONE: FACSIMILE: PHONE: Ot0c e: t/a-3 7c/ yg9o COMPANY: FacsimHO: Q ro,(c win: 204 4887 l outside- (412)374 4887 LOCATION: 8 Cover + Pages 1+3 The following pages are being sent from the Westinghouse Energy Center, East Tower, Monroeville. PA. If any problems occur during this transmission, please call: WIN: 284 5125 (Janice) or Outside: (412)374 5125. u COMMENTS: Mm due is nuaxa c m <uc iu s< n .o mou.wt na C12mcrW Dw m". NM we Dio Alor DELE w ,zous n~s tot n e Q uen w ew r3 Fen. Am 7Ast 6 M erv i aA ou A mmmw pove,yc f u e t- . v b __ _ yid'5 ,
. dW
L.
- 11. Radioactive Waste ManagemeIt !
G w - G E E - T7 3, Ke< , 0 Table 11.5-2 AREA RADIATION MONITOR DETECTOR PARAMETE ; Nominal Range Service Type Detector 1.0E 0 to 1.0E+7 R/hr Containment High Range (Note 3) ; y 1.0E 0 to 1.0E+7 R/hr ! PXSJE-RE160 Containment High Range (Note 3) y 1.0E-0 to 1.0E+7 R/hr PXS-JE-REl61 Containment High Range (Note 3) y 1.0E 0 to 1.0E+7 R/hr PXS JE RE162 Containment High Range (Note 3) y 1.0E 1 to 1.0E+7 mR/hr PXS JE RE163 Primary Sampling Room y 1.0E 1 to 1.0E+4 mR/hr (Note 1) RMSJE RE008 y Containment Area PersonnelHatch 1.0E 1 to 1.0E+4 mR/hr RMSJE RE009 y Main Control Room RMSJE RE010 1.0E 1 to 1.0E+4 mR/hr Chemistrylaboratory Area y 1.0E 1 to 1.0E+4 uR/hr (Note 2) RMSJE RE011 Fuel Handling Area y 1.0E 1 to 1.0E+4 mR/hr RMSJE-RE012 RailCarBay Area /AuxiliaryBldg. y RMSJE RE013 Loading Bay (Note 4) 1.0E 1 to 1.0E+4 mR/hr y LiquidandGaseousRadwaste Area RMS-JE RE014 1.0E 1 to 1.0E+4 mR/hr Technical Support Center y 1.0E l to 1.0E+4 mR/hr RMS-JE RE016 Radwaste Bldg Mobile Systems y RMSJE RE017 Facility (Note 4) 1.0E 1 to 1.0E+4 mR/hr I Hot Machine Shop 7 RMS-JE RE018 1.0E.1 to 1.0E+4 mR.hr Annex Staging & Storage Area 7 RMS !E RE019
--C> monitor and by a portable bridge di i
<!1Radiation levels are monitored by di thei permanent containment area
- 1. d in the main control room.
monitor during refueling operations. 5 The containm monitofand by a portable di i di i monitor ' located tobest ' 2. Radiation levels are monitored id by the perman alarm locally an n the main control measure the increase in exposure rates for this area s of tLand to prov e an room. ! t resins) and dry
- 3. Safety related d 4.
Monitors areas used for storage of wet wastes (including pro wastes. FatHarAhy /.0 E'l to 10 E m#1de-& T [ - ws - 3E- tzcozo Aru-4 Revision: 12 April 30,1997 W Weslingh00$4 11.5 19
^
1, ,
,.. I
- 9. . . , ,
. :.r:C
' g 4 I I s:ve. Q8 2 l j @-. 'tps yhr,m r s
'J.W.2. i: e ll l gg l a v
, sr yy,
- n. .- . ,
'T i3l '1 84
' 'dj y, i g
e+ g
. 3 r
Q,,{ ;
'4n . gi;{ .- .; r
.;.jj
.;.w i,C C C l C ,.(,9
- 1
@ .: y ,
I
- L .. l. ./' t ,.
[ jlT t
/
i A! / 8- ..y@j ' 1' pr i / . l r- v- 'g "'U l . I _ j - i* : r-i'f; .I!*l ( \!I, tiI !e
] g; .., ,,_ !j f* '
s
,+l q,
0 - p . ~- il'
, I
9 .qh,,'* g, ' g, 7 :T, g I kd! ;
. o,f [
a,,n=w.
; , lh 4 ,.
y NI
'v
-s
,i--dgs,, n!Pl;7j ir a fl 1' I
r (A 1
- , y , c.. N, s 7hI hi jif)gvgli ij',i!! C ..
u e il' r 14 r% e++ ,,.J -
,i i
; (14 < n! ~. .g..$y +/ " >
l'
. 4 G, f/
ll ,5)!bl .' !' 9
* , r. q ;^r ' ,j 'w \ n!. '- li.
l : , s
, !. i ; *
' Tid $)N .IA ,p[l h Y / I
* ~'
S (-' , g " e m ,tgy w.9 dm e u . l u p,q s_4
'i ;
i - . . - i i' li
, ] n'ji;,
j ,
~
.::a h !
l5' gi il ,'
'! g l1.,f!
j tg . .. @-4' .M. . . !m rl","f-{ l
' ' .- ! .V q 4Il 1 :
'g. $' . M J---
)
g -M
/!
\' - i 3 *N
; g A A 1 4 a . .. s i. . .
rTrv . h 9 3 9 / @'$ @ ,I h @ ft
.. lij l N ,' %
shI :. !
).!M$k,;
* * .i ?. L.._...*... i
+
b O E N N ri o ', c CN
)
.i G ;
.- I 4
i
= , ,
I . . I
~
4, . i i' :l
}
.f.l'>ih ,Fo1 t
ten !4 ;j:. sA .sd ;. j .
, I i t a e
'i ! ) 3 .'-
e e a e a e e r e .
- f[ F-4 p ; l
. I1 .;t j' !
i i. 3
)". II, I ; hl id i
h!]Ll . i 3 . n' ft. ii. \i UL' ik ; , j llf, y1 8,,C ... ,. M;go i
.'s. L _; w '.]! p [,
t 7oMk.'{ s . j! !, !I:l. c K !; 3
- ; 'i
. n $ M-E+i +.,.i=5(
,4=: --
~
,h _
Q i.c :. .; - 1
,j . '
1 Mr. P!ib?d -F
~ !@ i'
,f 9 T% Wj 'y . l I
" /
/ .... . . _ .:....'
M [' 1 .. ' q 5 ,.,
,1l n[i. :_/ p
}nt.j.;f ' 4 L l
( , ;! ! .!' ::
.3 ,!
l
)! ! '
- .- l 4
k *
!( . . d: 1 h
i t . ; J k. , . d.i I:! ,, gh.I li. I 4 X _ i \ .i 53I !9f!!!! I'! i j
\ ; I wr - l..
t I i(
\\
-A ta
!N t
! t '
p 7%Q t-fi 4j diQL.:::: -!lo i f 7 ' I ' 4
%[ n. , =%pp igfg
--- g.i '
.4
.. t 3 y l9 ,[ j . e *! 1
'1'%[9'l
;I 4 1
,1 s'%. M, d'
. _! k
' .~% '{h f u +97s1
'1,2 E 7'4e i
(! c ti r t ..-J. (d i
,GI. J, u!" *. 4.e
, i-- __
A , s t l j , llf . l
) ., . ws .
1 pi * " fl* *t *
-192 i
i .-8 4
- t. 4 4 4 t. t. 55i.:.
i 54' e,. .a.s . I! .. .a.s
,_ t . . .
p:xr,. _- ._
- i -
1 . I 6 I l 1 i I I j
' f, 1
ll 4 y mumew :.a
r b ! Novendstern, Earl H,08:56 AM 6/5N7., RE: AP600 CHPATER 21 OPEN ITEM l From: "Novendstern, Earl H." <novendeh@ westinghouse.com> To: "'W. Huffman'" <WCH@nrc. gov >
Subject:
RE: AP600 CHPATER 21 OPEN ITEM UPDATE Date: Thu,5 Jun 1997 08:56:47 -0400 X-Priority: 3 Bill - Thanks a lot for taking the time to get Lambrose to focus on statusing OITS. I'm having them entered into the system. Earl Earl H. Novendstern Phone: (412) 374-4790 Fax: (412) 374-4011 ECE - 426 B
> From: W. Huffman[SMTP:WCH@nrc. gov]
> Sent: Thursday, June 05,1997 6:21 AM
> To: . Novendstern, Earl H.
> Cc: Winters, James W.
Subject:
AP600 CHPATER 21 OPEN ITEM UPDATE
> << File: Imbrs-21.upd>>
> Earl,
> attached is an update to Lambros's open items for
> WCT-LBLOCA based on discussions from yesterday's
> telecon.
> FYI ----- ------------ Bill
> j Printed for'"Briam A. McIntyre" <mcintyba@wesmail.com> if]
e-llf Winters, J mes W.,01:25 PM 6/4/97., Wednesd:y Rimindrr of items Ne l From: " Winters, James W." <winterjw @ westinghouse.com> To: "'desl @ nrc. gov'" <desl @nrc. gov >, "'trq@nrc. gov'" <trq@nrc. gov >,
"'jms3 @nre. gov'" <jms3@nre. gov >, "'wch@nrc. gov'" <wch@nrc. gov >
Cc: "*dtj @ nrc. gov'" <dtj @ nrc. gov >, "'tjk2 @ nrc. gov"' <tjk2 @ nrc. gov >,
"McIntyre, Brian A" <mcintyba@ wesmail.com>,
l "Cummins, Ed"
<cumminwe@ westinghouse.com>,
"Vijuk, Robert M."
<vijukirm@ westinghouse.com>,
"Rarig. Bruce E."
<rarigbe@ westinghouse.com>.
"Nydes, Robin K." <nydesrk@ westinghouse.com>,
"Lindgren, Donald A." <lindglda@ westinghouse.com>,
" Haag, Cynthia L."
l:
<haagIcl@ westinghouse.com>,
'" mms @ nrc. gov'" < mms @ nrc. gov >,
"Tupper, Robert B." <tupperrb@wesmail.com>,
" Winters, James W." . ;
<winterjw@ westinghouse.com> l
Subject:
Wednesday Reminder ofItems Needing NRC Acknowledgment Date: Wed,4 Jun 199713:25:41 -0400 X-Priority: 3 l > The background for each of these items is outlined in the Open Items
> Tracking System. They ALL have been addressed by Westinghouse.
> NRC is requested to please acknowledge receipt of information related l > to each of the following Open Items. The reviewer in each case should
- > have a submittal from Westinghouse as identified in OITS for the item.
! > Recognizing that reviewing for completeness of the response in each l > case constitutes an NRC action, we recommend that receipt
'> acknowledgement be accompanied by direction to change their "NRC l > Status" to " Action N". If these are truly " Action W", please provide
> a description of the action Westinghouse is expected to take. We know
> of no action required. Many of these are very (over 6 months) old.
> We are not asking for resolution or even NRC review at this time,just l- > acknowledgement that you have received the information as outlined in l > the OITS Status Detail. If your investigation shows I goofed and
> didn't remove item numbers that I should have, please let me know.
l SCSB - 972, 973, 984, 988,1002,1007,1008,1009,1012,1458,1461, l ! !623,1633,1638,1639,2413,2415,2416,2417,2418,2421,2469,2485, 2487,2496,2502,2503,2504,2505,2512,2514,2718,2883,2884,2885, 2887,2888,2889,3 % 2,3063,3064,3065,3066,3067,3068,3069,3070, ! 3071,3072,3073,3074,3075,3076,3077,3078,3079,3080,3081,3124, - 3125,3126,3127,3128,3129,3091,3198,3200,3202,3208,3210,3211, 3215,3419,3422,4162,4562,4542,4543,5293 i S RXB - 854,1262,1627, 2237, 2238, 2239, 2241, 259, 2343, 2608, 2609, 2610,2611,2615,2688,2739,2922,2923,2924,2925,2927,2960,2961, Printed for " Brian A, McIntyre" <mcintyba@wesmall.com> 1] I
, .- .-. . - - . . . - . ~ = - . . . - . . - . _ . . . . - . _ , . - . _ ~ . - . - - . . - . . - . - i e 1-lj ,w I i 2981,2982,2983,2984,2986,3164,3165,3166,3167,3168,3169,3170, ! 3183,3187,3230,3381,3384,3385,3390,3397,3427,3960,4148,4187, . 4188,4973,5093,5113,5114,5115,5116,5117,5207,5208,5209,5210, 5211.-5212,5213,5214,5215,5216,5217,5218,5219,5221,5222,5223, 5224,5225,5226,5227 ; l HICB - 1521, 1576, 2434, 2436, 2437, 2438, 2439, 2440, 2441, 2442, 2443, 2444,2445,2446,2447,2449,2450,2451,2452,2453,2455,2456,2457, i 2458,2459,2460,2462,2463,5095,5096,5097,5098,5099,5100,5102, ; 5103 l ! l SPLB - 3,4,372,1024,1025, i142,1194,2419,2892,2893,2894,2895, 28 % ,3053,3098,3105,3106,3107,3122,3424,3482,4170,4190,5004 SPSB - 1406,1423,1432,1447,1448,1450,1452,2795,2939,2942,2945, ! 2958,2959,3009,3943,5014,5015,5016,5119,5120,5129,5130,5220 l TSB - 1278,1279,1280,1281,1282,1283,1284,1285,1970,2074,2351, 2352,2353,2354,2355,3054,4224,4225,4226,4227,4971,4972,5250 ECGB - 549, 649, 662, 664, 668. 745, 750, 751, 766, 767, 769, "'72,1885, 2515,5028,5029,5030,'5031,5032,5150 HQMB - 1971,3233,3234,3236,3238,3239,3240,4852 i l EMEB - 27, 798, 800, 801, 805, 814 PDST - 501,502,504,505,1763 PERB - 1023,2387,3520,3521,3522 No Branch Identified - 3961,4145,4182,4615 HHFB - 1525,3941,5247 ADT - 459,1991 i l l ' > Thank' s l: > Jim Winters l - > 412-374-5290 l i l l Printed for " Brian A. McIntyre" <mcintyba@wesmail.com> _ ___2l l
i i Bri n A. mci: tyre,05:42 PM 5/29/97, Summ ry of 5/6 RTNSS mtg l Date: Thu,29 May 199717:42:28 -0400 To: wch@nrc. gov From: " Brian A. McIntyre" <mcintyba@wesmail.com>
Subject:
Summary of 5/6 RTNSS mtg Cc: haagel@ wcsmail.com, meintyba@ wesmail.com, vijukrm@wesmail.com, TRQ@NRC. GOV, mms @nrc. gov, schulztl@ westinghouse.com Bill. l My overview summary of our May 6,1997 management meeting on RTNSS was that . I our proposed ADDITIONAL regulatory oversignts were well received by the staff. Based on that feedback, we agreed to funher develop the proposed oversights for the RTNSS systems identilied in as a part of the post 72 hour approach from our March 14,1997 letter and those identified in WCAP-13856 (September 1993). It was clear that some effort had been made by the staff to respond to my request to provide an explanation of HOW these proposed oversights would address the multitude of concerns the staff has that the staff has indicated that would be resolved if we would only agree to some regulatory oversight on a select number of systems. Your evaluation was that DAS ESF actuation could resolve the PMS common mode failure concern. When the staff was polled, Nick felt that that might be true. Nick also j presented four additional concerns that did not seem to be addressed by any j RTNSS availability controls, but rather were general PRA concerns. Alan said that what he heard helps, with no details as to what that meant. The steps we agreed to were: .
- 1. Determine the scope
- 2. Determine the format
- 3. Determine the number Based on the meeting, I believe we are there on scope, at least for the j systems identified. The staff stillindicates that they are not looking for these systems to be safety related with tech specs. We also seem to be there for the format.
Our observation is that the staff concentrated on the scope and format and still needs to think about how these systems resolve the issues. For i example, would the RNS availability control really help solve an issue, or l simply be a warm feeling. What types of words would you write in your FSER? j We really need to come to grips with that issue. Any suggestions that you have on how to make that happen will be greatly appreciated. I have requested that we meet with Gary prior to the 6/13 senior management meeting to ensure progress continues to be made. l < Printed for " Brian A. Mclatyre" <mcintyha@wesmail.com> 1l , 1 l l I
4
$ i Brian A. McIntyre Bell 412.374.4334 WIN 284.4334 FAX Bell 412.374.4887 FAX WIN 284.4887 l
l l l i l Printed for " Brian A '%felntyre" <meintyba@wesmsil.com> 2I}}