ML20134F615
| ML20134F615 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 10/28/1996 |
| From: | Mcintyre B WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Quay T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19353D960 | List: |
| References | |
| AW-96-1027, NUDOCS 9611070062 | |
| Download: ML20134F615 (76) | |
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I Westinghouse Energy Systems Bcx 355 Electric Corporation Pittsburgh Pennsylvania 15230 0355 i
AW-96-1027 i
October 28,1996 Document Control Desk i
U.S. Nuclear Regulatory Commission Washington, D.C. 20555 ATTENTION:
T.R. QUAY APPLICATION FOR WITill10LDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE i
SUBJECT:
INFORMAL CORRESPONDENCE
Dear Mr. Quay:
f The application for withholding is submitted by Westinghoure Electric Corporation (" Westinghouse")
pursuant to the provisions of paragraph (b)(1) of Section 2.750 el the Commission's regulations. It centains commercial strategic information proprietary to Westinghouse and customarily held in cer/idence.
The proprietary material for which withholding is being requested is identified in the proprietary version of the subject report. In conformance with 10CFR Section 2.790, Affidavit AW-96-1027 accompanies this application for withholding setting forth the basis on which the identified proprietary information may be withheld from public disclosure.
Accordingly, it is respectfully requested that the subject information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10CFR Section 2.790 of the Conunission's regulations.
Correspondence with respect to this application for withholding or the accompanying affidavit should reference AW-96-1027 and should be addressed to the undersigned.
Very truly yours, 4.-s Brian A. McIntyre. Manager Advanced Plant Safety and Licensing
/nja cc:. Kevin Bohrer NRC 12115 9611070062 961028 PDR ADOCK 05200003 A
PDR 2973A
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AW-%1027 AFFIDAVIT i
l COMMONWEALTil OF PENNSYLVANIA:
ss COUNTY OF ALLEGIIENY:
Before me, the undersigned authority, personally appeared Brian A. McIntyre, who, being by me duly sworn according to law, deposes and says that he is authorized to execute this Affidavit on behalf of Westinghouse Electric Corporation (" Westinghouse") and that the averments of fact set forth
)
in this Affidavit are true and correct to the best of his knowledge, information, and belief:
A Brian A. McIntyre, Manager l
Advanced Plant Safety and Licensing Sworn to and subscribed i
before me his day of
,1996
, [o try Pubre JanetA. c Monroevine Boro. A!!eghany County' My Commission Exp;rss May 22,2000 Member, Pennsylvania troc,ation of Notanes
/
Notary Public 2
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AW-96-1017 1
(1)
I am Manager, Advanced Plant Safety And Licensing, in the Advanced Technology Businesc Area, of the Westinghouse Electric Corporation and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear power plant licensing and rulemaking proceedings, and am authorized to apply for its withholding on behalf of the Westinghouse j
Energy Systems Business Unit.
i l
(2)
I am making this Affidavit in conformance with the provisions of 10CFR Section 2.790 of the Commission's regulations and in conjunction with the Westinghouse application for withholding accompanying this Affidavit.
j (3)
I have personal knowledge of the criteria and procedures utilized by the Westinghouse Energy Systems Business Unit in designating information as a trade secret, privileged or as confidential commercial or financial information.
(4)
Pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld, j
i (i)
The information sought to be withheld from public disclosure is owned and has been held in confidence by Westinghouse.
I (ii)
The information is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the public. Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence. The application of that system and the substance of that system l
constitutes Westinghouse policy and provides the rational basis required.
Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows:
2974A
AW-96-1027 (a)
The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.
(b)
It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability.
(c)
Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.
(d)
It reveals cost or price information, production capacities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers.
(e)
It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse.
(f)
It contains patentable ideas, for which patent protection may be desirable.
There are sound policy reasons behind the Westinghouse system which include the i
following:
)
(a)
The use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors. It is, therefore, withheld from disclosure to protect the Westinghouse competitive position.
(b)
It is information which is marketable in many ways. The extent to which such information is available to competitors diminishes the Westinghouse ability to sell products and services involving the use of the information.
2974A
AW-96-1027 (c)
Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.
(d)
Each comp 3nent of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage. If competitors acquire components of proprietary information, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.
(e)
Unrestricted disclosure would jeopardize the position of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition of those countries.
(f)
The Westinghouse capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a competitive advantage.
(iii)
The information is being transmitted to the Commission in confidence and, under the i
provisions of 10CFR Section 2.790, it is to be received in confidence by the Commission.
(iv)
The information sought to be protected is not available in public sources or available information has not been previously employed in the same original manner or method to the best of our knowledge and belief.
(v)
Enclosed is Letter NSD-NRC-96-4864, October 28,1996 being transmitted by Westinghouse Electric Corporation (E) letter and Application for Withholding Proprietary Information from Public Disclosure, Brian A. McIntyre (E), to Mr. T. R. Quay, Office of NRR. The proprietary information as submitted for use by Westinghouse Electric Corporation is in response to questions concerning the AP600 plant and the associated design certification application and is expected to be applicable in other licensee submittals in response to certain NRC requirements for justification of licensing advanced nuclear power plant designs.
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AW-96-1027 This information is part of that which will enable Westinghouse to:
(a)
Demonstrate the design and safety of the AP600 Passive Safety Systems.
(b)
Establish applicable verification testing methods.
(c)
Design Advanced Nuclear Power Plants that meet NRC requirements.
(d)
Establish technical and licensing approaches for the AP600 that will ultimately result in a certified design.
(e)
Assist customers in obtaining NRC approval for future plants.
Further this information has substantial commercial value as follows:
(a)
Westinghouse plans to sell the use of similar information to its customers for purposes of meeting NRC requirements for advanced plant licenses.
(b)
Westinghouse can sell support and defense of the technology to its customers in the licensing process.
Public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to provide similar advanced nuclear power designs and licensing defense services for commercial power reactors without commensurate expenses. Also, public disclosure of the information would enable others to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the information.
2974A
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AW-%1027 l
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The development of the technology described in part by the information is the result of applying the results of many years of experience in an intensive Westinghouse effort -
and the expenditure of a considerable sum of money.
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In order for competitors of Westinghouse to duplicate this information, similar
]
technical programs would have to be performed and a significant manpower effort, having the requisite talent and experience, would have to be expended for developing analytical methods and receiving NRC approval for those methods.
i Further the deponent sayeth not,
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29744
Attachment I to Westinghouse Letter NSD-NRC-96-4864 (This attachment contains information which is proprietary to Westinghouse Electric Corporation) j i
2973A
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h Westinghouse FAX COVER SHEET D
RECIPIENT INFORMATION SENDER INFORMATION i
f DATE:
8,tt Nupr,eqAM NAME:
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TO:
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LOCATION:
ENERGY CENTER - EAST i
PHONE:
FACSIMILE:
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Office:Il1-Ilaf.g ?,go COMPANY:
Facsimile:
win:
284-4887 j
() [A[k outside: (412)374-4887 LO. CATION:
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1 Cover + Pages 1+$
I The following pages are being sent from the Westinghouse Energy Center, East Tower, MonroeviNo, j
PA. If any problems occur during this transmission, please ca5:
WIN: 284-5125 (Janice) or Outside: (412)374-5125.
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Attachment - Description of_ pH Adjustment Analysis Cases
{
The following discusses two cases which bound the post accident contairunent water pH adjustment of I
the AP600. These cases assume the same release of radioactivity from the RCS during the same time
]
period. The differences between these cases bound the pH adjustment perfonnance and radioactivity release from the AP600. It is expected that case I will result in the largest 2 hr offsite dose. Case 2
{
is expected to result in a larger 30 day offsite dose and control room dose.
Case 1 Challenge to pH Adjustment in Containment j
. Accident - 2" CL LOCA System Operation -
ADS stages 1/2/3 fail, all stage 4 work Two CMT inject Two Accumulatorinject
- IRW3T doesn't inject (causes core damage)
IRWST dump to containment works (both lines)
IRWST gutter doesn't work CVS BAT is injected Comments - All of the activity released from the RCS initially enters the containment atmosphere.
It should be assumed that some water circulates from the containment into / through the IRWST. This assumption results in the largest challenge to the pH in the contamment by mixing in the borated water in the bottom of the IRWST.
Case 2 Challenge to pH A4ustment in IRWST Accident - Spurious ADS (stage 1)
' System Operation -
ADS stages 1/2/3 all work, all stage 4 fail Two Chn inject Two Accumulatorinject IRWST doesn't inject (causes core damage)
IRWST dump to containment works (both lines)
IRWST gutter works CVS BAT is injected Comments - All of the activity released fmm the RCS initially enters the IRWST through the ADS spargers under water. "Ihe IRWST dump is assumed to be initiated just as activity release from RCS is completed. This case will result in water in the bottom of the IRWE that is not mixed with the containment water & TSP (no recirculation should be assumed as was done in case 1). As a result its pH will remain low.
Note that the IRWST has vents to the contamment that open under tank pressurization and close when vent flow stops. Gravity operated louvers close the vents. 'Ihe vent area is about 5% of the IRWST roof surface area. As a result, after the blowdown of the RCS and the subsequent release of activity, the vents are expected to close.-
However, some exchange of IRWE air space with the containment atmosphere should be assumed due to leakage. Sensitivity studies may be required to determine the importance of this assumption.
- TX CONFIRMATION REPORT **
AS OF OCT 24 '96 15: 44 PAGE.01 AP600 DESIGN CERT 4
DATE TIME T0/FROM MODE MIH/SEC PGS STATUS 01 10/24 15:43 813014152002 G3--S 01'03 02 OK
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ENERGY CENTER - EAST i
PHONB:
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PHONE:
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WIN: 284-5125 (Janice) or Outside: (412)374 5125.
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AP600 Open Item Tracking Systen Databege: Esecutive Sennehary Date: 1er2U96 l
Selecties:
[DSER Section) liite 9.4* Sorted by item #
i f
hem DSER Secmon/
Teile/Descnpanon Resp (W)
NkC No Branth Qisensson Type Desad Samus F9-r Status Samus letter No I Dese I
i 263 NMR/SPt_B 942 MTG-Ot Wueers/BRC Closed Rescived i
IM9 4 2-4 ( ANNEX / AUX. BUILDINGS NON R'ADIOAUTIVE huh'C SEST5MS)2tanfy MSIV area deMMime since the AP600 SSAR states T
~
'1 hat the MSIV ases desage semperemme lames is 104 F while the SSAR Table senses that it is 105 F. _ _ __
'~' ~_,, _ _ _ _ _ _
l Closed'- SSAR M9.4.2.1.2,9.4.2.2.I.4 and 9 4123 4. Revannom 75ve been sevised so lie'A=E '
~
I
""8 'ha" ** d'"P~
8'r en MS V ases as 105 F.
269 NMR/SPt2 942 841G-01 Wissen/BRC Closed Acteun W M9 4'2 5kANNEX/ AUX 3UliDINGk~fdRA11U CHVE HVAC SYSHiMSIPiovide$ne[s El woneen'slocker numm e'n'heuss fans dass fur the '
~
~
~
I gamasel men HVAC syneen in Table 9.4.2-2 of she SSAR.
9.4.2.2.1.1,Itevassen 7,i=h a U~of the opaa_ _ _ _A cithe eo St enhemst fans.
~ ~ ~
~
Closed SSAR These Imms use met in a safety-selssed or decemoe-analepsh posson of the systems. They are not included in she ogagens embles or syneem duettes peded for die symma,_,_ _ _ _
270 NRR/SPG 942 MTG4tt Wimmers/BRC Closed Action W
~
I
~M9T2iihMNEX/ AUX 75UUUINdfMR DIU CHVE HV AC SfSTEMS'~iEnsieEamd'wmer semperanse data for entrance and esa
~
)
h for sur handhas ammt (AHU) heemas and conhas coals for general area HVAC synessn espapment mum HVAC system, swachgear rtumm HVAC
(
syssani, MSIV conspensmont HVAC synessa, demameraliand waner dogmaner secen HVAC sysseen and _,. penetramon room HVAC sysseen in Table 9.4.2-2 througin 9.4 2-7. suspecovely 5
- Camarary en she ar==== smede in 12/13/94 sessung between Wmagh-* and N Plant Sy Benach, air and weser e dass for hemmag and mahay mils in air h==amt imuss is not to be ymvided en the SSAR. Commensat web past parana includsag, for **=mple she CE Sysseni 80+,this infunusuon is to Madat for SSAR inchision and is not macasesy to_sypet a gemarmi undanesehng of the syseme design.
l 27i NRR/SPIE 942 MTG-Of WinneraalRC Closed Actium W l
M9.4.2-7 (ANNEX / AUX.'BUltDINGS NON RADidAUTIVE HVAC SYSTEMS) Figusei>I4.2-2 of the SSAR shows thste hut waier unis heasers wah i
I
~
esempessame swaches servens the h espsysment sonen in the ammes I bushhag wah a pnnisson for she hut wases to be provkled (nun the VYS AdemonaNy,the h aspapmesma seosa HVAC subsysean also serves the RCC and ' ',
core cooling mon < lass IE penetrauma roarns and sencear any sweectgaar I and il sensus in the massbery heuttag. W==gb=a needs to reflect she above information wah as associated detasis in the hr=== 9.4.2.2.2_of she SSAR.
Clemed - SSAR en=arman 9.4.2.23 Itevision 7 imcludes a descnymon of the operamos of henaers in each of t
she _
, huslengs moeratoncave HVAC. ",
272 NMR/SPLB 942 MTG4)I Wimaus4tRC Closed Acuve
[M9'4[2-8(ANNEXIA NA ILDINGS NON-RADIO CHVEHVACSYSTF5SIFnPEbo2[00'M cutac feet per annuse (SCFM)is
[
~
h for hom espapsummt sonen HVAC syseman AHU senos it suppies 27.600 SCFM whste the meesta flow is only 25.200 SCFM and 1200 SCtht is l
leshammend toen the bushery suomi(Tame 9.4.2 3 of the SSAR shows 2-100 pescent capacity tuseery room eslumst fans, e g
~
9.4.2.2.13. Revision 7 i=rhad= a descnymen of the *T"r===s roosn HVAC Closed SSAR subsyneese wish its two 100% raparmy air handsms units and its two 100% capacity bassery roosn eshaust fans (one for each moe{lmas IE banery scom). For monnat operamon, one air headies unit and hash humery seem eshaust fans ese opensamg. See SSAR aderman 9.4.2.23 3, Revision 7.
i l
i Page: 2 Total Records 63
ArtOS Open Itesn Tracking Systema Desabases Execuelve Senunary pese: IW21/96 I
%etection:
[DSER Section) hite 9A** Soned by heat #
hean DSER h* ='
Tule/Desenyteen Resp (W)
NRC l
No Bramth
(>====
Type DeemtSessus F"fama" Status Stamss LeuerNo./
Dane l
273 NltR/SPLB 942 MTG4)I Wimeen/BRC Closed Acnon W M9 4 2-9 (ANNEX / AUX.'BUllDINGS NON RADIUACNVE'~HTVSfSTEMS5 Provide the na[ona1e foiseleenag the MSIV companmiese HVAC I
~
~
synnesn's only Sher wah an efEr==ry of 25 posoemt. Ilevise Talde 9.4 2-5 of the SSAR acx:o_ rdingly.
Clemed! 'SAR==de==5sub 9.4.2 describes the defemae-in4psh 6s=resa== of the as men /manharyWaimys_-_,..,_
_ ~ ' - - '
S
~-
~
% HVAC sy=====
Dese me no endsey sehnsd funceous. De MSIV compensment HVAC subnysessa has no defemme-in4pdi an=rma= As such, Jie Risers fut she MSIV companment AHtts ese seiscasd selsey for the pompeme of keepang the ranhen and hemmag coals cisant De speaEc selecean of Shers fue eius purpose is me sastant web imhsmery 4
peernce and ASSRAE % et she 1991HVAC Syssens and ligspassa Homensk, Chapest 25, Table 2.
274 NRR/SPl.3 942 MTG4)I Wanamn/BRC Closed Acteun W j
t M9 4.2-10 (ANNEX / AUX. BUILDINGS NON.RADIOACI1VE HVAC SYSTEMS) Table 9.4 2-7 of the SSAR for the valve /pipsag penetrahos roosn...
i HVAC system shows,2-l_00 percent AHU whd. Figine 9.4.2-3 allows a ss_agte_AHU. Reconcde the infiesence and revise the SS_A,R accordingly. _
Cisend - SSAR =sh=== 9 4.2.2.14. Revinson 7 senses that the valvedpereng peneensson ed HVAC l
[
embsynessa camasses of two 100 pesamt capacey aar hamusag ismas, De SSAR is now r==a*=s.____
j 275 NRR/SPLS 94.3 MTG4)I Wimmen/BPC Clumed Resolved M9.4.3-1 (RADIOLOGICAL.LY CONTROI J Fn AREA VENT 1LAT10N SYS1EM) i Ptownde a descnpanon of the unit bessers ramapnammsu in h1amm 9.4 32 of the t
SSAR and doen in Table 9 4.3-1. Aino provide Yammes H buniding imut henners ctosasacamom den in Table 3.2-3 af she SSAR.
l CInmed - SSAR subsection 9.4.3 2.2, Revenson 7,i=rhad== a descnymen of the esmet heneers in the radiologically commelled asua vensdemon sysema_ Dame hemass ase met in a safseyweimand or defence-in<iepeh pureos of she syne _s_e_n They ese meth in Table 9.4.3-1 or she system shana _,._
7 276 NKR/SPLB 94.3 MTG4)I Wimmen/BFC Closed Resolved iM9 4.3-2 (RADIOLOGICAL Y CONTROE I Fn AREA VENTib110N SYSTEM) Revise Section 9412 of the SSAR to include the (10_25_f_r,r_th__e u_mn _ba_ss._es.y,_a_s i=ar==d on Table 3.2-3.
s
, Closed - Hseudusua tar=== 9.4 Revenson 7 descnymous of eiscenc uma hesners include sefusence so s
UL 1025.
277 NRR/SPLH 9.4.3 MTG-OI Winnen/BPC Closed Acteun W g
M9 4 3-3 (RADIORDGICAl.LY CONTROI J FD AREA VENTILATION SYSTEM; Provale kwal einuent boidup tank exhaust una cunipuneet
_ds_ecngesen in tarenaa 9.4 3.2 of the SSAR and daea in Tables 9.4.3-1 and 9.41.wm_
e e+...
-+^-+w
[Ckimed - SSAR ednaaraan 9.4.3, Revenan 7, has been sevised en seAsce she d=amq a= of the efnuenthadA=p pe-g.mee.em-
=..wemme
~
,ummk *=h=== aar IEiPA fibers.
f 278 NRR/SPLB 9.43 MTG-OI Wimmen/BPC Cluned Chmed
{
M9 4 3-4 (RADIOLOGICALLY CONTROLLED AREA VENTILA110N SYSTEM) Provide efficiency and flow infunnassus data in Table 9 4-I of the
.SSAR fc_r _A_ABVS and, fuel % _ase_ ve=edsman syseem (RIAVS)Ingh-efEcsency pernch air (HEPA) hhers.
IChmed. DISCUSSED AT 12/1994 MEETING BETWEEN WES11NGHOUSE AND NRC PLANT SYSTEMS BR ANCll l
r i
6 L
i i
Page: 3 Total Reconds 63
_ _.. _.. _. _ _ _. _.. _. _. _ _ - -.. __. _ _..__.~. _
APtet Open Isen Tracking Syssesa Dataw Execative.W pese: IW21/96 betecdon:
IDSER Sectionj hke V4** Soned by hem #
i hem DSER Secteuel Tale /Descnpseum Resp (W)
NRC No tiranth a>=a==
Type Desmal h F"f="
Saanes Status tenerNo /
thee 279 NRR/SPIE 943 MTG-OI Wessen/BPC flamat Resolved M9 4.3-5 (RADIOLDGICA11Y CONTROI I Fn' AREA EENT1tlTK)NUYSTEM) Rev5 Table 9 4 3-I of she SSAR so'includeAwiipmeas dass for~
~
RCLVS supply ismas and sevise enh== s immes dass as two 100 gen:ent umsts, as sensed in Section 9.4.3 4 t
Closed - The sadhish M au'hsynaam is not safesy dAs sucbSAR U 9 4.3,
~
f
~~
Revesom 7, psovides a level of desad consesamme web shes classe6r=snam The sad chese lab w= mass==
syne is heed on two IM capacey apply as W umns.
20J NRR/SPLB 94.3 M1G4]I Wineen/BPC Closed Resolved i
M9 4 3'4'(R AD00tDGICA11I CONTROI i FD RE 'V5 T5'15NSn fLMi Revise IEchom ' I4 3$2 of the SSAR'so provule AHU outlet design 9
essayerumme for AABVS,19tAVS, and RG.VS and sense that she AHUs ase comerolled by sensperanse cosmuliers wish thest==m in the m.-:,- M 8%."PF.I.u.cm umam she speciGed.
d Cloemd - SSAR 9 4 3 as well as, the helmace of Section 9 4 kas been sevesed in Rhaon 7 to_ _ _ _ _ _ _ _
~'~_ _ ____ _ _ _
[
~
~
, ah the apply au _
a-a===s empesammes and,esapersnee cumerut.
f 2si NRIUSPt2 943 MTG-OI Winnen/BPC Clamed Acuum N t
t
. - - -M94.3-7 (RADIOLDGICALLY CoffTROR I Fn AREA VENTILATION SYSTEM) Revise Table 3.2 3 of the SSAR to psovide clamficanoe of all auger <==ra===== as shown in Fipse 9.4.3-I, anchuhms fise desapers Clemed. W emble only deals wish A.B.C.D. These smay be sosme D in VAS but also E.
~ ~ ~ _~ ~
~~ ~ _~~
k DISCUSSED AT 1/25/95 MEE11NG BEIWEEN WES11NGHOUSE AND NRC PLANT SYSTEMS BRANCH
[
Tahoe 3 2.3 282 NRR/SPt2 9.4.3 MTG4)I 3.2-34.andesee Cb Resolved 3 8lRAD00bF51CAiE.YMni~~FD AREA VENULATION SYSlifM) SieheMSc appiscable codes and standards for all VAS l
5
~
M9
- W i"
_E3 of g SSAR_ and_T, sete 3M ___ _, _ _ _ _ _ _ _ _. _ _ _ _. _.
Cimmed7SSAR'E 9 4.3, it'evneon 7, was sevened eIM~eluiM~M aM ~
'~
~~_
j
}
Table 3.2-3 has home seviend (Itev. 8) to property addsens the safesy-selseed -,
in the VAS. _ _ _
[
283 NRR/SPLB 9.4.3 MTG4)t Wissen/BPC Closed Resolved M9 4.3'9iRADIOLOGICA11Y CONiltOUN~AREUrFN5tTTK555 STEM) Pdclanfication of the musnber of fue dangers provided for
[
~
~
RCLVS and some apphcahte ape 00 SSAR h -- "
~
~
1he sud chem lab vesademos subsynaam is not saisty sehmed. As s[SUAR subsection 9 4[
~
Revissen 7, does not psovide a level of duned amt iactudes she esart number of fise dampers in the sub-sysamen. Fue damper panc-==a wig he communant with deemded durs seusing and in accordana wah she Hse ases showings inchsend in the SSAR.
284 NRR/SPLB 943 MTG4)t Wunen/BPC Closed Resolved n'e' 4515IRAD00EOGICAU M I FD AREA VIEI55750N'S STEM) Prdwentilanon desels and safe hydrogen level for the f
~
~
9 I"*"_8 '"I:**_Q._me to keep me asympment helow die puedecemuned tunn of by concentranon level A
(
Closed - Revinson 7 of the SSAR has included,is she rah pasagraph of naamarsaa= 9 4.3 2.31 a sesseinens thss w=ename== is adequase to mesmessa safe hydsegna in the gemenses radwasee area _,
t t
l t
[
t i,
Page: 4 Tosal Records 63 I
AP600 Open leen Tracking Syssent Database: Executive Samumary Date: 100,1196 helecties:
[DSER Sectionj hke 9.4*' Socied by hem #
l hem DSER Sectual Tale /Descnpaum Resp (W)
NRC No Branth Quension Type Detal Seasus Engmeer Status Status tener No /
Dese 255 NRRISPLB 946 MTGol landpen.D Closesi Acton W M9 4 6-1 (CONTAINMENT RECIRCULA'110N COOLI5G SESTEht)
'~
~
~'
~
W-f stases that the VCS confunus to she apphosMe celes and scandards as inmed in Sectsom 3.2 of the SSAR. However. Table 3.2-3 does not luit jthe_cisess6canumof VCS-Cloemd - No -
secuculasses coohng syseem componesas me Class A. B.C or D They ase not uncluded as she generalcodes and senadants discussnems of SSAR =ad=arama= 3.2. The appiscaMe ANSI / OACA samadasds ese hh===aad in SSAR h 9 4 6.2.2. Revision 7.
l 286 NRR/SPut 946 MTG01
- Winnen/EPC Closed Closed M9 4 6MCOOT INMENT REUIRCU~I1110N COOUdSYSTEM)~
~
~
'- ~
~~
We=magha==* mends to psevide (I) r=d=a======an imede each steam generaser.,
1(2) component detasis and comformamm wah ASME N509
[
1909 senadeses. '= chad =g Tame 4-2. ASME N510-1989 standants and RG l.140 for portable eshaust er Gluanon uma, and (3) updase SSAR TaNes 3.2-3 by psovstas t.lasesAcamen of compa==== desa 9 4 fri en last dessem parameters.9.4-1 for aar flow noe and efficiency data, and 9 4-2 for nuesmum b55BRANCHS
~
l Closed. DISCUSSFE 125/95 MEETING B ESUNCh0U NRC T
287 NRR/SPLB 946 MTG-Of Wissen/BPC Closed Resolved M9 4 6-3 (CONTAINMENT RECIRCULATION COOLING SYSTEM) fisme 9.4 61 of the SSAR. None 6 i=dar=a== shot the ducs sma==and selsef dampers wdl be locased mhen duct layout is fmahm:d The staff considers the i
sehef dassger W on VCS Figuse 9.4 6-1 of she SSAR to be a descnymacy Closed - None 4. fonually Note 6. of SSAR Figuse 9.4 6-1. Revision 7. has been changed to stase that the sehef denyer locamen is typical and that she Anal harmaa= will be W when duct layout is fashmed, _
255 NRR/SPLB 9.4.7 MTG-Of Wissen/BPC Closed Resolved M94 7-l (CONTAINMEN[ AIR FILTR AThbN SYSTEM)
What me the amtment summmer and wesser dessen tesupermanes for which the VFS supply ear subsyssems are deugned, specirsed temperature maintaned at AHUs(comarelled by _.
_ coussoBess wah thest====ars a the asyply duct), and tempemureganges mesmemmed in _ tim
- served arm?
Ckdb 7 of die SSAR inchades, in s=h=arama== 9.4.3.1.2 and 9 4.7.1.2, a seierence to the amtment ausammer and wisest dessyn immposammes in =ad==rs=== 2 and leses of the semperieuse ranges mannamed a che saved asses.,,.,
289 NRR/SPLB 94.7 MTG-OI landpen.D n=ad Accom N g
f M9 4.7-2 (CONTAINMENT AIR FILTRA110N SYSTEM) l T_ awe 3 2 3 of die SSAR does not Isentse VFS n==g====== class 6 canon Clemed -1EVFS conta===a= wese i=chadad in TeMe 32-2 escert for she a==*==h=g issue of the conect
[
- OId'aTers. The damper i sp=maa= is cowreed by Open heen 283.
WimmerABPC Chmed Resolved
[
290 NRR/SPLB 9.47 MTG-Of
~
~
k M9 4 7-3[ CONT INMENT UR FILTRATKE S5 STEM)
What me_sh_e specenc sypiscable codes and sammdents for the VFS egwpument in Secison 9 4.7 and Table 3 2-3 of the SSART. _ _.
Closed - SSAR h 9.4.7.2.2. Revision 7 i=rh=4s= appsopname gefusences to SSAR section 3 2. as well as, ademmfysms she specsAc appiscaMe codes and sammdads for r==an===sent er Skramos sygemyne
=
t Page: 5 Total Records-63
=_
AP600 Open Itein Tracking Syssesu Database: Executive Sununary Date: IW21/96 Selecties:
IDSER Section) like 9.4** Soned by item #
hem DSER Secoun/
Talr/Descnpuan Resp (W)
NRC No Branch h *==
Type Desaal Seasus Engmeer Status Status Irvier No /
Date 2*I
~ NRR/SPLB 947 MTGG Winners /BPC Closed Acuan W M9.4 7-4 (CONTAINMENT Alit F1LTRATION SYSTEM)
~
~
~ ~ ' -
~ ~ ~ ~
Wlut are the kicates of die aar =aM Staae wW dicy are gnmamd agianst _the q_genenned eximal n6 sales,
ClemedI ~desmpnan o'f de e~ar ims=he ple==es is provided in SSAR Revisaan 7.==h===343.32, first
~
~
~
~
paragraph ___,, ____. _
292 NRR/SPLB 948 MTGG 3.2-Wadgien Closed Action W
'M9 4.8-l (RADWAS1E BUlti)ING HV C SYS1EM)
~
~ ~ ~
~ ~
~ ~ ~ '
~
~
vise Table 3 2-3 of the SSAR for vacuum selsef syneem (VRS) components inthDmg indissed system dampers and high and low efficiency hhers.
~~
~
Cioned - The lia~dwanse BelkUV5FSysaem (viiEy~n'em ikEmwEve cmqA the areItUsed as APWO Eqtupment Cess'A B[C or DS s
Only Class A, B,C and D -
and valves are included on Table 3.2-3; The VRS is not included in Table 3_2-3_.
293 NRR/SPLB 948 MiGG Winners /BRC Ooned Action N
~ i4 8 2 (RADNASTE BUILDINGiU FSESTEM)1.ist separameththe VRS cfficiency data"fw all V'R'S Iugh a'd low efficiency fihers uiTable 93 8 M
~7~
~
~
n I and sliow all t_he_m_ om_,F_ igure 9 4 8-l acconhagly Closed - fileEdata lor all Risers is provided as SSAR Revision 7 Tatie 938-l and Rgure54 8'I-
~
'~
~~
~
l NRC-Acmos N - sanff seviewing _
294 NRR/SitB 9.48 MTG G Winners /BRC Closed Acuan W M9 4 Bl(RADWASTE BUni) LNG HVAC SYST55 Revise EsioeWfoESSARE provide nuluAy m'le ' data for VRS components concervung thest design,commmasca and emanag i
295 NRR/SPLB 9.45 MTG-OI Wineers/BRC Closed Closed
[M9 4 B[(R ADWASTE BUILDING HVAC SYS1EM) Provide Esa for niesis [womenilocker room exhauss fans in T l
[
I ItadM M anangemesis has been sevisedThtunidag no longer mitaan[lahs. _In[rwrn gxhaust fans are mi kmger required l M
~
~
t 2%
NRR/SPLB 9.48 MTGG Wimeen/BRC Cluned Actum W NTD-NRC-95-4464
[M9'4 S[5 (RADW AS1E BU'IdEUdHVAC SYSTEM) Updene Secsson 9 4.8'o]f die S R to prov'ide cddata for the system compone l
~
i Closed - No radwanee Inubhag HVAC mohng system cosuponent are Class A, B. C or D. The applicable ANSI /AMCA ade and sammdases ase A,a-amad in suh= aman 9 4.8.21_ __ _, __ _ _ __
297 NRR/SPLB 948 MTGG Wimmers/BRC Closed Action W NTD-NRC-95-4464 M9 4 85RADWASTE Bull 5NdEEIC SYSTEM) What are the anEsummeiandEineer' design L.[ [ for which the VXS subsystems are
~
~
pesagned
=,_;, _ _ _ _ _.
[ Closed - N specine desage room sempermanes and a refesusice to she arnbeena L.r.
q are inchaded in SSA_R subsection 9 4 8 l_, Revismni 7.
l 298 NRR/SPLB 9.4.9 MTGG Winsers/SCS Closed Acuve
~
~
M9 4 9-I (TURBINE Bull. DING VE 11LAT10N SY'STEE)~5 9 4 9 of die SSAR descnbes the system bnefly Provide desagn parameters for j
t.sysicm components or papeng,insanamentation diagram, and classancauan of the VTS sysaem and cumponents an Table 3 2-3 Cloned - The marbene budding vensdesion system serves no safety - setened functions and has no safety design basas. Nome of its componeess are classened a.B.Cor D. The syseem and component descngwian provided in SSAR =d==mam 9.4 9. Revision 7, pmvides aufRcsamt deemil for a desernumanon of the system's eficca on plant safety.
Page: 6 Total Records 63
. _. _ _ _ _ _ _ _ _ _ _ ___.________.______________________________._____________________________.______.___________________________.________________j
.__._m.
i Arte0 Open Iteen Tracking Syssesa Daembage: Executive Sumunary Date: te/2U96 helectime.
(DSER Sectionl litte 9.4* Sorted by leem #
I hem DSER Secoue/
Tale /Descnpsun Resp (W)
NRC No Branch rW=
Type Desant Seamus W
Seus Status tener No /
Due i
299 NRIt/SPLS 9410 MiGG Wussen/BRC Closed Resolved M9 410-l (DIESELGENERATORilUll MNG HVAUSESNM PriEule the specine AHU oinlet tempenEue maatanned and saase'that AHUs are
~
~
q by cauallers web ther senmus in the_s_syply duct to mamma the _mr apply at thes spioned_sempensum
,__n
[
'Ch'ine[.~The ehe~A and desip sense gesaperususes ase included in SSAR subsecison 9.4.10.I
(
T ***?.:.
- ~
300 NRR/SPLE 9410 MTG4)I Winnen/BRC Oceed Acanon W j
M9 4$i0'2 (DIESEL GENEiR T0R BUILDINdHVAC SYSTEM) To M'the eteent InfSamformanEwsah GDC 'l7, as~i:Mio ensunng f
~~
~
paper W of she sammesy nm=me ac elecanc power syseem,W- - f ' should conGnn that the VZS saaney eahaust vensdation systems me equipped wnh she air fibers and thus she bonsver lar=mana for cuaside air inashe confonn wah the gh of NUREGICR4660 [6.I m (20 lb) above grade]
[
l eo camasel she these and ashee, _-
Revue Rgime 10.4.10-1 of the SSAR acantungly
~
Closed - As i=ar=aad in the *Are00 C,
- " sammensent for GDC 17 in SSAR haasi 3 l l,' Re'vW7,, _, _ _ _ _ _
E che absent genereers ase act pan of she safety-seissed power sounes for apt 00. As such. NUREGICRab60 i
ased not apply to the deep of the themel seassumers, the diesel generusor t==bhat or the diesel generaser bemidag HVAC. However, since NURfiGCR-0MO does psovute pnadent design smad=== she diesel generasar 8==aang hessung and h synnass does not congsly as fotoes:The aar intake tothe service module, j
which huumes he unspor etacerical agmysmaatW with else DG umst,is locaned as bagh up on she biedding 88 precacal i
tw==a. er to the sesvup=aade as thesed to pewet she speed at dust and aan amo ekorical espapment t
In mE apenmag modes, aar supphed to elecencal e asses is L%esed.
Etscencal egepamme c=a===== me specsAnd to be thest aght.
Air povedad to the eague seem is Ada-d and is geham ihmugh insakes enou *:, high as in the tankhag as precacal ch ser is imken ham the===daars van a h aar ca.===, mot hem the engine scom.
l The sammesy e=h=== v==an==a= sadisysnem openses only when the ehemels me neuung and supphes v==hashna only to lhe empne sensus. The supply of Ahased air no eiscencal espapment is umanected by
[
operumm of she semesy enkmut venimos messysant Wueen/BRC Oosed Actice W l
301 NRR/SPLB 9.4 10 MTG4)I
~
f M9.4.li3'(DIESEL GENERITolt BUILDINdildSEMEvahasse the equepment operabalay for die equipment locmed inside DG area capueed
~
_88130 F whale DG in opersasom
'Eh no be lar=a d in the diesel gameruser inmidung wiu be specified no operuse in an ambient of 130 F. A scess tesaperamme of 130 F is typecal and =r=rs=ha, for ahesel engines and gemensors. The of 130 F h is r======= wish URD sequeammesas. The 130 F sequuement is not esplaculy sensed in she SSAR har===* me egapsumas inc=ame in the diesel geommaar bushhag is safety selmed.
l 3.2-3/ Wieners Closed Acteam W
~302 NRR/SPLA 9.4.11 MTG4)I 6
[
M9.4.11-1 (IEALTH PHYSICS AND HOT M ACHINE SHOP HVAC SYSTEM) Updme Table 3.2 3 of the SSAR for VHS curmpuments aciuding umbened syneem damipess and het machmae shop threon unit subsyseese
_,,' ' ' ' ~ '
' ~
~
lClemed. Itevision of SSAR Table 3.2-3 inchada emiety-seiened isens in the VHS l
Winessa/BRC Ckmed Closed 303 NRR/SPLB 9.4.11 MTG4)I M9 4ilT(55AL'TH'PH SICS'AND HOT MACHINE SHOP HVAC SYSTEM) Provide the specahed AHU uselet semperature and same that AHUs consround by assapesmae comentiers wish their samsons is the supply duct to momena the air supply at slus p_6ed tesmerunse
~
l j
[ Closed DISCUSSED AT 12/13/94 MEETING BiffWEEN WES11NGHOUSE AND NRC PLANT
~
t l
Page. 7 Total Records 63 e
f
f APtee Open leen Tracking Systems Database: Executive Seinennary ORw: :ss21/96 betecties:
lDSER Section) hite 9A** Soned by hem #
i leem DSER h *='
Tale /Descnpason Resp (W)
NRC No Breach th=
Type Detaal Semeens Engmeer Sammas Status teteer No. /
Dese 304 NRR/SPLB 9 4 II MiGG Wsmeen/BRC Closed Achom W i
M9 4 Il-3 (HEALTH PHYSICS AND HOT MACHINE SHOP HVAC SYSTEM) Clanfy the number of radianum monssors wnh assened MCR high
[
med high-high almnus med museher of Alwamos unit fur the hot p=*=* shop are provided med sevise effected SSAR secteos. Egure, table, med drawmig.
' '. AI- _
Closed - These es a sangle smaama= -r===
in the exhause of the hemhh physics med hos macheme shop HVAC syssem to the pimme vest sanck_ This is i=ar===I in SSAR =h 9.4.11.2 I, Revision 7 med in h II.5, Revenson 6.
305 NRR/SPLB 9411 mig-OE Wmeers/BRC Comed Acnon W M9 4.11-4 (HEALTH PHYSICS AND HOT MACHINE SHOP HYAC SYSiliM) Revise Table 9 4 Il-1. Shees 2 of 2 to sinne "fiher requirements.* not- - - ~ - - - -
"basmag coal sequeememes." Also, she enkle needs to het the conect sammber of HEPA Steers for VHS or ape 00 SSAR secnom med fagine need to be revised.
I nomsdagly Clemed -The hemhh physecs med has an==+a=* shop HVAC syneem is not safety selsted. As such, SSAR
=d=ar=== 9.4.3. Revissom 7, psovides a level of desad ahme does act include the enact number of hisers L
em the systemt. The syneem does amt i=r+=d 15!PA nimess.
j 1801 NRit/SPLB 9411 DSERG Wmeers riaaat Acnon N l Tie ~sElhas adyes' she --. ', of she design of the nuclew esimmd mouradiancave venedanson system.
j i
~
Cloemd - SSAR 9.41 Revision 7.e4=*a p==eny open isens 261 time 264. This compleses she W- --f i
subsuments sequesd for NRC seview of the mesclear isimmf somrmar=raive v-ad=== syseem.
1804 NRIt/SPl2 9.42-1 DSER G Wumers Closed Acuve t
~, of the desidshe mEMN HUAC syseem in[tlie mm ex/mumilpuy tunkhngs.
]
[
~
~~
{ Tie senn has mut[yet deeermanad5-~
[hV [ ' 'has psodmilinfos==n== fonenNy sar=*=a-a. See Open leeses 265 sluough 2UI ~ ~
~
~~ _l f
~
1105 NRR/SPLB 9.4.3-1 DSER-OI Wumers/BPC/WEC Closed Acuan N NTD-NkC-95-4464 I
lThe senn has not yet desenmaned the --
htEdesho~fthe'
[=H arNvennlatson system l
y
[CEsod. SSAR Re73'A==d===
no sessmag open issues 273 to 284_
l
~
Winners /WEC Closed Aceve f
l106 NRIt/SPLB 945-1 DSER-OI
, of venniemen syneens for R1NM~s'yEms.[ _ [_ _ _
has ma'h[e Mihe -
~l
~
l15e.. _ - _. _.. _ _. _ _.
r Closed - SSAR h== 9 4. Revision 7. N emfas===ma= on the pensons of the anr " '
_ hemung.
<= hap med va-ad=ma= sysessus ehnt perfons safety-selseed and defemme-smalepth fiancooms: These is no anose infonummem =rr====8 by MRC for "vand==r-systems for RTNSS :. -
syssems." These is no l
t
" Safesy Femanes Vemminaca Syseems." trarde seipsenes for =dama==8 sofonnesson from NRC ws5 he comed by fumme open immes.
I107 NRR/SPLB 946-1 DSER G Womeers/WEC/INI Cimed Action W
. -. _ - -. -. -. - -. _', of the design of the wasament secirculasmas cochag sy] esa l
samffy not yes detesmened the --
Closed - With the issue of SSAR Secison 9.4. Revision 7, Open Isess numbers 285,286,287 ed 1766 are
- ecirculanom can.=e These ese no anose specs 6c sequeses hose NRC for infos==== cm the -
r mesme syneen.
l t
Pdge. 8 Total Records 63
AP600 Open Iseen Tracking Systeal Database: Executive 5ssmemmary Date: 10/21/96 Selection-
[DSER Section] hke V4** Sotted by item G hem DSER Sccison/
Tet h npoon Re5P (W)
NRC No Esanth Quesnan Type Detail Sensus Enguieer Status Status letter No /
Due I103 NMR/SPLB 947-8 DSER G WuserWBPC Ooerd Actsun W NTD-NRC-95-4464 lThe sealf has nos yet denenanned she'--- [ in[f the deUgn citlE
- Esar filtrusi$
~
~ [_
_[~
l Ooned - Wuh the issue of SSAR Secuan 9.4, Revision 7. Open leesu numbers 288,289. 290 and 291 are_ _ _ _..
closed. These are no more specific sequests fross NRC for infornuanon on the -
^ air fikration symen i109 NRR/SPLB 948-l DSER-Of Wumers Closed Action W
{1he staff has notydesennamed she Sof Uselesign uf ErdmEbus,lAng HVAC syseem.
{
Cl$edMi$u[o~f SSIR Revision 8. whsch inchades Table 3.2-3, cornpleses sutunatal of all infM requessed by the NIIC'for the rEw of'the radwasee temkhag HVAC. No add =-.a NRC requesas for infonnamon are - -
1Ito NRR/SPLB 94.9-l DSEF Ot Wiseers/SCS Closed Actson W (line semiiEs~ mot ye[dessuun$id she -
5dde des $gn the Ubemidag ventila:Esystem
[
]
Oceed -The susbane taaldmg wed=a= syssens has no safetyM or deframe-in4teph functions
~
or-See Open inesa 298 for sunse eksenis. There ase no other rap==* for infonnamon till NRR/SPLB 9 4.10-1 DSER-Of Weneers/BRC f1=M Action W
[1he staff has nos yet desenuamed the --
-y of the desagn of the diesel generator budding heating and venalmeon system Closed - Wah she issue of SSAR Sacnon 9.4, Revision 7. Open mese numbers 299,300 and 301 are cloned.
Ther ase no mose speca6c sequessa fuosa NRC for sofonmanon om the deesel generanor bankhas b=nar and w=adama= symen.
1842 NRR/SPLB 94.111 DSER G Womers Closed Action W
[Ijasaff has not yet deserummed'she -
[of Edesign 5 the hmiehi ys~ib and h[nE:b thop HV AC system.,
f
~
_~
~
~
~
IClassEAM s=M Efonmanom has been provided to the NRC.
l 1766 NRR/SPLJB 946 MTG-Of Landgren Closed Acuan N M94 64iCONTAINMENfR5ditCFLA110A2OOliSG S 511iM)~
~ ' ~ ~ ~ ~
Samff so ennenanne any =dama==I meeds for Table 3.2.3 A bases (aeher than what has aheady been identined in 283)
AC110N RtOM I/25t95 MEETING BE1 WEEN WESTINGHOUSE AND NRC PLANT SYSTEMS BR_ANCH
[n=ad - Wem@e has complened m sulusasals so sigport staff seview. _ _
)
17&7 NRR/SPLB 94.7 MTG-Ol Landyte s'
1 Acuan W M9 4.7-5 (CONTAINMENT AIR FILTRATION SYSTEM)
RAI 410.237. Ref C mot provided under seferences. %=M be Tatde I.l-l.
ACHON PROM 1125/95, MEETING BETWEEN WESTINGHOUSE AND NRC PLANT SYSTEMS BR ANCH l Closed - SSAR Secania17 no longer has a refesence to Reference C. Tabic l.7-2 is tE hst of'AP600'sysaems
^
l
^
~
Wiesers/BPC Oused Acnon W 2890
, NRIUSPLB 94.1 TEL-Ol
~'
I lm 5ISIR Section 915 address VBS hieranon uset confonnance to GSI B-365 ASME N 509 l989 and ASME N 510-1989 and a&lress VHS ascs and hamany =a-d* of snaum connel roose confonannoe to GSI B-66, ASME N 509-1989, and ASME N 5141989. Evalume whether CUL teems must be
=..
3---
Closed Am=sar. web esher seasons and systems psensused for ape 00 Design Certificanon in the SSAR, no COL inese will be added to ensuse-
= wish codes and samaderds idemnfied in the SSAR on a system-by-syneese hans. k is assumed that, seem slane codes and samadeds are called out in the DCD follownag Desage Certsfuman they are followed in enter to massessa
= wa_h_ the Rule _ _
Page. 9 Total Records: 63
a,_
AP600 Open Items Tracking Systega Databeoe: Executive Sa=== mary page: le/m96 Sefacties:
[DSER Section] like 9.4** Sorted by leem #
leem DSER Secmont Tale /Descnpetum Resp (W)
NRC No Branch Quemoon Type Deumi Stansa Engmer Stasus Seasus knerNo /
Due 2897 NRR/SPLS 94i TEL-OI Womeen/BPC ri-8 Acnon W Addsess defesa em depsh cntena for the VBS. These cneena inada - ' -.-
-, power supply, envuummensal quehficanon for sevese =m4 s, hazard y
prosecmon (fue, nood assurmi phenomena, esc _ L_apsahey assurme, avad=8= ley, and admmuerusive controism
' Chimed 75S'AR a= ream 9 4. I, Revenson 7, includes sofos-saan addreaming she defence i[depeh cneena and
~~~
densyn of the e postoms of the nuclear isimed mammaa=reve ve=samaan syntesn (VBS). For example, as sessed in pd==reaa 9 4.1.1.1, portoms of the syssess ase d===g=ad consamceed and teseed in accesdance wah ASME N509 and ASME N510. Other considmamens me addressed in subsyseem descnynons. For example, seemadmacy for the umana commel sensa / ad==c=8 suppost cemeer HVAC sidssyneem is a=saa=ad as 9.4.1.2.3.1. Gamesel cneena and our puded appsonch no d Ea= in derah funcmons throughoui che desige ase cosassmed am she appsopnase==== of the $$AR. For e===mpae apsahey assurance sequerements see comensmed in hpnar 17, admuasswamve commels in thpaar 13 and a,=en.hainy in (hp,,16_ __
i r
3085 NRR/SPUB 9.4 RAIG Wassers Closed Action W NSD-NRC-964727 410.276 SSAR Seceam 9.4.1. Nuclear Island Naaradiancave Va=ad=ma= System _ _ _ - _. _. _ _.
Table 9.4.1-1 of she SSAR idensenes======d in-leakages shsough the Mme Control Room (MCR) access doors and the MCR/Iechnical Support Cemeer (TSC) aqunpaneet shectwork (operamag) and out leakages through the MCR samcsure and the through MCR/ISC Heating Venulasson and Air C% (HVAC)asympament and ductwork (operanas). Womanghnume should suae thss dunng ahmonmal openmon wuh high aartiorme radioactivsy
[
==a==== the MCR/ISC HVAC subsyssess can lunut she doses to the casesol sucum operators to General Design Cneena (GDC) 19 dose imuts given the amammed in-and aus-leakages
~"
~~
hinead maap==== psweeded by NSD NRC-96-4727.
3086 NRR/SPUB v4 RAl4)I 3.2-3/Wusers Clused Acuum W NSD-NRC%4817 410 277---.Waaa=gha=== ahamad sevue SSAR text and table as follows:
Itevise SSAR TsNe 3.2-3 and SSAR test and sable in hrea= 9 4.2 to inchade component and Code data for the secam humsdiGer,inot maser uan a.
bassars, and aleiancel sehest cods.
- b. Revise SSAR Table 3.2-3 and SSAR seat and saides in kraa= 9 4.3 to include component and Code data for steam humuhner, lum water umt heaters,
-and elocascal seheat coal.
._._1 n _
u_
Closed - lefonessem on the safuey-selmeed and defense-inepeh pensons of she Ammez/Anadeary Bustdess NoraJioactive HVAC system is included in Tame 3.2-3.
Closed - la sesponse so lemer NSD-NRC-964817 deced Sept. 10,1996 3C37 NRR/SPLB 9.4 RAIG Wimmers.
Closed Actace W NSD-NRC-96-4727
~
41527s SSAR'aecE9.4.g. Itadweste Buddag HVAC System
~ ~~
t The W -.
ah==dd sense in Section 9.4.s of she SSAR thus (I) fire dampers me provided a duct penetranons through fue bemers to manutasm the fue sesentance ranags of she bemers and meest the desage and ime=n.ana= sequaesments of UL-555 (1990),(2) VRS (radwasee bankhag venidation system) smahde Ahrataos units,inchuhmg IEPA filters. - ' ' ; the guidana of RG I 140. Posanons C.I and C.2,(3) the supply and exhause an syssem f
ductwask is desegmsd,labncased and insenued to confona with the w of Shees Metal and Air Condusoming Contractors National Associanon (SMACNA) standeds, and (4) shesisag of ew and persommel during normal plant opension is -
with radianon sources in the f
p viciassy of she VRS = tap====s
,__ _ _ _ _ _,,_ ___ _ ~
~
{Chiul n==pa=== provided by NSD NRC-964727.
l
~
[
.t F
k Page; 10 Total Records 63
AP600 Open leesa Tracking Syssesa Database: Executive Santmas7 Date: IW21/96 Selecties:
[DSER Secuon)like 9.4* Soned by hem #
Im DSER Sectumi/
Tele /Desenpron Resp (W)
NRC No Bramh Qucanon Type Desmi Sunus Eagwer Susus Susus im No /
Dane 3482
~ NRR/SPl_B 94 RAl4)I Butler Closed Action W NSD-NRC-96-4850 RAls 4I0 296 - NRC lener 8/15/1996 Some SSAR figues are not legible, for example: Figures 9.4.1-I,9 4 2-1.9 43-1.9 441,10 3 2-1, and 11.4-I.
. _ _ ;f is W to revue the SSAR ngues to be legible _ _ _
W (Ckned 3*='r pNMU _
leser NSD-NRC 58'5blan$d 10/17/96.. _, _ _ _
['
[___, _ _ _ _ _ _ _]'))
b k
l L
Page-II Total Records: 63
FnX to Diane Jackson at NRC This is to amplify our " doneness" for section 3.9 of the SSAR and DSER.
Revision 9 (August; 1996) of the SSAR provided our last planned revision of section 3.9 to reflect design changes. This chapter will be changed only if an error is found or if required by NRC. The Open Item tracking system indicates that 97 of the 111 items associated with section 3.9 show "(W) Status" of
" Closed". Of the remaining 14 items 5 are awaiting Revision 10 of the SSAR and are tracked as " Resolved, SSARREV" items. Two items are associated l
with the Chapter 14 and are being tracked with other Chapter 14 related open items. The remaining 7 items require dialog with NRC and closure. The
"(NRC) Status" for the 111 items associated with section 3.9 shows 66 that are
" Resolved" or " Closed." Westinghouse knows of no further submittal requirements for 38 of the section 3.9 items which do not indicate " Resolved" or " Closed." As indicated on the schedule provided to NRC on October 15, 1996, it is our intent to supply NRC with all information necessary for it to complete the section 3.9 portion of the FSER by December 12,1996. We request that the NRC understand that Westinghouse is not expecting to submit any additional revisions or information for section 3.9 except for the 7 outstanding items identified above. We should have a teleconference definitively scheduled to resolve any remaining NRC concern.
Jim Winters October 17, 1996 4
l
i l
i j
FAX COVER SHEET l W8Stingh00S8 D
1 4
l RECIPIENT INFORMATION SENDER INFORMATION 4
$ lx/rNTf/t>
DATE:
brooctL //
/ 99[#
NAMF.:
TO:
h, Ade' tar /oq LOCATION:
ENERGY CENTER - EAST PHONE:
FACSIMILE:
PHONE:
0ffice: '//2-I 7 d-I290 COMPANY:
Facsimile:
win:
284-4887 l
() JA[A_C.
outside: (412)374-4887 LO. CATION:
l 4
\\
Cove.r + Pages 1+[
3 i
The following pages are being seni from the Westinghouse Energy Center, East Tower, Monroeville, l
PA. If any problems occur during this transmission, please caE:
j WIN: 284-5125 (Jenice) or Outside: (412)374-5125.
COMMENTS:
TO SkTWP/ W ]I*T(W ouA Y73 Tl.5 o$ B 4 4c 5 rd*T T acd. ~[r t s DRAFT nao usuu. nto r BV~ Pfav<'xs Fenneu/ ta %-
~
we AIAC l =-ca TPsc Otw ca n s ou a es i n ia c w stoa T%t T ett uanc i
(~e~ ttmttu/ i%@ P AectD rs 50." E JNil] Ft c40^f. CA u. i f y/da W uir Oa GDe An.
n
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Secondary Coolant System Leakaga 3.7.8 3.7 PLANT SYSTEMS 3.7.8 Secondary Coolant System Leakage LC0 3.7.8
'The secondary coolant system pressure boundary leakage into containment shall not exceed 5.0 gpm.
APPLICABILITY:
MODES 1, 2, 3, and 4 with reactor coolant system (RCS) not cooled by normal residual heat removal system (RNS).
ACTIONS CONDITION REQUIRED ACTION CONPLETION TINE A.. Secondary coolant A.1 Reduce leakage to within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> system pressure limit.
boundar'y leakage into containment sump not within limit.
.B. Required Action and B.1 8e in MODE 3.
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> associated Completion Time not met.
AND B.2 Be in MODE 4 with RCS 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> cooling provided by the RNS.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 Verify unidentified leakage into the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> containment sump is less than limit.
i
@ AP600 3.7-1 Draft:
September 30, 1996 m Q304w W-101NG
Secondary Coolant System Leakage 3.7.8 B.3.7 PLANT SYSTEMS B 3.7.8 Secondary Coolant System Leakage BASES BACKGROUND Detection of leaks in steam generator (SG) secondary side piping and nozzles is necessary to ensure that the leak-before-break (LBB) pipe service conditions are met for the lines to which LBB applies.
These conditions apply only to the main steam and main feedwater lines which are inside containment.
By limiting operation following the detection of leaks associated with the postulated. leakage flaw (crack) size, pipe rupture is precluded.
Flaws smaller than the critical size normally only increase in size due to pressure i
or temperature transient cycles.
Flaws larger than the critical size are considered unstable and may increase in size due to a constant applied stress (i.e., pressure load).
Because pipe rupture is precluded, the equipment qualification design bases for equipment in the LBB pipe local area do not include conditions associated with pipe rupture. The primary advantage of this approach is that for, these lines, the pipe restraints are not designed to withstand forces and displacements associated with a pipe rupture (Ref. 1).
~
j This design approach requires that small pressure boundary leaks be detected and if not isolatable, action be taken to shutdown the plant.
Detection of leaks in excess of 0.5 gpa is necessary to preclude pipe rupture in MODES 1 through 4
.due to a safe shutdown earthquake (SSE). Therefore, pressure boundary leaks through cracks must be detected and action taken to isolate the leakage.
Leakage past gaskets and seals are not associated with conditions leading to pipe rupture and, therefore, are not considered to be pressure boundary leakage.
The same leak detection instrumentation, required to be OPERABLE by LCO 3.4.10, "RCS Leakage Detection Instrumentation," in MODES 1 through 4 for detection of reactor coolant system (RCS) leakage, is used for detection of secondary coolant system leakage in containment.
Evaluation of potential secondary coolant system leaks in excess of 5.0 gpm is required.
Additional instrumentation is available for evaluation of these leaks and is discussed in SSAR Section 5.2.5 (Ref. 2).
(continued) h AP600 B 3.7-1 Draft-September 30, 1996 m 430dw wof101 me
Secondary Coolant System Leakage 3.7.8 l
l BASES (continued) i APPLICABLE The limit on leakage ensures that conditions leading to pipe i
SAFETY ANALYSES rupture are detected and the event is avoided, thus reducing the probability of a secondary coolant system break inside containment.
Early detection of leakage permits operators i
to take action to limit the likelihood and consequences of l
postulated events.
Piping established by analysis to be LBB will not rupture, provided the critical flaw size is not exceeded. The leakage limit is conservatively selected to correspond to a leakage crack size that is detectable, structurally stable under seismic loads, and permits sufficient time for operator corrective action to preclude pipe rupture. The size of the leakage crack is established such that the
. expected leakage is 10 times the minimum leak detection capability for that location (Ref.1).
Limiting pressure boundary leaks in LBB piping permits elimination of local dynamic effects of postulated pipe ruptures from the equipment qualification design bases for essential structures, systems and components.
Local dynamic effects include; pipe whip, jet impingement, missiles, local,
pressurizations, pipe break reaction forces, and decompression waves in the intact portions of that piping or communication piping.
Although LBB piping will not rupture, provided leakage limits are met, global effects of steam generator secondary j
side piping line breaks are addressed in safety analyses, consistent with Draft Standard Review Plan 3.6.3 (Ref. 3)
Although'the secondary coolant system leakage limit is not required by any of the criteria of the NRC Policy Statement, this specification has been included in Technical Specifications in accordance with NRC direction (Ref. 4).
LCO This LCO ensures that the leakage from steam generator secondary side LBB lines inside containment associated with i
the critical crack size assumed in the LBB analysis is not exceeded. This leakage limit precludes LBB pipe rupture, thus preserving the equipment qualification design basis.
(continued) i h AP600 B 3.7-2 Draft:
September 30, 1996 m k330ew wwof-101M
.e
Secondary Coolant Systen Leakage 3.7.8 BASES (continued)
SURVEILLANCE SR 3.7.8.1 REQUIREMENTS The unidentified leakage must be verified to be less than the LCO limit each 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Leakage past gaskets and seals shall not be classified as pressure boundary leakage.
The containment sump level monitor required to be OPERABLE by LC0 3.4.10, "RCS Leakage Detection Instrumentation," in MODES 1 through 4 continuously monitors leakage collected in the sump and will detect and alarm flow rate increases of 5.0 gpm. The LC0 3.4.10 instrumentation along with other available instrumentation provides the capability to establisie the leak source (Ref. 2).
REFERENCES 1.
AP600 SSAR, Section 3.6 " Protection Against the Dynamic Effects Associated with the Postulated Rupture of Piping".
2.
AP600 SSAR, Section 5.2.5 " Detection of Leakage Through Reactor Coolant Pressure Boundary".
3.
Standard Review Plan, Draft Section 3.6.3, " Leak Before.
Break Evaluation Procedures" FR32626, 8/28/87.
4.
NRC letter, Diane T. Jackson to Westinghouse (Nicholas J. Liparulo), dated September 5,1996, " Staff Update to Draft Safety Evaluation Report (DSER) Open Items (OIs) Regarding the Westinghouse AP600 Advan'ced Reactor Design," Open Item #365.
@ P600 A
B 3.7-4 Draft:
eptember 30, 1996 m t1304w wwW 101 me d
j Secondary Coolant System Leakage 3.7.8 j
f BASES (continued) i i
APPLICABILITY In MODES 1, 2,3, and 4, when the SG is being used for RCS heat removal, the secondary system pressure and temperature conditions are capable of causing pressure boundary growth of a critical size crack which in combination with an SSE could result in pipe rupture.
i i
The secondary system temperature and pressure conditions in MODES 4, 5, and 6, with RCS cooling provided by the normal residual heat removal system (RNS), are not sufficient to propagate a leakage crack. Additionally, the local dynamic effects of a postulated pipe rupture in MODES 4, 5, and 6, with RNS cooling, are insignificant from the standpoint of equipment qualification design bases for essential structures, systems, and components. Therefore, leakage monitoring is not required in MODES 4, 5, and 6, with RCS a
4 cooling provided by the RNS.
i ACTIONS A.1 With secondary coolant system pressure boundary leakage into
- containment in excess of the LCO limit, action must be taken.
to reduce the leakage within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. This Completion Time is based on predicted crack growth rate and allows time to isolate the leak or take other appropriate action to reduce the leak rate.
This action is necessary to prevent further deterioration of the secondary coolant system pressure boundary.
B.1 With steam generator secondary side leakage in excess of the limit, the unit is in a condition potentially outside the LBB analysis. Therefore, the unit must be placed in MODE 4 with RCS cooling provided by the RNS, where the probability and consequences of crack growth in the secondary coolant system pressure boundary inside containment are minimized.
To achieve this status, the plant must be placed in at least MODE 3 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and in MODE 4, with RCS cooling provided by the RNS, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The allowed Completion Times are reasonable, based on operating experience, to reach the required conditions from full power, in an orderly manner, and without challenging plant systems.
(continued)
/
h AP600 B 3.7-3 Draft:
September 30, 1996 m J30ew wsf-101eBS
i i
b mcq <[ phsj% Tdeem d&. kJRt, : s
.)
/
4 NRC's October 10,1996 Conunents on MAAP4 and T/H Uncertainty RAI Responses (nNAc i) c i
October 15 Telecon Discussion RAI s Solgect 492.15 Provide a quanutative eumane of what Westinghouse
" Ample margin" is' hated on expecting calculated PCfs to be in the range canaders "aniple margin" to the PCT lindt as discussed of 1200* to 1800*F, which is below the tesnperature of significant zirc oxulahna l
in this response i
Regarding the response to how margins will be reflected Westinghouse will address the impact on the Baseline PRA, as well as the i
in the overall baseline PRA, Westinghnuw has indemed Focused PRA, if the MAAP4 benchamarkang idenhfies iunes that switch that scenanos which have less than 1% impact on the scenanos from successful core cocling to failwe. 'Ibe reference to the focused PRA will not be canadened. Akhough this snay leuer that discusses the T/H uazrtaanty resoluuon process is to indeme i
l be justifiable for the focused PRA, scenanos that are less anat that process is a subset of (it will " supplement") the =<*<unens; the than 1% of the focused PRA frequencies are of the sanne T/H uncertainty resolutaan is not the entirety of the assessment mennoned enter of magniende as the baselane PRA and would in the RAI response.
appear to potennally impact the basehne results. Please provide addisonal infonnamon on ibis.
492.21 Why is the core heat sansfer not ranked "high" or Discussion centered on the predicted PCT dependency on the two-phase "imponant" in the P1RT7 'Ibe staff is amore interessed in anxture level. Westinghouse agreed to search through our existang LOCA the heat transfer during the transison frans covered to docusmentauon to find support for position that the ranking of the two-l uncovered and the return to covered.
phase mixture level is sufficient, and the effect of the core heat transfer on 1
PCT is sanali.
i 492.23
'Ihe staff's question regarding this RAI response is how The issue is why the CMT nemperature is not ranked as high importance l
one differenuates between abe impostance of one source on the PIRT, while the IRWST temperature is. The CMT operates at high of ECC injecuan and anoeber in tenns of its PIRT enough pressures that the CMT water injecting will be significantly i
rankag.
subcooled. By contrast, the IRWST injects at low presswes, and relatively small changes in the temperature can affect the subcoohng. It was also noted that while CMT tesaperasure is not identified as "high importance," it is idennfied as an area of "high interest" because it is unique to AP000. 'Iberefore, CMT temperanne is a parameter that will be examined in the benchmarking.
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NRC's October 10,1996 Comunents on MAAP4 and T/H Uncertainty RAI Responses t
j RAI#
Subject October 15 Telecen Discussion i
I 492.23 (Con 0 The response states that there "is no modelling There is a difference between saying that RNS prevents ADS-4 actuanon 4
masuteranon of whether RNS prevents ADS-4 and whether ADS-4 actuanon is needed for RNS. ADS-4 is not needal so actuanon." It was the staff's understanding that if RNS lower the RCS pressure to achieve RNS injection. Therefore, ADS-4 is I
was avastahh in a baseline PRA LOCA event tree, it not a decision point on event paths that have successful RNS. Queov=t affected the a==ulerauon of whether ADS-4 was that do not differentiate between successful core cooling and core damage needst.
are not asked un the event trees. It was also noted that if the ADS-4 i
question is not askal on an event tree, that does not mean that its 4
I actuauon has been prevented; it only encans that it was not credited.
During the discussson, another issue on a potendal adverse interact;on was j
identified by the NRC, However, the issue has already been transmitted j
via an RAI, and will be addressed through that pathway.
492.24 The RAI response does not provide a convincing "Ihe discussaan started with Westinghouse re-iecradng the position that argument that the break discharge coefficient should not analyzing a range of break sizes addresses the issue.
be an important parasmeser in the PIRT. Westinghouse should be prepared to explass the values of discharge The dialogue turned to a discussion of a broader issue of whether the coefficients used in the T-H analyses and why they are uncertaansaec of all the high isnportance itemis in the PIRT are going to be macervasive.
==haamaniasert as being haamdent it was agreed between Westinghouse and the NRC that we need further discussion on this broader issue.
492.25 The spien=== are on the interpretauon of trends in abe Westinghouse and the NRC agreed that we will need to see the results of j
compenson of MAAP4 and NOTRUMP, and what is the henchsmarkeg to be sure that we agree on the interpretation of trends.
l sneant by code deficiencies.
and whedier differences are significant. The NRC noted that the key to this issue is the last esmaemens of the RAI response: "Ihis will be judgal i
based on whether wrong conclusions would be drawn if analysis results 1
i were avadable from MAAP4 only."
i 492.30 The staff noses that one aspect of a SGIR that Westinghouse agrees with the comment, and will include this inue within distinguishes it from a SBLOCA scenario is the potenhal docunnentauon.
I for contamment bypass.
}
f l
t i
1 october 10, 1996 TO:
Cindy Haag FROM:
Bill Huffman SUBJ:
AP600 T-H Uncertainty RAI Responses
- Cindy, below are some of Alan Levin's comments on the RAI responses provided in your August 30, 1996 submittal on T-H uncertainty.
If you can have some kind of kritten response prepared for our Friday afternoon telecon, I will write a telecon summary which will document the responses.
RAI 492.15 Please provide a quantitative estimate of what Westinghouse considers " ample margin' to the PCT limit as discussed in this response.
Regarding the response to how margins will be reflected in the overall baseline PRA, Westinghouse has indicated that scenarios which have less than it. impact on the focused PRA will not be considered. Although this may be justifiable for the focused PRA, scenarios that are less than 1% of the focused PRA frequencies are of the same order of magnitude as
,the baseline PRA and would appear to potentially impact the baseline results.
Please provide additional information on this.
492.21 The response to this question did not specifically address the staff's concerns.
It is understood that during steam cooling conditions there is relatively little difference in the results if either ' good" or " poor" heat transfer is assumed.
The staff is more interested in the heat transfer during the transition from covered to uncovered and the return to covered.
For those sequences in which the core uncovers but
" damage" is not predicted because the core recovers before PCT exceeds whatever cutoff is established (to account for
" adequate margin), the timing and modeling of the transition from nucleate boiling to steam cooling and vice-versa may have a significant effect on the predicted peak temperature.
It is for this reason that it would appear that core heat transfer should be a high-importance phenomenon (it is tied to some extent to calculation of the two-phase level, as well).
The transition of most interest is probably trom uncovered to rewetted.
It is assumed that dryout is modelled as essentially concurrent with reaching a void fraction of 1 at a particular level (though that may not,actually be the physical case). However, depending on the rod surface temperature when the mixture level recovers, ' quenching" may well not coincide with the mixture level reaching a given elevation.
If there is a delay between recovery and rewet, the calculation of film boiling heat transfer and the transition to nucleate boiling is important.
492.23 The staff's question regarding this RAI response is how ons differentiates between the importance of one source of ECC l
injection and another in terms of its PIRT ranking.
Westinghouse did not address this aspect in the response.
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In addition, the response states that there "is no modelling consideration of whether RNS prevents ADS-4 actuation.'
It was the staff's understanding that if RNS was available in a baseline PRA LOCA event tree, it affected the consideration of whether ADS-4 was needed--i.e., failure of ADS-4 would not need to be considered in the event tree.
Please provide additional information on the role of RNS in the baseline PRA.
492.24 The response to this RAI does not clarify how Westinghouse will treat the discharge coefficient for breaks that are near or equal to the pipe diameter in question.
Specifically, for full diameter breaks (or equivalent), how would Westinghouse establish the break coefficient impact without varying it explicitly. The staff has seen analysis results from Westinghouse that appeared to indicate that relatively small changes in this parameter could cause significant changes in calculated peak temperatures (although it was not clear why that should have been the case). The RAI response does not provide a convincing argument that the break discharge coefficient should not be an important parameter in the PIRT.
Westinghouse should be prepared to explain the values of discharge coefficients used in the T-H analyses and why they are conservative.
492.'25 Please provide some elaboration on this response. For instance, if both NOTRUMP and KAAP.show the same ' trend
- of decreasing core mixture level, but NOTRUMP uncovers and MAAP does not, is that "okay* or "not okay?" Further, the second part of the answer seems in part to contradict the first, or at least, they do not appear entirely consistent. For the first paragraph, if differences in the trend are, in fact,
' caused by a "well-defined deficiency in MAAP4' does this mean that the comparison is 'okay?"
(That's what the sentence seems to say.)
If there is a 'well-defined deficiency in MAAP4," wouldn't this be a case where (in para. 2)
- phenomena are encountered that are beyond the capability of MAAP4?'
(i.e., doesn't a deficiency imply a situation beyond the capability of the code?)
492.30 The staff notes that one aspect of a SGTR that distinguishes it from a SBLOCA scenario is the potential for containment bypass. Westinghouse should address this difference when it prepares the pertinent documentation the discusses SGTRs rad SBLOCAs l
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This provides additional justification of classification of the main condenser evacuation system as a Class E system. NRC has questioned this classification in light of the Standard Review Plan and Regulatory Guide 1.26 in this area. Regulatory Guide 1.26 indicates that Class D standards should be applied to water-or steam-containing components not classified in a higher class that contain or may contain radioactive material. The main condenser evacuation system and the gland seal system in AP600 do not contain radioactive material. They may contain radioactive material if there is a steam generator tube leak that allows radioactive material to be introduced into the systems without appropriate stern system isolation. In such an event, the evacuation and gland seal systems may draw in radioactive material from the steam spaces in the condenser or turbine.
AP600 SSAR section 3.2.2.7 contains the conditions for which "may contain radioactive material" do not require classification of components in Class D:
The system is only potentially radioactive and does not normally contain radioactive material.
This is true for the evacuation and gland seal systems in a pressurized water reactor like AP600 where the, steam generator provides and effective barrier to the primary coolant.
The system has shown in plant operations that the operation with the system containing radioactive material meets or can meet unrestricted area release limits. Studies have shown that once a ;:nall steam generator leak is detectable it is still small enough to meet unrestricted area release limits. Automatic and techspec limits are exceeded well before unrestricted area release limits. For very large steam generator leaks, other operating parameters provide trip and isolation actions befcre exceeding unrestricted area release limits.
. An evaluation of the system confirms that the system contams features and components that keep the consequences of failure as low as reasonably achievable. This portion of AP600 is' very similar to many operating pressurized water reactor plants. There is a low probabdity of leakage and there are radiation monitors and radiation limits on the main steam system and evacuation exhausts. This has resulted in good performance record of no release from this source greater that unrestricted area release limits.
As a result of meeting these three conditions for not being Class D, the evacuation and gland seal systems are Class E.
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NRC REQUEST FOR ADDmONAL INFORMATION i
l Revision 1 m-Question 410.115-R1 Describe how AP600 SWS is designed to minimize the potential for water hammer.
Response
Prior to system stanup, the service water system (SWS) is filled with water and vens'--ee" e^::f-- 9.2.!.3.1. During normal operauon, the SWS pumps water from the basia at the SWS cooling tower, through piping and equipment, to a high point located at the SWS cooling tower riser; the cooling water is then discharged to atmosphere in a spray fashion above the cooling tower basin. The system arrangement is such that there are no high points in the system piping that can lead to formation of vapor pressure voids upon loss of system pumping.
When the pumps are stopped, check valves located at the discharge of each pump minimize reverse flow of system fluid through the-pumps and into the basin; alsc, :":; :: ifn-5 '::'- ' -in. S ;-----
r=: :;; _i if both pumps stop due so loss of normal ac power, cooling tower blowdown is isolased. Therefore, drain down of system fluid is minimized when the system is shut down. Drainage that might occur, : _:t x 'l_ _ f S :- " ""
- .:: : :" ; " : is replaced by air. No vapor cavities will form. Therefore, the potential for water hammer due to water column rejoining upon pump r.. tart is minimized.
Motor operated valves at the discharge of each SWS pump are interlocked to close prW to pump start. These valves then open at a controlled rees following pump start to slowly admit waner to the system.1his feature results is reduced fluid velocities during system start and minimizes transiest effiscts that may occur as the system sweeps out any-air and obtains a water solid condition. Temperatures in the system are moderate and the pressure of the SWS fluid is kept above its saturanos pressure at all locanons. 1herefore, the poseanal for waaer hammer due to thermodynamic voeding and subsequent vapor collapse is minimi==d These are no fast acting power-operased valves in the system, and the only check valves in the normal process flow path are in a standard configuranon at the discharge of each SWS pump. Therefore, the design of the system minimizes water hammer potential due to rapid valve actuanos.
SSAR Revision:
Section 9.2.1.2.1, General Description, add new fifth paragraph:
.. heat exchanger to dischargs to either cooling tower cell.
Temperatures in efe"synessi"ain umoderese and the pressure of the esevice water system fluid is kept above saturation at af locadoes.1 bis along wielt other design foneeres of the system arrangement and control of valves minnaians abs possadal for ^
Y " or trassent waaer beauner.
Service waner maaerials.
Secnoa 9.2.1.2.3.6, Loss of Normal AC Power Operanon, revise as follows:
410.115ti-1
4 NRC REQUEST FOR ADDmONAL INFORMATION 1
In t!e event of loss of normal ac power, the service water pumps and cooling tower fans, along with the associated motor operated valves are automatically loaded onto their associated diesel bus. This includes isolation of cooling tower blowdown, which mlat=l= drain down of the system while both pumps are off.
What drainage that does occur is replaced by air without vapor cavities. The potential for water hammer on pump restart is minimized. Both pumps and both cooling tower cells automatically start after power from the diesel generator is available. Following automatic start, the operator may return the system to the appropriate configuration.
l l
1 1
I 4
4 j
f f
410.iisri-2 W wasnnpouse
i FAX to Joe Sebmsky at NRC l
This is to amplify our " doneness" for Chapter 14 of the SSAR and DSER.
j Revision 9 (Augus',1996) of the SSAR provided our last planned revision of t
Chapter 14. This chapter will be changed only if an error is found or if l
required by NRC. The Open Item tracking system indicates that 82 of the 84 i
i items associated with Chapter 14 show "(W) Status" of " Closed". The remaining 2 items are associated with the ITAACs and are being tracked with other ITAAC related open items. The "(NRC) Status" for the 82 items associated with Chapter 14 shows none that are " Resolved" or " Closed."
Westinghouse knows of no further submittal requirements for Chapter 14.
l Westinghouse recognizes that NRC has linked review of Chapter 14 with review I
of the ITAACs. It is our intent to supply NRC with all information necessary for it to write the Chapter 14 portion of the FSER by December 2,1996. Since i
the 2 items associated with the ITAACs will be closed upon the submittal of the ITAACs in early November and is not associated with Chapter 14, itself, we I
request that the NRC understand that Westinghouse is not expecting to submit any additional revisions or information for Chapter 14. We should have a teleconference definitely scheduled to resolve any remaining NRC concern.
i l
Jim Winters October 9,1996
1 l
l FAX COVER SHEET Westinghouse b
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The following pages are being sent from the Westinghouse Energy Center, East Tower, Monroewi5e, i
PA. If any problems occur during this transmission, please ca5:
4 i
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h NRC REQUEST FOR ADDrTIONAL INFORMATION Revision 1 Question 410.255r1 Section 10.4.1.2.1 of the SSAR states " refer to Table 10.3.51 for permissible cooling water inleakage and time of operation for maintaining the required condensate /feedwater quality." Describe how the information in this table provides the above information. Where is the permissible cooling water leakage? Where is the infonnation of length of time that the condenser may operate with degraded conditions without affecting the condensate /feedwater quality for safe operation? What are the definition of the action levels (1,2, and 3) listed in Table 10.3.5-17 Also, provide j
information in the SSAR regarding the procedure to repair condensate leaks in accordance with Section 10.4.1 of RG 1.70.
Response
SSAR subsection 10.4.1.2.1 is intended to convey that there is no absolute value of cooling water inleakage nor specific time of operation for maintaining the required condensate or feedwater quality. The measured parameten that affect plant performance and operator actions are the water quality values in SSAR Table 10.3.5-1. As a basis for design of the condensate polishing system, cooling water inleakage of.001 gpm " continuous" and.1 gpm
" faulted" are used. These values are identified in SSAR subsection 10.4.6.1.2. Note that the circulating water system described in the SSAR is for reference only. Any certified AP600 may have another type or source of circulating water. As a result, the effect of.001 gpm inleakage of cooling water on condensate or feedwater will vary from plant to plant. Thus the real limit on inleakage is on the resultant quality of condensate and feedwater and not on 4
the amount of time of cooling water inleakage. Once condensate or feedwater quality are degraded to outside the limits contamed in Table 10.3.5-1, the operator should take actions consistent with the EPRI NP-2701, PWR Secondary Water Chemistry Guidelines. 'Ihis EPRI document defines action levels I,2 and 3 and the actions required for each. SSAR subsection 10.4.1, Revision 6, provides a description of the procedure for repairing condensate tube leaks.
SSAR Revision: None l
p 410.255ti-1
]
FAX COVER SHEET I
W95tingh0088 W
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RECIPIENT INFORMATION SENDER INFORMATION i
DATE:
{gan 27/9%
NAME:
,,1,1 (X)icTcq I
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PHONE:
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- 10. Steam and Power Coenrsion Sp m-CHAPTER 10 STEAM AND POWER CONVERSION SYSTEM 10.1 Summary Description The steam and power conversion system is designed to remove heat energy from the reactor coolant system via the two steam generators and to convert it to eisctrical power in the turbine-generator. The main condenser deaerates the condensate and transfers heat that is unusable in the cycle to the circulating water system. The regenerative turbine cycle heats the feedwater, and the main feedwater system returns it to the steam generators.
Table 10.1-1 gives the significant design and performance data for the major system components. Figure 10.1-1 shows the heat balance for the tubine cycle process.
10.1.1 General Description 2
The steam generated in the two steam generators is supplied to the high-pressure turbine by j
the main steam system. After expansion through the high-pressure turbine, the steam passes through the moisture separator / reheater (MSR) and is then admitted to the two low-pressure turbines. A portion of the steam is extracted from the high-and low-pressure turbines for -
seven stages of feedwater heating.
Exhaust steam from the low-pressure turbines is enadaaerd and deaerated in the main condenser. The heat rejected in the main condenser is removed by the circulating water system (CWS). The condensate pumps take suction from the condenser botwell and deliver the condensate through four stages of low-pressure closed feedwater heaters to the fifth stage, open deaerstmg heater. Condensate then flows to the suction of the steam generator feedwater booster pump and is discharged to the sucuon of the main feedwater pump. The steam generator feedwater pumps discharge the feedwater through two stages of high-pressure feedwater heaters to the two steam generators.
The moisture separator. drain is pumped to the deaerator.
The reheater drams and high-pressure feedwater heater drains c==cada into the deaerator. Drams from the low-pressure feedwater heaters are caecadan through mecanively lower pressure feedwater heaters to the main raadaaw.
,.tp.t af At The Westinghcuse turbine generator has : s..O '
.e.
ef 675,000 kW for the Westinghouse nuclear steam supply system (NSSS) thermal output of 1,940 MWt. The prmeipal turbine-generator conditions for the turbine rating are listed in Table 10.1-1. The raied system E+iW-3 for the NSSS are listed in Table 10.1-1. The systems of the turbine cycle have been designed to meet the maximum expected turbme generator conditions.
Instrumentanon systems are designed for the normal operanng conditions of the steam and condensate systerns. The systems are designed for safe and reliable control and irs-pe.k 1
W Revision: 5 10.1-1 February 29,1996
1 1
- 10. Stenas and Power Coevenion Systen FAW -
I 1
Table 10.1-1 SIGNIFICANT DESIGN FEATURES AND PERFORMANCE CHARACTERISTICS FOR MAJOR STEAM AND POWER CONVERSION SYSTEM COMPONENTS Nuclear Stenas Supply Systesa, Full Power Operation Rated NSSS power (MWt).............................
1940 Steam generator outlet pressure (psig)...........................................
833 Steam generator inlet feedwater temperature ('F)...........
........................... 435 l Steam generator outlet steam moisture (%)...........................................
0.25 Steam generator outlet r eam temperature (oF)...............
523 I
Quantity of steam generators........................................................ 2 Flow rate per steam generator Oter)........................................... 4.22 x 10' l
Turbine Output (kW)...................................................
675.000 kW (
)
Turbine type........................................................ T
- pound, 4-flow, 47-in.
last-stage blade Turbine elements....................................................... I high pressure 2 low pressure Operating speed (rpm)....................................................... 1800 1
1 h<J bal,- vala l
1 l
l ll y Weg$lghougg Revision: 5 10.1-5 Fetunary 29,1996
)
i i
FAX to Bill Huffman at NRC 4
l This is to amplify our " doneness" for section 16.2 of the SSAR and DSER.
Revision 7 (April,1996) of the SSAR provided our last planned revision of
-section 16.2. However, this section will be revised to reflect agreements 4
j reached at an NRC/W meeting on August 16, 1996. Otherwise, it will be l
changed only if an error is found or if required by NRC. The Open Item j
tracking system indicates that 7 of the 14 items associated with section 16.2 i
show "(W) Status" of " Closed". Of the remaining 7 items, 6 reflect the agreements of the August 16 meeting and 1 is associated with the Technical Specifications. This 1 item is being tracked as a TechSpec Open Item. The
"(NRC) Status" for the 13 items associated with section 16.2, itself, includes 7 j
that are " Closed" apd 6 that are " Resolved." Westinghouse knows of no submittal requirements other than the resubmittal of section 16.2 resulting from the August 16 meeting. It is our intent to supply NRC with all information necessary for it to write the section 16.2 portion of the FSER by October 31, 1996. Since the 1 item associated with TechSpecs above is not associated with section 16.2, itself, we request that the NRC understand that Westinghouse is not expecting to submit any additional revisions or information for section 16.2, other than for the August 16 meeting. We should have a teleconference definitely scheduled to resolve any remaining NRC concern.
Jim Winters September 26,1996 t
'1 i
1 FAX to Tom Kenyon at NRC
~
This is to amplify our " doneness" for Chapter 13 of the SSAR and DSER.
1 Revision 9 (August,1996) of the SSAR provided our last planned revision of j
Chapter 13. This chapter will otherwise be changed only if an error is found or if required by NRC. The Open Item tracking system indicates that 41 of the 45 items associated with Chapter 13 show "(W) Status" of " Closed". Of the j
l remaining 4 items, 3 will be " closed" upon resubmittal of our at-power ERGS, i
and are being tracked as ERG Open Items. The other is associated with habitability of the Technical Support Center (TSC) and will be resolved with other items associated with the TSC. It is being tracked as an MMIS Open
].
Item. The "(NRC) Status" for the 41 shown by "(W) Status" as " Closed" l
includes 5 that are " Closed" and 5 that are " Resolved." Westinghouse knows j'
of no submittal requirements for the other 31. It is out intent to supply NRC with all infoimation necessary for it to write the Chapter 13 portion of the j
FSER by October 18, 1996. Since the 4 items discussed above are not l
associated with Chapter 13, itself, we request that the NRC understand that l
Westinghouse is not expecting to submit any additional revisions or information for Chapter 13. We should have a teleconference definitely scheduled to i
resolve any remaining NRC concern.
t l
i i
l C>#
i l
Jim Winters j
September 26,1996 i
1 l
l
4 i
i M Westinghouse FAX COVER SHEET W
l RECIPIENT INFORMATION SENDER INFORMATION i
i DATE:
9 97-26, /99b NAME:
% k)wTEM 2
TO:
Dragg
[Aucte d LOCATION:
ENERGY CENTER - EAST PHONG:
FACSIMILE:
PHONE:
Of fice: e//2 -374-52 90 I
COMPANY:
Facsimile:
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284-4887 3
d 3 Al/2.C outside: (412)374-4887 t
LOCATION:
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)
Cover + Pages 1+2
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The following pages are being sent from the Westinghouse Energy Center, East Tower, Monroevi5e, i
PA. If any problems occur during this transmission, please cad:
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)
COMMENTS:
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- 9. Auxillary Systems l-9.2.1.4 Tests and Inspections Preoperational testing is described in Chapter 14. 'Ihe performance, stmetural, and leaktight integrity of system components is demonstrated by operation of the system.
(
l 9.2.1.5 Instrument Applications l
Pressure indication, with low and high alarms, is provided for the discharge of each service i
water pump. A low pressure signal automatically starts the standby pump. Flow indication, i
with low and high alarms, is also provided for each service water pump. Due to the system configuration, pump flow indication can also normally be used to monitor flow through the heat exchanger or heat exchangers in service.
Temperature indication is provided for the service water supply to each component cooling water heat exchanger and for the discharge from each heat exchanger to determme the temperature differential across the heat exchanger. Heat exchanger inlet temperature indication also is used for performance monitoring of the service water cooling tower.' Iow i
and high heat exchanger inlet temperature alarms are provided. A high alarm is provided for the outlet temperature from each heat exchanger. Temperature instmmentation is provided for the service water retum to each cooling tower cell to automatically control the operation I
of the associated cell fan.
Differential pressure measurement across each service water strainer is provided and will initiate backwash of the stramer on high differential. A high-high differential pressure alarm
)
l across the strainer is provided.
Power actuated valves in the SWS are provided with valve position indication instrumentation.
In addition, the tower bypass valves are provided with position indication instrumentation.
Level indication is provided for the cooling tower basin along with high and low level alarms.
'Ihe basin level signal is also used to control the normal makeup water supply valve to maintain the proper level in the cooling tower basin. Flow iad% of cooling tower basin normal makeup is provuled using ntanong ggeupgalveg g3 4 A radianon monitor with a gh alarm is provided to monitor the service water blowdown flow fordetection of poten y radioactive leakage into the SWS from the component cooling 1
wasar best exchangers.
Flow uxhcation of the blowdown flow is provxied using i
instrumentation internal to the blowdown control valve.
4 l
9.2.2 Component Cooling Water System
'Ihe component cooling water system is a non safety-related, closed loop cooling system that transfers beat from various plant caapaaants to the service water system during normal phases of operanon. It removes heat from vanous cerg-:=4 needed for plant operanon and removes core decay heat and sensible heat for normal reactor shutdown and cooldown.
(
Revision: 6 3 WBEtk1ghoute 9.2-7 March 29,1996
l
+
- 9. Aurmary Systerns l
9.2.1.2.3.3 Power Operation De service water system, during normal power operation, provides cooling water at a i
maximum temperature of 89'F to the component cooling water heat exchanger in service.
t l
One semce water pump and one cooling tower cell are in service. De flow rate and heat load are shown in Table 9.2.1-1.
l De standby service water pump is automatically started if the operating pump should fail, thereby providing a reliable source of cooling water. De system is designed so either pump can serve as the operating or standby pump.
9.2.1.2.3.4 Plant Cooldown/ Shutdown
?
During the plant cooldown phase in which the normal residual heat removal system has been placed in service and is providing shutdown cooling, the semce water cooling tower providea l
cooling water at a temperature of 88.5'F or less when operstmg at design heat load and at an j
ambient wet bulb temperature of no greater than 80*F (1 percent exceedance). Two service j
water pumps and two cooling tower cells are normally used for plant cooldown, and the cross-connection valves between trams are normally closed. De semce water system heat load and i
flow rate are shown in Table 9.2.1-1. Durms these modes of operation the normal residual,
heat removal system and the component cooling water system remove sensible and decay heat l
from the reactor coolant system. In the event of failure of a service water system pump or
{
cooling tower fan, the cooldown time is extended.
f 9.2.1.2.3.5 Refueling l
I During refueling, the service water system normally pmvides cooling water flow to both I
component cooling water system heat exchangers. Two semce water pumps normally provide l
flow through the system for refueling modes.
i l
9.2.1.2.3.6 IAss of Nerusal AC Power Operaties i
j l
In the event of loss of normal ac power, the semce water pumps and cooling tower fans, i
along with the associated motor operated valves, are - -
+="y loaded onto their associated diesel bus. Both pumps and both cooling tower cells automatically start after power from the j
diesel generator is available. Following automanc start, the operator may return the system to the appropnaes configuranon.
l 9.2.1J Seesty Evaluettom l
De service water systern has no safety-related functions and therefore requires no nuclear l
safety evaluation.$ f..J, ub. fLJ, s ch 6tel,4 rk u r s. c wd,-
sfs% %u b/wdcwn [lw cm k e scleicd y nah.m I ceted. rk
]
%e, b/wdow udx Lit clad 4cn lou dedmdp n v ans ~,& w.
1 f
Revisies: 6 March 29,1996 9.24 T Wagttgitoute
i l
FAX to Tom Kenyon at NRC This is to amplify our " doneness" for Chapter 7 of the SSAR and DSER.
Revision 8 (June,1-996) of the SSAR provided our last planned revision of Chapter 7. This chapter will otherwise be changed only if an error is found or j
if required by NRC. The Open Item tracking system indicates that 27 of the 28 j
items associated with Chapter 7 show "(W) Status" of " Closed". The j
remaining item will be " closed" upon submittal of our ITAACs, and has been i
identified as an ITAAC Open Item. The "(NRC) Status" for the 27 shown by l
"(W) Status" as " Closed" includes 9 that are " Resolved." Westinghouse knows i
of no submittal requirements for the other 18. It is our intent to supply NRC l
with all information necessary for it to write the Chapter 7 portion of the FSER i
.by October 4,1996,, except for the ITAAC item. We therefore request that the NRC understand that Westinghouse is not expecting to submit any additional i
revisions or information for Chapter 7 itself (except for the ITAAC item identified above) and we should have a teleconference definitely scheduled to j
resolve any remaining NRC concern.
i i
4 Jim Winters 4
September 23,1996 l
4 I
I l
l, l
FAX to Diane Jackson at NRC 3
This is to amplify our " doneness" for SSAR subsection 3.11 of the SSAR and DSER. Revision 8 (June,1996) of the SSAR provided our last planned l
revision of SSAR subsection 3.11. This chapter will otherwise be changed only l
if an error is found or if required by NRC. The Open Item tracking system i
indicates that 17 of the 23 items associated with SSAR subsection 3.11 show i
"(W) Status" of " Closed". We received 6 new RAIs in a letter dated August 8.
These remaining 6 items will be " closed" upon submittal of our RAI responses.
i The "(NRC) Status" for the 17 shown by "(W) Status" as " Closed" includes none that are " Closed" or " Resolved." Westinghouse knows of no submittal i
requirements for these 17. It is our intent to supply NRC with all information necessary for it to write the SSAR subsection 3.11 portion of the FSER by October 10, 1996. We therefore request that the NRC understand that
{
Westinghouse is not expecting to submit any additional revisions or information i
for SSAR subsection 3.11 itself (except for the 6 new RAls identified above) and we should have a teleconference definitely scheduled to resolve any remaining NRC concern.
t l
cx** -
i Jim Winters September 23,1996
i i
i FAX to Bill Huffman at NRC This is to amplify our " doneness" for Chapter 4 of the SSAR and DSER.
Revision 8 (June,1996) of the SSAR provided our last planned revision of Chapter 4. This chapter will otherwiseW~ changed only if an error is found or if required by NRC. The Open Item tracking system indicates that 29 of the 29 items associated with Chapter 4 show "(W) Status" of " Closed". The "(NRC)
Status" for the 29 shown by "(W) Status" as " Closed" includes 7 that are
" Closed" and 20 that are " Resolved." Westinghouse knows of no submittal requirements for the other 2. It is our intent to supply NRC with all information necessary for it to write the Chapter 4 portion of the FSER by October 10, 1996. We therefore request that the NRC understand that Westinghouse is not expecting to submit any additional revisions or information for Chapter 4 and we should have a teleconference definitely scheduled to resolve any remaining NRC concern.
Jim Winters September 23,1996
l FAX to Diane Jackson at NRC I
This is to amplify our " doneness" for SSAR subsection 3.7 of the SSAR and j
DSER. Revision 9 (August,1996) of the SSAR provided our last planned l
revision of SSAR subsection 3.7. This chapter will otherwise be changed only l
if an error is found or if required by NRC. The Open Item tracking system i
indicates that 69 of the 75 items associated with SSAR subsection 3.7 show
"(W) Status" of " Closed". The remaining items will be discussed at our next i
meeting with NRC on seismic items. We hope this next meeting can be held in October. The "(NRC) Status" for the 75 items includes 4 that are " Closed" and 56 that are " Resolved." Westinghouse knows of no submittal requirements for the other 15,except for our meeting on seismic items. It is our intent to supply NRC with all information necessary for it to write the SSAR subsection 3.7 i
portion of the FSER by October 4,1996, except for the 6 meeting items. We therefore request that the NRC understand that Westinghouse is not expecting to-l submit any additional revisions or information for SSAR subsection 3.7 itself (except for the seismic meeting identified above) and we should have a teleconference definitely scheduled to resolve any remaining NRC concern.
c>
Jim Winters September 23,1996 e
4
i FAX to Diane Jackson at NRC I
This is to amplify our " doneness" for Chapter 2 of the SSAR and DSER.
Revision 9 (August,1996) of the SSAR provided our last planned revision of Chapter 2. This chapter will otherwise be changed only if an error is found or l
if required by NRC. The Open Item tracking system indicates that 103 of the 103 items associated with Chapter 2 show "(W) Status" of " Closed". The
"(NRC) Status" for the 103 shown by "(W) Status" as " Closed" includes 1 that is " Dropped" and 92 that are " Resolved." Westinghouse is in the process of determining submittal requirements for the other 10. It is our intent to supply l
NRC with all information necessary for it to write the Chapter 2 portion of the i
FSER by October 11, 1996. We therefore request that the NRC understand l
that Westinghouse is finalizing any additional revisions or information for j
Chaipter 2 itself and we should have a teleconference definitely scheduled to res' lve any remaining NRC concern.
o l
I Jim Winters September 23,1996 e
1 1
i FAX to Diane Jackson at NRC i
This is to request your assistance to maximize our " doneness" for subsection 3.2 of the SSAR and DSER. The Open Item tracking system indicates that only 8 of the 20 items associated with SSAR subsection 3.2 show "(W) Status" of " Closed". Tne "(NRC) Status" for the 20 items includes only 7 that are
" Resolved." It is our intent to supply NRC with all information necessary for it to write the SSAR subsection 3.2 portion of the FSER by October 10, 1996.
We therefore requests that we have a teleconference or meeting definitely i
scheduled to resolve any remaining NRC concerns.
1 i
h 4
4 Jim Winters September 23,1996
$