NSD-NRC-98-5778, Provides Commitment to Include Requested Changes Into AP600 Design Control Document.Discussion W/Vijuk on 980825 Re Disposition of Ltrs DCP/NRC1074,dtd 971016 & DCP/NRC1324,dtd 980403,formalized

Provides Commitment to Include Requested Changes Into AP600 Design Control Document.Discussion W/Vijuk on 980825 Re Disposition of Ltrs DCP/NRC1074,dtd 971016 & DCP/NRC1324,dtd 980403,formalized

ML20238F746
Person / Time
Site:	05200003
Issue date:	08/27/1998
From:	Mcintyre B WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	Quay T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NSD-NRC-98-5778, NUDOCS 9809040268
Download: ML20238F746 (6)

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Westinghouse - Energy Systems Bm 355 Pittsburgh Pennsylvania 15230-0355 Electric Corporation DCP/NRCl434 NSD-NRC-98 5778-Docket No.: 52-003 August 27,1998 Docament Control Desk U. S. Nuclear Regulatory Commission Washington, IE 20555 ATTENTION: T.R. QUAY SUB.fECT: STAFF REQUESTED REVISIONS TO AP600 SSAR

Dear Mr. Quay:

On Monday, August 24,1998, your staff faxed the attachment to this letter to. Westinghouse requesting that these changes be incorporated into the AP600 Standard Safety Analysis Report. Based on our telephone conversation on August 26,1998, it is our understanding that this fax represents all NRC comments concerning the AP600 SSAR through Revision 25. Pursuant to our discussion on August 26,1998, this letter provides a commitment to include these changes into the AP600 Design

- Control Document.

1 This letter also formalizes your discussion with Mr. Vijuk on Tuesday, August 25,1998, concerning the disposition of letters DCP/NRC1074, dated October 16,1997, and DCP/NRCl324, dated April 3, 1998, it is our understanding that since these letters have both been revised that the NRC will destroy the original submittals.

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Brian A. McIntyre, Manager Advanced Plant Safety and Licensing ami /)

cc: J. M. Sebrosky, NRC/NRR/DRPM [

lt A. Sepp, Westinghouse ,

i 9909040268 990827 $

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t FeeM b the staff on SSAR revision 25  :

1) Misspelled the word " Interface" on p.1.2 22.

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2) Also, p.13-1, SSAR Rev 24, section 13.1, uses the term "mone interface system design" and not current term of " human system interface design".

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Al?G 24 '98 12:06 PAGE.002

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6. Enstaserod safety Features .

6.4.2.1 De5mition of the Mala Control Rooan Presa Boundary De main control room pressure boundary is located on elevatiort 117'-6* in the =nitwy [

building, on the nuclear island. As shown in Figure 6.4-1, the presswe boundary cacompasses /

the main contml area tagging room, operator ama, shift supavisort office.(leWdesk,7 h kitchen, and toilet facilities. De presure boundary is repmsented byibe hea~vy-')olid line around the periphery of the boundary in the figure. The stairwellleading down to elevationN 100' is specifically excluded from the boundary.

De areas, equipment, and matenals to which the main control room operator requires access during a postulated accident are shown in Figure 6.+1. His figure is a subset of Figwe 1.2-8. Amas adjacent to the main control room are shown in Figurcs 1.2-25 and 1.2-31. He layout, size, and ergonomics of the operator workstations and wel panel information system depicted in Figure 6.4-1 do not reflect the results of the design procesa described in Chapter 18. De actual size, shape, ergonomics, and layout of the operator workstations and wall panel information system is an output of the design process in Chapter 18.

6.4.2.2 General Description De main control room emergency habitability system air storage tanks me sized to deliver the required air flow to the main control room to meet the ventdation and pressurizadon requirements for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> based on Ge performance requirement of subsecsion 6.4.1.1.

.. Normal system makeup is povided by a connecuon to the breathable quality alt compressor

?**. in the. compressed and instrumet air systern (CAS). See subsecdon 9.3.1 for a description of the CAS. A connection for mfilling apea% is provide:1 in the CAS.

He function of paviding passive heat sinks for the main control room, instrumentation and control rooms, and de equiprnent rooms is part of the main contml room ernergency habitability system. he heat sinks for each roorn are designed to limit the temperature rise inside each room during the 72-hour period followay a loss of noclear island nonradioactive ventilation system operation. he heat sinks consist primarily of the thermal mass cf the concrete that makes up the ceilings and walls of these rooms.

To enhance the heat.absorting capability of the ceilings, a metal form is attached to the intedor surface of the concrete at selected locations. Medalhe plates am etted gr /.*cular to the form. Dese plates extend into the room and act as thermal fins to enhance the best transfer from the room air to the coenrete. De specifies of the fin construction for the main control room and I&C room ceilings are described in subsection 3.8.4.1.2.

he nonnal operadng tempenuures in the main control room, instrumentation and control moms. de equipment roorns. and adjacent rooms are kept within a specified range by the nuclear island nonradioar.tive ventilation system in order to maintain a design basis initial beat sink capacity of each room. See sutmetion 9.4.1 for a description of the nuclear island namarhactive ventilation system.

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Reddon: 24 Y M @ 88 6.4 3 J837 % 1998 AUG 24 '98 12:06 PAGE.003

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6. Engineered Safety Features e

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am c'm TOILET KITCHEN s NM - _

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J j OPERATOR ELEC. / / AREA.

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RODM ' CLERK ) SHIFT SUPV.

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Figure 6.41 Mala Control Room Envelope w

Revision: 25 August 19,1998 6.4 16 Westinghouse AUG 24 '90 12:07 PAGE.004 I

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', 9. AusBary Systems + e n SP&.in f l O 9A Airtonditionlag, Heating, CooUmg, and Ventilar#m Systein The air-conditioning, headng, cooling, and ventilation system is comprised of the following systems that serve the various bulklings and semctums of the planc

• Nuclear island non=Mye ventilation system (subsection 9.4.1)

= ' Annex / auxiliary buildings nonradioactive HVAC system (subsection 9A.2)

• Radiologically controlled area ventilation system (subsectwn 9AJ)

• Contamment recirculation cooling system (subsection 9.4.6) l

• Containment air filtradon system (subsection 9A.7) e Radwasts building HVAC system (subsection 9.4.8)

. Turbine building ventilation system (subsection 9.4.9)

= Diesel generator building heating and ventilation systern (subsecsion 9.4.10)

• 'IIcalth physics and hot machine shop HVAC system (subsection 9.4.11) 9A.1 Nuclear Island Nonradioactive Ventuation Systess "Ihe nuclear island nonradioactive ventilation synem (VBS) serves the main control room (MCR), tecimical support center (TSC). Cleas IE de equipment rooms. Class IE instrumentadon and conpot (IdcC Class IE electrical penetration rooms, Class 1E /___ ~

battery rooms, remote shutdow area, r coolant pump trip switchgear rooms, adjacent G corridors, and the passive con , cooling system (PCS) valve room during normal plant operadon.

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• 1 The main control room emergency habitability system provides main control room habitabillry )

in the event of a design basis accident (DBA) and is described in Section 6.4. j 9A.1.1 Design Basis ,

9A.1.1.1 Safety Design Basis The nuclear island nonradioactive ventilation system provides the following nuclear safety-related design basis functions:

• Moniton the main control room supply air for radioactive particulate and iodme  !

concentrations

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Revision: 24 I Westinghouse 9.4-1 July 30,1998 AUG 24 '98 12:07 PAGE.005

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• Provides smoke removal capability for the Class lE electrical equipment rooms and battery rootns

'Ihe system maintains the following room temperatures based on the maximum and minimum outside air safety temperature condidons shown in Chapter 2, Tab!e 2-1: -

i Area I Temperators N

Class IE battery rooms 67 - 73 Class 1E de equipment rooms 67 - 73 Class 1E electrical penetration rooms 67 - 73 i Class IE instmmentation and control rooAns 67 - 73 Corridors 67 73 Remote shutdo D4 Y '

67 - 73  %

Reactor coolant p 'p switchgear rooms 67 - 73 HVAC equipment rooms 50 - 85  !

Passive Containment Cooling Systan Valve Roosa l The subsystem maintains the following room temperatures based on the maximum and mirdmura outside air safety temperamre condidons shown in Chapter 2, Table 21:

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Area Temperature . , ,

N Passive contamment cooling system valve room 50 - 120 Post.72. Hour Design Basis Main Control Room "Ihn specific function of the nuclear island nonradioactive ventilation system is to maintain the control room below a temperamre approximately 4.5'F above the average outdoor air temperature.

Divisions B and C Instrumentation and Control Roomas Dealga Basis "Ihe specific function of the nuclear island nonradioactive ventilation system is to maintain the IAC rooms below the qualification temperanut of the I&C equipment.

Revisiest 24 j July 30.1998 9.44 T Westinghouse AUG 24 '98 12:07 PAGE.006 l

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