NSD-NRC-96-4849, Provides Status Rept for Open Items Identified in 960724 NRC Ltr Open Items Status Re Several Plant Sys Branch Review Areas for AP600 Advanced Reactor Design

Provides Status Rept for Open Items Identified in 960724 NRC Ltr Open Items Status Re Several Plant Sys Branch Review Areas for AP600 Advanced Reactor Design

ML20129C359
Person / Time
Site:	05200003
Issue date:	10/17/1996
From:	Mcintyre B WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	Quay T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NSD-NRC-96-4849, NUDOCS 9610240005
Download: ML20129C359 (13)

Text

',

Westinghouse Energy Systems Ba 355 Electric Corporation Pmsburgh Pennsylvania 15230-0355 NSD-NRC-96-4849 DCP/NRC0628 Docket No.: STN-52-003 October 17,1996 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 ATTENTION:

T.R. QUAY

SUBJECT:

AP600 DESIGN CERTIFICATION, OPEN ITEM STATUE FOR SEVERAL PLANT SYSTEMS BRANCil REVIEW AREAS

Reference:

NRC letter "Open items Status Regarding Several Plant Systems Branch Review Areas for the AP600 Advanced Reactor Design," dated July 24,1996.

Dear Mr. Quay:

This provides a status report for the open items identified in the Reference. The items from Enclosure 1 of the Reference are addressed as items 3105 through 3123 in the Attachment to this letter. All items from Enclosure 2 of the Reference were identified as " Resolved" except 22. Of these 22,11 were identified as " Action N."

Westinghouse has provided all information requested for these 11 items. Of the remaining 11 items, four (0111.1-4,0111.1-5,0111.2-5 and 0111.5-7) were closed by the issue of Revision 9 of the SSAR in August,1996. Of the remaining seven, five (11.5-4,11.5-9,11.5-10,11.5-12, and 11.5-14) are addressed as items 1189,1194,1195,1197 and 1199 in the Attachment to this letter. Item 11.5-19 was discussed with the NRC. There is no requirement to list principal isotopes measured by area radiation monitor and to do so could be misleading. Item 11.1-3 is addressed as iem 3425 in the Attachment and will be closed upon issue of the RAI review identified by the item if you have any que ions, please contact Jim Winters on (412) 374-5290.

rff Brian A. McIntyre, fanager Advanced Plant Safety and Licensing hY

Attachment:

Open items Related to NRC July 24,1996 letter cc:

W. Iluffman, NRC N. Liparuto, Westinghouse (w/o attachments / enclosures) 9610240005 961017 PDR ADOCK 05200003 i

A PDR l

Q&U ~

AP600 Open Item Tracking System Database: Executive Summ^ry Date: 10/16/96 Select'en:

[ item no] between 3105 And 3123 Sorted by item O Item DSER Section/

Title /Descripion Resp (W)

NRC Wo.

Branch Question Type Detail Status Engineer Status Status letter No /

Dse 3105 NRR/SPLB 9.2.4.2.2 TEL-OI Winters Closed Action W

_Ikminerahzed Water Storage Tank j"A floating top a.xmNy is provided to retard oxygen"- was deleted.

l t

Condensate Storage Tank j"The tank is provided with floatmg top assembly to retard oxygeriingress" - wits deleted

. Westinghouse should explain u hy the flosing top assemNy is not needed.

CkEd - hiention of a floating Dp assemNy to retard oxygen ingress in the desenprion for both the dEnneralized water storage tank and the condend storage tank was deleted because it is unnecessary detail in the SSAR for the nonsafety-related demmeralized wser transfer and storage synem Subsedim l

9.2.4.1.2 states ths the system design basis includes requiring oxygen cement in both the condensare storage tank and the demineraltzed water distribution i system from the demineralized water storage tank to be less than 100 ppb The metini or methods to maintain oxygen content below 100 ppb may include l a floting top assemNy or any of a number of other methods. The method (s) wdl be selec:ed based upon overall plant cost, mamtamability and operabihty tradeoffs. The details of the selected method (s) are not requued to be Tier 2 and therefore not required to be included in the SSAR.

31C3 NRR/SPLB 9.2.4.3.1 TEL-OI Winters Clased Action W I

Normal Operation I

i

'2nd paragraph "A volume of 85000 gal. is reserved in the demineralized water

{

storage tank for use by the chemical and ' 4 tune control system for primary I

plant makeup" - was deleted.

l

, Westinghouse should explain why the reserved water is not needed.

j

, Closed - There is no reason to specify in the SSAR any specific amount of water in the demmeralized user storage tank that is reserved for the chenucal,

'and volume control system or any wher specific demand. SSAR suibsection 9.2.4.1.2 states that a design basis for the demineraliicd water storage tank is !

that it supply a source of demineralized water to the chermcal and volume control makeup pumps dunng startup and required borori ddution evolutions.

i

The demmeralized waer transfer and storage system supplies the sequired amount of water to the chemical and volume and control system for reactor water I mneup. SSAR subsection 9.2 4.2.2 states that the demineralized water storage tank has a capacity of approximately 100.000 gallons. SSAR sulvection 9.2.4.3.1 povides a desmption of system operation which maintains the desired volume to supply the expected demands for demineralized water durmg i

normal plant operatim 3107 NRR/SPLB 9.2.46 lEL-OI Winters Closed Action W Instrument Application lIst paragraph - A level detection system as installed on lxth the demmeralized l

water and condensate storage tanks, level signals are transmitted to the auto-(

lmaric tank level control devices. level alarms are provided in the main control

{

room for the condensate storage tank and the deminerali2ed water storage tank.

Afonitoring of demineralized water transfer and storage system operating data will be performed through the display and processing system" - was deleted.

) Westinghouse should explam how the water level of the demineralized water and condensare storage tank is measured, controlled and alanned.

. Closed - SSAR subsection 9.2.4.6. Revision 8 includes an explanation of the instrumentation systems for AP600. Ibr the demineralized water transfer and :

storage system, as for other systems, monitoring ofinstrumentation shown on a PalD is performed by the data display and processing system. Control is !

performed by the plant control system. Appropnate alarms are provided in the control room. Local indicsion, display and manual control are available in j portaNe display units u hich may be connected to the display and processmg system.

i Page: 1 Total Recortis: I8

AP600 Open Item Tracking System Database: Executive Summ:ry Date: 10/16/96 Selection:

[ item no]letween 3105 And 3123 Sorted by item #

Item DSER Section/

Title /Descripion Resp (W)

NRC No.

firanch Question Type Detail Status Engineer Status Status Letter No. /

Date 3103 NRR/SPLB 9.2.5.2.2 TEL-OI Winters Closed Resolved Potable Water Storage Tank

The potable wat'-r storage facility consists of a *2000 gal? cartum steel tar k with, while the "2000 gal

• was deleted. The information on tank _ size is needed.

Oosed - SSAR sidwection 9.2.5.2.2. Revision 9, indicate = the approximate size of the potable water storage tank.

j i

NRC Status Update provided in September 5,1996 letter l

l In a fax dated July 23,1996, Westinghouse provided a draft markup of i SSAR 9.2.5.2.2. The staff found this change accepable. The staff

[ seviewed the change in Revision 9. This item is resolved. Resolved i

3109 NRR/SPLB 9.2.5.3 TEL-OI Winters Clowd Resolved

. System Operaticn

!4th paragraph - 1% table water is not supplied to other areas that are potentially contaminated!- was deleted.

f 5th paragraph - No interconnection exist between the pxable water system and "any ptentially radioactive system" or any system using water for purpose 3other than domestic water serviw,in which,"any pwentially raductive system' was deleted.

f

Westinghouse should explain how the system can satisfy GDC N) without

'the deleted statements.

Closed - SSAR subsection 9.2.5.3, Revision 9, indicates that there are no interconnections between potable water and potentially radioactive systems.

l I

'NRC Starus Update provided in Septerrber 5,1996 le ter:

i f in a fax dated July 23,1996, Westinghouse provided a draft markup of I

! SSAR 9.2.5.4. The staff found this change acceptable. The staff

, reviewed the change in Revision 9. This item is resolved. Resolved 3110 NRP/SPLB 9.2.6. l.2 TEL-OI Winters Gosed Resolved Power Generation Design Basis lThe sanatary dramage system is designed to accommodate 25 gallons / person

'/ day for 500 persons during a 24 - hour period. The '500 persons" was replaad

'with 'We largest number of perso s expected at the station? What is the

largest numb _er of persons at the.arion?

g Closed - SSAR subsection 9.2.6.1.2, Revision 9, indicates the approximate number of persons used to design the sanitary drainage system for the portion of I the plant covered by Design Cettification.

l

.NRC Status Update provided in September 5,1996 letter:

[

! In a fax dated July 23,1996, Westinghouse provided a draft markup of SSAR 9.2.6.1.2. The staff found this change acceptable. The stati

< reviewed the change in Revision 9. This item is resolved. Resolved Page: 2 Total Records: I8

AP600 Open item Tracking System Database: Executive Summ.ry Date: 10/16/96 Selection:

[ item no] between 3105 And 3123 Sorted by item #

j Item DSER Secton/

Title /Descripton Resp (W)

NRC

~

I No.

Branch Question Type Detail Status Engmeer Status Staus letter No. /

Date I

3Ill NRR/SI1 B 9.2.10.2.1 TTi-OI Winters Closed Resolved General Desenption Ist paragraph - Major ma==aata of the heating system include heat exchangers, purnps, a surge tank, and a chernical feed tank."- was deleted.

jihis informarmn is needed.

Closed - SSAR subsecnon 9.2.1011. Revision 9, includes a list of the major -W.;in the hot water heming systern.

NRC Staus Update provided in September 5,1996 letter-

.In a fat dmed July 24,1996, Westinghouse provided a draft markup of l

i SSAR 911011. The staff found this change acaptable. The staff

[ resiewed the change in Revision 9. This item is resolved. Resolved

(

3112 NRR/SPLB 9.2.10.2.2 Tri-OI Winters Closed Resolved Component Discription

[

f Chemical Feed Tank r

i f2nd paragraph - The tank is a 50 gallon vertical c3 nder of carbon steel con-h T

jstruction, while "50 gal." was deleted. The information on tank sim is

[

Closed - SSAR subsecten 9110.2.2, Revision 9, provides the appropnme informanon on the maximum sum for the chemical addition tank in the hot

' water heating system.

NRC Staus Update provided in September 5,1996 letter:

n a fax dated August 1,1996, Westinghouse provided a draft markup to l SSAR 911012 and 10.4.9.11 The staff for M this change acceptable.

i l The staff reviewed the change in Revision 9. This item is resolved.

Resolved 3II3 NRR/SPLB 10.4.512 1TLOI Winters Closed 3EUved 7

L l Component Discrpoon l

l l

1

. Piping and Valves l2nd paragraph - piping iss designed for 60 psig as are the expansion joints, * - was deleted. The piping design pressure is needed.

l

Circulming Water Chenucal injection j4th paragraph - A sodium hypochlorite tremment system is provided for

! control of micmorganisms which cause foulmg. _ _" The paragraph was deleted. Westinghouse should addrnss an ahemative system if this one is not ised.

Closed - SSAR subsectmn 10.412.2. Revision 6, presides the appropriate informanon on design pressure and biocide for the circulating water system.

l iThe attendant subsection 10.4.12.1, Revision 6, provides appropriate COL informanon items to ensure that proper expansion joints and biocides are

selected and used.

I

'NRC Starus Updme provided in September 5,1996 letter:

In a fax dated July 26,1996, Westinghouw provided a draft markup of 7

SSAR 10.4.5.2.2. The staff found this change acaptable. The staff reviewed the change in Revision 9. This item is teso!ved. Resolved

]

Page: 3 Total Records: 18

AP600 Open Item Tracking System Database: Executive Summtry Date: 10/16/96 Selection:

[ item no] between 3105 And 3123 Sorted by item #

' Resp (W)

NRC Item DSER Section/

Title / Description No.

Branch Question Type Detad Status Engmeer Starus Status letterNo. /

Date 3114 NRR/SPLB 10.4.5.5 TEL-OI Winters Closed Resolved

.insmanentation Applicsions 3rd paragraph - the pressure transmitter also provides indicmion in the control room and provides a signal to the plant computer * - was deleted. His

'informanon is needed.

,7th paragraph - The circulating waser chemistry is controled by cochng tower blowdown and chenucal addition "to maintain the circulation water at a

'Imgelier Index in the range of +0.1 to +0.2 or a Stability Index in the range of l7.0 to 7.5", while the numbers were deleted. His information is needed.

" Closed - SSAR subsection 10.4.5.5, Revision 9, provides the appro[riate information on imuu.~Mie for the circulating water system. The attendant l subsection 10.4.12.1. Revision 9, provides appropriate COL information items to ensure that proper operating limits on water chenustry are se used.

lNRC Status Update provided in September 5,1996 letter; j

.in a fax dated July 26,1996, Westinghouse provided a draft markup of SSAR 10.4.5.5 He staff found this change acceptable. The staff reviewed the change in Revision 9. His item is resolved. Resolved 3115 NRR/SPLB 10.4.7.1.1 TEl OI Winters Closed Resolved Safety Design Basis Ist paragraph - the isolation valves close within 10 seconds after receipt of an isolation signal? - was deleted. His information is needed.

Closed - As agreed, SS AR subsection 10.4.7.1.1, Revision 9, provides the appropriate referena to the Technical Specificmions for feedwater isolation j

l closure times. De valve closure assumed in safety analyses is 10 seconds, except where used for mass and energy releases into containment where 5

! seconds is used. Consistent with the evaluation of the effects of these release on containment, the Technical Specifications will include the proper value

' assumed by Safety Analysis.

f NRC Status Update provided in September 5,1996 letter:

In a fax dated July 26,1996, Westinghouse provided a draft markup of l

SSAR 10.4.7.1.1. De staff found this change acaptable. De staff l

reviewed the change in Revision 9. His item is resobed. Resolved i

i

{

e k

s b

b i

P Page: 4 Total Rectmis: 18 I

...m AP600 Open Item Tracking System Database: Executive Summcry Date: 10/16/96 Selection:

[ item no] betweeri 3105 And '*23 Sorted by item #

Item DSER Sectmn/

Title,1)escripion Resp (W)

NRC No.

Branch Questen Type Detail Staus Engineer Status Status leter No. /

Dale 3116 NRR/SPLB 10.4.7.1.2 TEL-OI Winters Closed Resolved Power Generation Design Basis

+

j4th paragraph - De pumps and other system components are designed to

! avoid the need for an immediate trip of the condensme, feedwwr booster, or

'feedwater pumps on low net positive suction head." - was deleted. His

[information is needed.

Closed - SSAR subsection 10.4.7.1.2, Revision 9, provides the approprime design basis for protection of the pumps from opersing with low net positive jsuction head.

,NRC Staus Updse provided in September 5,1996 letter:

i

' In a fax dated July 29,1996, Westinghouse provided a draft markup of l

SSAR 10.4.7.1. De staff found this change acceptable. The staff reviewed the change in Revision 9. His item is resolved. Resolved i

3117 NRR/SPLB 10.4.7.2.1 1El OI Winters Closed Resolved 3

General

Description:

l l4th paragraph - Steam is provaled to the deaeration feedwater heater fmm the

l. auxiliary steam supply system to preheat the feedwater 70 about 225-250 F'

'during the initial cleanup and startup recirculation operations, while the

{emperature was deleted. His information is needed.

+

' Closed - SSAR subcection 10.4.7.2.1, Revision 9, prosides a range for hesup of the feedweer during startup.

l lNRC Status Update provided in September 5,1996 letter:

In a fax dated July 29,1996, Westinghouse provided a draft markup of SSAR 10.4.7.2.1. De staff found this change acceptable. The staff f reviewed the change in Revision 9. His item is resolved. Resolved 3119 NRR/SPLB 10.4.7.2.3 TEL-OI Winters Closed Resolved I'lant Shutdown:

f lIst paragraph - As power is decreased "below 50 percent of full-load condensate flow " one of the two operating cmdensse pumps may be stopped.

l lWhile "below 50 percent of full-load condensare flow" was deleted,it should stay.

[

F

, Paragraphs 2 and 3 were deleted and a new paragraph was added. However,the new paragraph did not a$ dress the plant conditions following reactor nip or when bringing theplant to cold shutdown. De new paragraph should include this informanon

.}

Closed - SSAR subsectmn 10.4.7.2.3.3, Revision 9, provides the appropriate references to reactor inp and cold shutdown dunng plant shutdown. Dere is

no reason to limit shutting of condensate pumps to well less than 50% of full-load condensate flow. If a pump were shut down at a higher flow design

controls and alanns would activate. See SSAR subsection 10.4.7.2.2 for the pump design requuements of 50% of fullload. However,if the condensse

' flow were less than about 70%, depending on waer im.a. a single pump could supply the required flow.

l NRC Staus Update provided in September 5,1996 letter-In a fax dated July 29,1996 Westinghouse provided a draA markup of l

I SSAR 10.4.7.2.3.3. The sta'f found this change acceptable. He staff l

[

reviewed the change in Revision 9. his item is resolved. Resolved I

i f

Page: 5 Total Records: I8 m______m m

m

m.....

=

s ww AIY90 Open Item Tracking System Database: Executive Summ:ry Date: 10/16/96 Selection:

[ item no] between 3105 And 3123 Sorted by item #

Item DSER Section/

Title /Descripim Resp (W)

NRC No.

Branch Question Type Detad Status Engineer Status Status Letter No /

Date 3120 NRR/SPLB 10.4.7.5 TEL4)I Winters Chwed Actim W Instmmentation Applications:

l l3rd paragraph - De main feedwater pump speed vanes to maintain a programed pressure differential "between the steam header and the feed pump l

l discharge header" - this 'information" was deleted, it should stay.

I 4th paragraph " Automatic rectreulation valves are provided in the discharge lines from each condensate pump.* - was deleted. These valves are required l to protect the pumps from becoming vapor tamd and should not be removed.

{

,5th paragraph "A flow cierrent is installed i' the discharge of each of the steam generator feedwater pumps to provide the control signal to open the minimum recurculation flow filves in order tt n 9tect the steam generator feedwater pumps."- was deleted. This infonnation is needed.

j Closed - 3rd par.: graph - he pmgrammed pressure differential is obtamed across the feedwater control salve as written in this p tragraph of SSAR

{

subsection 10.4.7.5, Revision 6.

{

Closed - 4th paragraph - Here are a number of recirculation pshs for the condensate pumps as shown on SSAR Figure 10.4.7-1 (Sheet I of 4), Revision

6. These paths include through the polishers to the hotwell or to the condensate storage tank. No further explanaion is required in the text of the SSAR.

Closed - 5th paragrapg - W sentence indrated was moved to the third paragraph, not deleted. _ _

_ _ __ _ j 312I NRR/SPLB 10.4.9.1.I TEIA)I Winters Closed Action W 5afety Design Basis

~

l Jst and 3rd paragraphs "The isolation valves chwe within 10 seconds after receipt of an isolation signal? - was &leted. He valve chwure time is needed !

[hhindicated for Open item 3115, the feedwater isolatioNalve closure time is identified in tETechnical Specifications j

3122 NRR/SPLB 10.4,9.I.2 TEL-Ol Winters Closed Action W

. Power Generation Design Basis:

l lIst paragraph "The startup feedwater system is a nonsafety-related system serving as a first line of defense for loss of feedwater events? - was deleted.

[This statement is required for the RTNSS review.

{

Closed - The identification of the startup feedwater system as a nonsafety-related system serving as a first line of defense for loss of feedwater events is not l k

an appropnate power generation design basis entry in the SSAR. De definition of systems and their contribution to RTNSS is contained in the PRA.

QAACs and in SSA_R sections which descnbe our graded _ approach and the differentration between safety-related and defense-indepth sys. ems.

3123 NRR/SPLil 10.4.9.2.2 TEL4)I Winters Closed Resolved

- -. - _. _ _ Component

Description:

Startup I' edwater Control Valve:

v 3rd paragraph "The SFCF will ckwe in 10 seconds or less"- was deleted,it should stay.

Startup Feedwater Isolation Valve:

3rd paragraph -De startup feedwater isolation valve and "Startup feedwater isolation valve

• provide isolation of the nonsafety-related pations of the system from the safety-related portions. The second isolation valve should be_startup feedwater control valve.

Closed - As indicated for Open item 3115, consistent with the evaluation of the effects of mass and energy releases on contamnent, the Technical _ _ _ _ _ _ _ _

l Specificatons will include the proper value assumed by Safety Analysis for fcedwater isolation valve closure tirrr. SSAR subsection 10.4.9 2.2, Revision j 9, correctly identifies the control valve in lieu of the isolation valve.

I

NRC Status Update provided in September 5,1996 letter

l In a fax dated August 1,19%, Westinghouse provided a draft markup to i SS AR 10.4.9.2.2. The staff found this change acceptable. The reviewed i

j the change in Revision 9 of the SSAR. This item is resolved. Resolved l

Page: 6 Total Recordr.. I8

?

8

AP600 Open Item Tracking System Database: Executive Sumncry Date: 10/16/96 Selection:

[DSER Section] like 'l 1.5-4' Sorted by Item 0 hem DSER Section/

Tide /Descriptkm Resp (W)

NRC No.

Branch Question Type Detail Status Engineer Status Status Letter No. /

Ihre i189 NRR/SPLB i 1.5-4 DSER-OI israelson, G/BPC Closed Resolved NTD-NRC-95-4464 l(k2 DIATION310N11DRING SYSW 1,5IS) Section I1.5 of the SSAR does not explain why the containnent atmosphere particulate detector (k[

.. _ _ _. _ _.[reacte coolant pressure boundary leak detection system) is non-seismic Category I and receives power from norplE power supply.

___ _ __j Cksd - SS AR, section 1 I 3.23.2, Rev. 3, descnbes the Containnent Atmosphere Radiation Monitor as being seismically qualified per Reg. Guide 1.100_ _ _ _ _. _.

ilhese detectors are not used for accident and post-accident monitonng. The Class 1E containment radiation monitors funcnons are discussed in section ilI.5.1.1 and these Containment liigh Radiation Monitors are discussed in section iI.5.23.2.

01 - Acton W - provide justification for meeting m6.u~n for design change for RCP boundary leakage.

I f

Ckwed -The applicable RegGuide on recomnended radiation monitors provides suggestions and indicates that a containnent atmosphere particulate detector may be used to help monitor leakage Imm the reactor coolant lunindary. SS AR sutwection 5.2.5, Revision 5, includes a comprehensive discussion

on detection leakage through the reactor coolant boundary. Part of this discussion details which instrumentation is used and how. NRC has accepted this !

' AP600 position on leak detection for use with the leak-before4reak position. The requirements for detectable leakage for leak before-break are rrmwe than ;

generally used in for operating plants. Therefore, since the leak detection position in SSAR subsection 5.2.5 is accepted withatu particulate detectors and j since the RE_GGuide suggests but_d_ose not, require particulare detectors, there is no requirement for purticulate detectors in AP600.

__ _ __ __j Page: 1 Total Records: 1

- AP600 Open Item Tracking System Database: Executive Summ~ry Date: 10/16/96 Selection:

[DSER Sectici] like '11.5-9' Sorted by Item #

[

t ltem DSER Section/

Title /Descripion Resp (W)

NRC

. No.

Branch Question Type' Detail Status Engineer Status Status 1stierNo /

- Date I

4 1194 NRR/SPt.B 11.5-9 DSER-OI Israelson,G/BPC Closed Active NTD-NRC-95-4464 jWestinghouse should included grab sangling and contmunus sampling provisions for iodine activity in the -- :--- --t parge exhaust.

Closed All rad

ologic21y cantrolled areas ventilation systems exhaust through the plant vent. VFS-M6001, Rev. 5 shows a matmuous samphng for

gases, iodines and particulares. This PalD is included in SSAR, Rev. 3. SSAR section 11.5.2.33 Rev. 3 includes a stasement that the plant vent radiation l monitor has particulase, iodine, and gaseous grab sampling capability.

l

.OI - Action W - review for design changes and add additional informanon to SSAR.

7 l

I Closed - SSAR Table 93.3-2, Revision 8, Figure 9.4.7-1, Revision 7 and Table i1.5-l, Revision 8, indicate that grab sampling and continuous sampling provisions are provided on the plant vent, which is the containment purge exhaust.

L l

t i

i i

b 6

i i

?

k l

t Page: 1 Total Record.s: 1 i

AP600 Open Item Tracking System Database: Executive Summ:ry Datn 10/16/96 Selection:

. [DSER Sectica] like 'l 1.5-10' Sorted by item #

1 item DSER Secnod Title /Desenpuon Resp (W)

NRC l~

No.

Branch Question Type Detail Status Engineer Status Status letter No. /

Dae 1195 NRR/SPLB 11.5-10

' DSER-OI Israelson G/SCS Closed Active jWestinghouse should include conunuous sampling and analysis provisions for servia weer system effluent. Provision of a continuous radizion monitor in an effluent line is not the same as provision of continuous sampling capability for the line.

4 Closed - RAI 460.7RI provided a discussion of the radiatwn monitor in the SWS. SWS blowdown radiation monitor descrgeon added SSAR. section l11.5.2.3.1, Rev. 3. SSAR Table 9.3.4-1,was revised to include the SWS radiauon rnonitor. The SWS includes provisions for cununuous sampling and l analysis of the blowdown using temporary equipment connected to the grab sample connection shown on the system PalD.

l i

j

'01 - Action W - review for design changes and add additional information to SSAR.

j I

i Closed - SSAR subsecnon 9.2.1 and 9.2.2 describe the functions and relationships between the senice wwer syssem and the component cooling waer Isystem. Unlike some plants, the AP600 system called the service water system has no interfaces with systems carrying rmlicactive or potentially

'radioacave fluids. It cools the component cooling weer system which provides the primary boundary to radioactive fluids. Two pressure boundary

[

, breaches are required to contaminate the service water system. As a result, continuous sampling and analysis provisions for service waser system effluent is

'not required for AP600.

t i

I i

i h

i t

I i

i t

7 Page: 1 Total Records: I

AP600 Open Item Tracking System Database: Executive Sumanry Dat : 10/16/96 L

Selection:

[DSER Section] like 'l 1,5-12* Sorted by item #

1 Item DSER Section/

Titic/ Description Resp (W)

NRC No.

Branch Question Type Detail Status Engmeer Swus Status Letter No. I Date-1197 NRR/Sti_B I I.S.12 DSER4)I Israelson, G.

Closed Active jWestinghouse should explain the purposes of the grab sampimg and analysis provisions for the component coohng water system, service water system

effluent stream, SG blowdown stream, turbine building drains, and wasse waeer drains. In additia Wes'inghouse should indicase if grab sampling and

analysis pmvisions for tritium activity are included for the above system, streams and drains.

j

Closed - The purpose of sampling is described in SSAR sections 933 (pnmary sampling) and 93.4 (secondary sampling). SSAR Tables 933-I and 933-2, revised to include tntium as one of the radioisotopes which is analyzed in both primary and secondary systems sampling.

i

.OI - Action W - review for design changes and add addrtional information to SSAR.

l

Closed - SSAR Table 933-2, Revision 8, includes proper grab sampling and analysis provisions for AP600.

I a

r t

l I

I t

6 t

i Page: 1 Total Records: I J

A

~

AP600 Open Item Tracking System Database: Executive Sununay -

Date: 10/16/96 Selection:

[DSER Section] like 'l 1.5-14' Sorted by item #

lean DSER Sectionf Title /Dex%ption Resp (W)

NRC 1

No.

Branch Question ~

Type Detail Status Engmeer Status Status letterNo. I Date 1199 NRR/SPLB 11.5-14 DSER-OI Israelson, GlSCS Comed Active

Westinghouse should include grab sampling and analysis provisions for secondary resir. slurry streant

[r IClosed - SSAR sectwns 10.4.63 and 10.4.8.23.6, mere revised to desaibe provisions to handle and contain radionaive secundary system spent resin. The i

jsSAR retisions stase that radioactive spent resin processing will be performed in the Auxiliary Buddmg loading bay with mobile equipment. Solid I

radwaste handling, sampling and proussing in the Auxilimy Building loading bay is described in SSAR section 11.4.

01 - Action W - review for design changes and add aiditional inforrnarn to SSAR.

I Closed - SSAR Table 933-2, Revision 8, includes the appropnate sampling and analysis provisions for the secondary resin slurry strearn.

I t

i i

b t

i I

I t

h I

I i

k i

i 4

i 6

Page: 1 Total Records: I j

i s

t

~m.

,-..-,%,w~--.

-.m

... w..

m

.,- +

w,+

.-n.

.v-

x 4

AP600 Open Item Tracking System Database: Executive Summcry Date: 10/16/96 Selection:

[DSER Section] like 'l 1.1-3' Sorted by item O Item DSER Section/

% 9 Title /Descriph Resp (W)

NRC No.

Branch -

Question Type Detail Status Engineer Status Starus letter No. I Datd 3425 NRR/SPLB 11.1 3 RAICI Winscrs Resolved Action W

,(Received in July 24,1996 NRC letter) lSSAR document. Since WeoJ, house decided not to do so, the responses that are not include This is a new open itent DSER Chapter I I was prepared based on that the responses to requests for adchtional informanon (RAls) would be part of the

! bases for the staff finding. MAR should be revised to include the above information that was only provided in RAI responses and that was used by the staft' las the buses for acceptance documented in the DSER.

l lOne example is show in DSER page 11-24 where the acceptance was based on the responses to Qi60.4th) and Q460.21. Another exmple is showti in DSER page Il-50 where the acceptance was based on the responses to Q460.16. The content of the responses to Q860.4(b), Qt60.21, and Qt60.16

!should be included in the SSAR. There are quite a few items of this nature. Westinghouse is requested to review DSER Chapter ii to identify and revise the SSAR for all those items.

! Action W - Westinghouse will review the RAI responses relied upon in the NRC DSER and will provide the NRC an explanation of where they are l addressed in the cunent SSAR or why they dont need to be in the SSAR.

Closed - Westinghouse recognizes that the level ofinformation of RAls related to SSAR Chapter I I is more detailed than that in SSAR Chapter I1 itself.

1 jThis approach is based on the fact that RAI responses are official Westinglasse information, forwarded by letter, and placed formally on the docket. We iconsider them to be artification support documents similar to test data reports or computer code validation reports. As such, they can be used as i

. justification for FSER conclusions. In addition, it is not appropnate to include in Tier 2 information the type of detail contained in the RAI responses.

jWestinghouse is reviewing the relevant RAI responses to ensure that they are consistent with the design described in the SSAR, Revision 9. The results of

this review will be forwarded to NRC by official letter.

J l

' Page: 1 Total Records: I

.... _.....