NSD-NRC-97-5047, Consolidates Responses & Resolutions of Items Associated W/Ssar Chapter 7 for Application for AP600 Design Certification

Consolidates Responses & Resolutions of Items Associated W/Ssar Chapter 7 for Application for AP600 Design Certification

ML20137Q357
Person / Time
Site:	05200003
Issue date:	04/01/1997
From:	Mcintyre B WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	Quay T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NSD-NRC-97-5047, SECY-97-051-C, SECY-97-51-C, NUDOCS 9704100228
Download: ML20137Q357 (8)

Text

-_

N 1

s

{f, s

1 s

Westinghouse Energy Systems gags smaacs Electric Corporation NSD-NRC-97-5047 DCP/NRC0799 Docket No.: STN-52-003 April 1,1997 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: T. R. QUAY

SUBJECT:

AP600 DESIGN CERTIFICATION; FORMAL NOTIFICATION OF RESOLUTION OF ITEMS ASSOCIATED WITil CIIAPTER 7.0

References:

SECY-97-051, " Schedule for the Staff's Review of the AP600 Design Certification Application," dated February 26,1997, forwarded by NRC letter " Westinghouse's Support of the Nuclear Regulatory Commission Review of the AP600 Design i

Certification Review," dated March 6,1997.

Dear Mr. Quay:

This letter is to fonnally consolidate responses and resolutions of items associated with SSAR Chapter.

7 and to confirm completion of submittal of final documentation related to SSAR Chapter 7 for our application for AP600 Design Certification. The Reference includes a milestone " Applicant Submits Final SSAR Revision & Documentation" by May 1997. Westinghouse interprets this to require NRC

[f acknowledgement of receipt of final documentation supporting our application for AP600 Design

/

Certification. To support this milestone, NRC and Westinghouse maintain a detailed activity plan which provides schedule goals for most SSAR/FSER sections and related activities, such as, the PRA, code validation, and ITAACs. In this detail activity plan, Westinghouse application input and NRC

[p0 internal FSER input for Chapter 7 of the SSAR had a schedule goal of December 31,1996. NRC and Westinghouse also maintain a joint open item tracking system to informally monitor the status and history of open items (DSER, RAI, meeting, and other) associated with our application.

NRC has requested that, although most items have been discussed and resolved using SSAR and RAI markups followed by formal revisions, Westinghouse consolidate their remaining resolutions into a

~!

single, formal response. Attachment I to this letter provides a chronology for each item discussed.

Westinghouse believes it has submitted resolution for all items for SSAR Chapter 7. Attachment 2 provides formalized copies resubmitting the resolving documentation for items not acknowledged by NRC. Note that some responses were provided some months ago. NRC is requested to acknowledge receipt of this information by directing Westinghouse to change the "NRC Status" to ' Action N" or

" Resolved" 353SA 9704100228 970401 y

PDR. ADOCK 05200003 d

i

^

appspppppy

NSD,NRC-97-5047

+

DCP/NRC0799 April 1,1997 1

l Based upon a review of the information provided for Chapter 7 of the SSAR and a review of the related open item entries in our informal tracking system, Westinghouse confirms its completion of the submittal of information to support this portion of our application. Any additional questions or.

requests for additional information on Chapter 7 of the SSAR which require formal response must be received by Westinghouse by May 9,1997 in order to support the May 1997 milestone in SECY-97-051, t

if you have any comments or questions on this letter please contact J. W. Winters (412-374-5290) or R. Nydes (412-374-4125).

W S

Brian A.

c ntyre, anager

' Advanced Plant Safety and Licensing i

jml Attactunent 1: Chronology for Chapter 7 Open Items : Chapter 7 Open Resolving Documentation cc:

D. Jackson, NRC N. J. Liparuto, Westinghouse (w/o Attachments)

T. Kenyon, NRC (w/o Attachments) l l

l i

StVA l

e 1

Attachment I to NSD-NRC-97-5047 Chronology for Open Items Associated with Chapter 7 Open NRC Response Vehide Response Date Appendix 2 Page Item Status Number 1044 Action W Fax - J. Winters to 3/21/97 1-4 l

T. Kenyon l

l 3135A i

s d

4 to NSD-NRC-97-5047 Resolving Documentation for Open Items Associated With Chapter 7 t

S i

e

'I

AP600 Open Item Tracking System Database: Executive Summary Date: 3/27/97 -

Select 6ete:

[nre st cenlel=* Action W' And (DSER Section] hLe '7** Sc:ted by Item #

he DSER Secteun/

- Tale /Descupson Resp (W)

NRC

(

No.

Branch Question Type Detail Status Enguieer Staus Status tenerNa /

Date _

1044 NRR/HICB 7.2.82 DSER4)I ITAAChutsch, K.

Confrm-W Actaa: W NTD-NRC-95-4464

(

[Westmghouse stundo provide infonnanon concerning envirtuwnental quahfiNof PMSNh~aakbess.ng kul i..[.^ ;Arnes al'nwe'thehma

andment espenenced by the components dunne operation.

It is desrable to have = Maw =tal margin tnait into the design The components should, therefore,1w quahfied by testag to lugher aeroperatures than '

specsfied in the SSAR for a given roarn envwonmese_ Wesunghouse should address this concern in the S$AR. Westmghouse shoidd also provide nuld 6

I'".'."_U"_"_'*' *t_"P. ment gificanoe in theg,.wh the caregading lTAAC. _ _ _ _ _, _ __.. _,,

. _.. _, _ _ ____. _._..._J.

c

Ckned - Technical information agreeded to by NRC dunng meetsng on May 15-16. Addmanal technical informatkut leganhag the espapment desagn margm to loss of HVAC has been incorporated into Revision 3 of the SSAR. Subsection 7.l.4 l.8. rkn 12/2 e

.Westmghouse needs to decide approach to ckne this item. rka 12/6 l

{ Action N - NRC still has the action to evaluate the Westeghouse proposal on procedwal fis ofinstrument overhearing after 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> penod (fi 28 mecung f

jauh W/SPLB/HICB). Based on I1/21 W/NRC telecun, tlus approach is reasonable; see quahficmion prognun in SSAR Section 311.

I i Action W - NRC requested W provi& proposed COL item for quahricanon margin and insuument sespoent data or document in the CDM and LM4ITAAC(W as considenng options, did not comnut to either approach). rkn 12/2 l

gW6;_..J does not consider there no be an applicable COL action to idennfy. Technicalinformanon relased to desagn meg-n against a loss of HVAC

'3

was provided in SSAR 7.1 A16 and is consadered technicauy resolved, as waws previously agreed to by NRC. This isem is considered ckmed sun there is

.no Westmghouse acuan rapired at glas time no address this item (since the NRC selases this comment to the PMS ITAAC,the responsable engmeer is

! changed to ITAAC). rka 1/1487.

i Action W -(from NRC on I/28N7) Subnut revised CMD & ITAAC sa include COL action to include aikhtional design margm to accunnlate a loss of the (normal HVAC. Provide an alarm af internal cainnet temperanses rea-h an escessive value.jww I/28 i

flhas was previously closed and is still considered closed, meanmg there is no Westinghouse actm identified or requucd o ckwe this nem; all nece submntals have been made. For background, SSAR Section 7.l 4.1.6 was revised in lib 1996 to address this. Specifically, there is a seinence which reads, *The cabmets containing the digital eqmpment are provided with temperiture sensors which provide an aksm ifirmernal cabinet temperatures reach an excessive value." This is ckned. rka 1/30/97.

Per telecon with Iluthert Li talay, the accon is for Westmghouse to include this alarm in the ITAAC. rka 2/1887. Rather than include the alarm specifically, the EQ info for PMS km a is mcluded in the draft ITAAC (pages of whid were famed today). W believes this a&hesus NRC

! concern rka 3/21 Confirm N - l'ax to Kenyon with ITAAC markup _wnet on 3/2 tS7.jww_ _

Page: I Total Records: I

l' VV YMSlingn0VS8 ra^ W V t H SH t:ET i

' RECIPlENT INFORMATION SENDER INFORMATION DATE:

/)1ARCM 2l /99 7 NAME.

3gy We TO:

LOCATION:

ENERGY CENTER.

IoA

[bN/0^/

F>ST CEce:(n.3 7q. yag PHONE:

FACSIMILE:

PHONE:

COMPANY:

Facsimile:

Mn:

284 4 % 7 (J S A/4 C outside: (412p74 4M7 LOCATION:

COVOr + Pages 1 + 2.

Tho following pages are being sent from the Westinghouse Energy Center, East Tower, Monroeville. PA. If any problems occur during this transmission, please call:

W.IN: 284 5125 (Janice) or Outside: (412)374 5125.

COMMENTS:

Mm

'THe A TTncr< eo rancus ce rw Pm s in w g a u n su co w 0 Pes) I> f o 4N,4ca.wr Cr<Nht ]. U)e Ate cunawt. " W sma "

TO "CwrMm IAJ ".

hLense cA a Arm 7 a t. v s wc csu en,weg",jge e, M ius 7u A c rw Al " aA. " Co u swm h/'

_{ t..' $cHA e 4 tA.

1 pn C f AJ7"IM.

AJ'{A 69 g g rt ce(

Q) uW i

s 4

4 2

< PROTECTION AND SAFETY MONITORING SYSTEM jj.u R:visI:n: 2 i;...,

, Eff;ctiv2: 10/31/96 q g 2.5.2 Protection and Safety Monitoring System Design Description i

ne protection and safety monitoring system (PMS) initiates reactor trip and actuation of engineered safety features in response to plant conditions monitored by process instrumentation and provides safety.related displays. 7'Ae. [vne bono / o r r es o cj e.me rd, o f f Ac. PMS a c h.p ie t.c ce m F,3 o e c. 2. 5. 2. - 1.

1.

De PMS has the equipment identified in Table 2.5.21.

2. The seismic Category I equipment, identified in Table 2.5.21, can withstand seismic design basis dynamic loads without loss of safety function. {os shoeAeune dem J orelocle)ne ua, [ e y q]

e be g o Me,ck n{

or

3. The Class IE equipment, identined in Table 2.5.21, can withstand the electromagnetic interference (EMI) and radio frequency interference (RFI) conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required j# ( to perform the safety functionf

. { N a) The Class IE equipment, identified in Table 2.5.2-1, is powered from their respective Class 1E dmsson.

b) Separation is provided between PMS Class IE divisions, and between Class IE divisions and non Class IE cable.

g 5 - De PMS provides the following safety related functions:

a) The PMS initiates an automatic reactor trip, as identified in Table 2.5.2 2, when plant process signals reach speci6ed limits, b) ne PMS initiates automatic actuation of engineered safety features, as identified in Table 2.5.2 3, when plant process signals reach speci6ed limits.

c) ne PMS provides manual initiation of reactor trip and selected engineered safety features as identified in Table 2.5.2-4.

Z e ne PMS provides the fo!!owing nonsafety related functions:

i a) ne PMS provides process signals tc the plant control system (PLS) through isolation devices.

l b) ne PMS provides process signals to the data display and processing system (DDS) through isolation devices.

e e

3 4

i

l'KUiLLilON Anu 3Al El Y MUNIiURING SYSTEM SECTION 2.5.2 1

3

\\

i Design Description REVISE ITEM NUMBER 3 TO BE AS FOLLOWS:

3.

De Class lE equipment, identified in Table 2.5.21, has c!ccincal surge withstand capability I

i (SWC), and can withstand the electromagnetic interference (EMI), radio frequency interference i

(RFI), and electrostatic discharge (ESD) conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety 4

function.

i 4

ADD THE FOLLOWING NEW ITEM NUMBER 4:

i De Class IE equipment, identified in Table 2.5.2-1, can withstand the room ambient temperature, 4

humidity, and mechanical vibtation conditions that would exist before, during, and following a i

i design basis accident without loss of safety function for the time required to perform the safety l

fu'nction.

REVISE ITEM NUMBER 9b (formally item 8b) TO BE AS FOLLOWS:

i 4

9. b) The PMS two-out-of four initiation logic revens to two out of.three coincidence logic if one of 1

the four channels is bypassed. The PMS automatically produces a reactor trip or engineered.

safety feature initiation upon an attempt to bypass more than two channels of a function that uses two-out of four initiation logic,

]

i I

t REVISE AND EXPAND ITEM NUMBER 11 (formally item 10) AS FOLLOWS:

11, De PMS hardware and software is developed using a planned design process which provides for specific design documentation and reviews during the following life cycle stages:

a) Design requirement phase b) Definition phase c) Development phase d) Test phase c) Installation phase f) Operation and maintenance phase.

12. De PMS software is designed, tested, installed, arid maintained using a process which incorporates a graded approach according to the software's relative imponance to safety and specifies requitements for:

a) Software management including documentation requirements, standards, revic0 requirements, and procedures for problem reponing and corrective action b) Software configuration management including historical records of software and control of schware changes c) Verification and validation including requirements for reviewer independence.

4-

-