View source for NSD-NRC-98-5732, Forwards Correspondence Previously Sent Informally Over Period of 980309-0629.Index of Encl Matl,Encl

{{Adams
| number = ML20236H777
| issue date = 07/01/1998
| title = Forwards Correspondence Previously Sent Informally Over Period of 980309-0629.Index of Encl Matl,Encl
| author name = Mcintyre B
| author affiliation = WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
| addressee name = Quay T
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05200003
| license number = 
| contact person = 
| document report number = NSD-NRC-98-5732, NUDOCS 9807070345
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 325
}}

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N Westinghouse                                                Energy Systems                         Bm 355 Pittsbu@ Pennsylvania 15230 0355 Electric Corporation DCP/NRCl391 NSD-NRC-98-5732 Docket No.: 52-003 July 1,1998 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: T. R. QUAY

==SUBJECT:==
INFORMAL CORRESPONDENCE

==Dear Mr. Quay:==

Please find enclosed a formal transmittal of correspondence we have previously sent to you informally.
This informal correspondence was sent over the period March 9,1998, through June 29,1998.
Attachment 1 provides the index of the attached material as you have requested.
Brian A. Mc ntyre, Manager A                                   g i
Advanced Plant Safety and Licensing                                                                                                     )
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i Attachment Enclosure                                                                                                                        [  /
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J. W. Roe, NRC/DRPM (w/o Enclosure)                    ,
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t Attaebment 1 to Westinghouse Letter DCP/NRC1391 DATE   ADDRESSEE                                           DESCRIPTION 3/9/98    Wilson -          EQ responses for CDM.
3/17/98  Wilson -          Liquid radwaste CDM.
3/18/98   Kenyon            Proposed SSAR changes for Chapter 2. Will be in Rev 22.
3/20/98   Wilson            Proposed changes to the CDM from 3/12 meeting.
3/23/98   Huffman           Proposed changes to ESFAS table.
3/26/98   Wilson            ITAAC seismic design floor response spectra.
3/26/98   Sebrosky          Figures for shield building roof. Will be in Rev 22.
3/26/98_ . Wilson           Response to OITS 6642.
3/30/98-  Sebrosky          Proposed revisions to Chapter 3.
3/30/98   Wilson            Proposed SSAR and ITAAC modifications for 3.9.3.
3/30/98   Sebrosky          Information for Tom Cheng - Table 3.8.4-7.
3/31/98   Huffman           Advance copy of response for RAI 480.1159F.
3/31/98   Huffman           Proposed changes to remove standards for paint and coatings.
Will be in Rev 22.
4/1/98    Wilson            Proposed SSAR changes for 3.9.3.
4/2/98    Magruder          identification of OITS items closed by WCAP-13054 and WCAP-13559, 4/9/98    Quay              Correction of Figure 11.2-1. Will go into Rev 23.
4/20/98   Sebrosky          Proposed revision for WCAP-13054 to close SRP conformance issue.
4/15/98   Sebrosky-         Proposed SSAR changes to address paint QA.
4/15/98   Sebrosky          Proposed SSAR changes to address ground water.
4/17/98   Huffman           Proposed addition to SSAR reference 51. SSAR subsection 3.8.3.4.2.1.
4/21/98   Sebrosky          Proposed change to WCAP-13054.
4/21/98   Huffman           Proposed SSAR section 5.2.5.2.3.
4/29/98   Wilson            Response to request for ITAAC on 3 second delay.
4/30/98   Sebrosky '        Proposed change to address Tom Cheng question. Will be in Rev 23.
4/27/98   Huffman            Proposed tech spec 3.9.5 and 3.9.6. Request for review.
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5/4/98                                             Wilson         Responses to four I&C issues.
5/7/98                                             Sebrosky       Draft responses to address FSER confirmatory issues.
5/11/98                                            Sebrosky       Advance copy of figures that show shift in MSIV compartment walls.
5/12/98                                            Wilson         Information to supoort meeting.
5/12/98                                             Iluffman       Slides for RTNS3 presentation.
5/13/98                                             11uffman       Revised tech spec 3.9.5 and 3.9.6.
5/15/98                                             Wilson         ITAAC open item responses.
5/18/98                                             Quay           COL item compariron.
l 5/18/98                                              Quay           COL item comparison.
l 5/19/98                                              Wilson         Responses to ITAAC open items.
6/9/98                                               Sebrosky/ Quay Chapter 19 COL item listing for discussion.
6/1/98                                               Wilson         Responses to six open items from 5/21 meeting.
6/5/98                                               Wilson         Proposed definitions to support ITAAC 3.3.
6/10/98                                              Wilson         Discussion points for 2:30 phone call with Jack Roe.
6/10/98                                              Scaletti       Markups from COL item discussion. Will go into Rev 24.
6/12/98                                              Wilson         Response to cable definition issue.
6/15/98                                               Huffman        Revision I to OITS 6786.
6/18/98                                               Wilson         Modification to table 2.5.2-2.
6/1/98                                               Throm          Figures in response to informal question.
4/23/98                                              Wilson         Proposed changes to Building ITAAC.
5/20/98                                              Wilson         Responses to 15 ITAAC OITS items.
i 5/29/98                                              Wilson         Proposed ITAAC to address deformation and critical sections.                                               l 6/2/98                                               Wilson         Proposed changes to SSAR chapter 3 to address ITAAC questions.
5/26/98                                              Wilson         Equipment survivability ITAAC.
6/29/98                                              Wilson         ITAAC OITS responses.
6/24/98                                              Wilsen         Remaining ITAAC open items.
6/24/98                                              Wilson         Proposed responses to 11 ITAAC open items.
6/23/98                                              Sebrosky       Proposed change to SSAR to make drainage from upper anr.ulus consistent in SSAR.
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  !         M Westinghouse                                FAX COVER SHEET D
RECIPIENT INFORMATION                               SENDER INFORMATION DATE:              N} &/2 cel    R / 9 q[            NAME:             $cNE ft/Laj)
TO:                                                   LOCAf.ON:        ENERGY CENTER -
FM/ /d/' 5 PM                                    EAST 3265 PHONE:             FACSIM!LE: [30/) M/f 2 o o z_      PHONE.           Omce: [-bA) 37/. 53f a j COMPANY:                                              Facsimile:       win:          284 4887 MM O - M/2d                                        outside: (412)374-4887 LOCAT10N:          Om= ikirt fiarNurst 0-to bzz l
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l        The fogowing pages are being sent from the Westinghouse Energy Center, East Tower.
l          Monroevule, PA. If any problems occur during this transmission, please call:
654 WIN: 284 5EM (. Bev ) or Outside: (412)374 -6529 l
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!,e T414 i=r 37/g RESPONSES TO NRC REQUEST FOR ADDITIONAL INFORMATION 5:- "5 Question 640.183 Your response to RAI 720.415 is unacceptable. The qualification of instrumentation and equipment required for severe accident mitigation and recovery to operate in the applicable environment must be venfied by an ITAAC.
The demonstration process used to provide reasonable assurance that the instrumentation and equipment will operate include one or more of the following factors: limited time period in or exposure to the environment, the use of similar equipment in commercial industry exposed to a similar environment, the use of analytical extrapolations, the use of vendor performance data, the use of procurement specifications imposed on the vendor, or the results of tests performed in the nuclear industry or at independent laboratones.

===Response===
The Westinghouse response to RAI 720.415 states that the instrumentation and equipment used for mitigation and recovery of severe a'xidents is included in the AP600 Certified Design Material (CDM). The instruments and equipment that is qualified for the hash environment for a Design Basis Accident (DB A) is included in the ITAAC.
The response to RAI 720.415 provides the rationale that concludes this instrumentation and equipment, as qualified for a DB A, is also available for severe accident environments since the environmental qualification used for the DBAs encompasses the environmental conditions of a sesere accident scenario.
The instrumentation and equipment that is qualified for harsh environment is delineated in the equipment tables referenced by the Design Commitments in the Design Description section of the System-based CDM.
I SSAR Revision:
None ITAAC Revision:
None 1
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NRC FSER OPEN ITEM                                                                                                                                   b                                  rwt      g*>4M Ww-L h                            Sh. W5.                                                                                                         ?
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                                                                                                                                                                                                . eY Ouestion: 720.415F (OITS # 5897)
Question 720.415F EOUIPMENT SURVIVABILITY ne instrumentation and equipment required for severe accident mitigation ar.d recovery should be demonstrated to operate in the applicable environment by inspections, tests, and acceptance c.iteria (ITAAC). De demonstration process used to provide reasonable assurance that the instrumentation and eqi.ipment will operate will include one or more of the following factors: lirnited time period in or exposure to the environment, the use of similar equipment in commercial industry exposed to a similar environment, the use of analytical extrapolations, the use of vendor performance data, the use of procurement specifications imposed on the vendcr or the results of tests performed in the nuclear industry or at independent laboratories. His demonstration has not been incorporated into the ITAAC and is an open item.

===Response===
ne PRA has identified the equipment and instrument required for severe accident mitigation, the environment for each location, and the post-event time frames when performance is expected. Installed equipment and instrumentation that may be utilized during a severe accident scenario and exposed to the severe accident environment is qualified for design basis event environments and has been included in the AP600 Certified Design Material (CDM).
An industry test program (EPRI NP-4354) has provided the high confidence discussed in SECY-90-016 that equipment and instrumentation qualified for design basis events will survive the effects of a severe accident and perform satisfactorily. Based on the results of the industry test program and the required performance time frames, it has been determined that the AP600 design basis event qualification programs are sufficient to provide a reasonable j
level of assurance that the required equipment and instrumentation will function during the severe accident time frames specified. Derefore, no special procurement requirements other than the IE qualification program are necessary for equipment expected to perform during severe accidents.
For example, for the Reactor Coolant System (RCS), CDM Section 2.1.2, item 7.a) of the Design Description (DD) states "De Class lE equipment identified in Table 2.1.21 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safery function." Referring to Table 2.1.2-1, the equipment listed includes sensors that have been identified as Class IE, e.g., system pressure from the RCS Wide Range Pressure Sensors and hot leg temperature from the RCS Hot Leg Wide Range Temperature Sensors. Rese same sensors have been identified in the Probabilistic Risk Assessment (PRA) as required for severe accident mitigation and recovery.
Although the Design Commitment is related to a design basis accident scenario, an additional ITAAC for environmental conditions is not required as the environmental envelope for the design basis accident scenario provides reasonable assurance that the same equipment and instrumentation will continue to operate under severe                                                                                           ;
accident conditions.     ,
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NRC FSER OPEN ITEM p:     :==
                                                                                                                                    -=
Thus, an ITAAC for equipment and instrumentation needed for severe accident mitigation and recovery is not required because the same equipment is used during a design basis accident scenario, is already included in the AP600 Certified Design Material, and is identified with respect to Class IE and harsh environment quahfication as a Design Commitment.
SSAR Revision: None PRA Revision: None ITAAC Revision: None l
720.410F-2
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Open item (OITS #6630)
Westinghouse needs to include in CDM Section 1.2, General Provisions, a discussion on what equipment qualification means, i.e., what constitutes qualification for harsh environment, similar to the discussion on the same subject al the CE System 80+ DCD.
Pasponse:
The AP600 iTAAC section 1.1 definition of " Qualified for Harsh Environment" will be revised to provide additional detail.
SSAR Change:
None ITAAC Change:
ITAAC section 1.1 is revised per attachment.
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(L (4 FT              3y          9q NRC FSER OPEN ITEM mt:amme Revl<ed ITAAC Section 1.1 1.0 Introduction 1,1 Definitions The following definitions apply to terms used in the design descriptions and associated inspections, tests, analyses, and acceptance criteria (ITAAC).
Acceptance Criteria means the performance, physical condition, or analysis result for a structure, system, or component that demonstrates that the design commitment is met.
Analysis means a calculation, mathematical computation, or engineering or technical evaluation.
Engineering or technical evaluations could include, but are not limited to, comparisons with operating.
experience or design of similar structures, systems, or components.
As built means the physical propenies of a structure, system, or component following the completion of its installation or construction activities at its final location at the plant site.
Cable means an electrical conductor with or without insulation, or a combination of insulated electrical conductors.
Design Commitment means that ponion of the design description that is verified by ITAAC.
Design Description means that ponion of the design that is cenified.
Division (for electrical systems or equipment) is the designation applied to a given safety-related system or set of components that is physically, electrically, and functionally independent from other redundant sets of components.
Functional Arrangement (for a system) means the major components, interconnections between major components, and connections to other systems that collectively provide the service for which the system is intended and which are described in the design description.
Ileavy Load means a load whose weight is greater than the combined weight of a single spent fuel                                        I assembly and its handling device.
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NRC FSER OPEN ITEM E          1 Type Test means a test on one or more sample components of the same type and manufacturer to qualify other components of the same type and manufacturer. A type test is not necessarily a test of the as-built structures, systems, or components.
UA of a heat exchanger means the product of the heat transfer coefHeient and the surface area.
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NRC FSER OPEN ITEM 1
Inspect or Inspection means visual observations, physical examinations, or reviews of records based on visual observation or physical examination that compare the structure, system, or component condition to one or more design commitments. Examples include walkdowns, configuration checks, measurements of dimensions, or nondestructive examinations.
Inspect for Retrievability of a display means to visually observe that the specified information appears on a monitor when summoned by the operator.
L, is the maximum allowable containment leakage as defined in 10 CFR 50 Appendix J.
Qualified for Harsh Environment means that equipment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of its safety function, for the time required to perform the safety function. Equipment identifed in the Design Description as being Qualipedfor Harsh Environment includes the equipinent itself(including lubricants) and cormected instrumentation, controls and connected electrical corrponents (switches, cabling, niring, and terrrinations) necessary to support operation of the equipment to meet the safety-relatedfunctions identifed in the Design Description to the e.ttent such equipment is located in a harsh emironment during orfollowing a design basis accident.
Safe Shutdown refers to a plant condition where the reactor is subcritical with adequate coolant inventory and core cooling, with a coolant tempera ure less than 420 F.
Safety-related is a classification applied to items relied upon to remain functional during or following a design basis event to provide a safety-related function, Safety-related also applies to documentation and services affecting a safety-related item.
Sensor means a transmitter, resistance temperature detector, thermocouple or other transducer, plus associated cables, connectors, preamplifiers, reference junction boxes, or other signal pnwessing equipment that is located in the immediate proximity of the sensor and subject to the same environmental conditions.
Test means the actuation, operation, or establishment of specified conditions to evaluate the performance or integrity of as-built stmetures, systems, or components, unless explicitly stated otherwise.
Transfer Open (Closed! means to move from a closed (open) position to an open (closed) position.
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                                                     ** TX CONFIRMATION REPORT **                                                                                                        AS OF  MAR 10 '98                                                                           9:53                     PAGE.01 APG00 DESIGN CERT DATE                   TIME                                            T0/FROM                                                             MODE   MIN /SEC PGS                                                                                     STATUS 01             3/10 09:47                                                           301 5042279                                                       G3--S   06*00                       10                                                                    OK l
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M Westinghouse                                FAX COVER SHEET D
RECIPIENT INFORMATION                               SENDER INFORMATION DATE:              M M M /~/, /fi [                   NAME:          M 'PIPu Q TO:                                                   LOCATION:       ENERGY CENTER -
JefM wtusoa                                        EAsr s u, z PHONE:             FACSIMILE: dp/) f 5, geog          PHONE:          Omce. J7/. (J/o COMPANY:                                              Facsimile:      win:           284 4887   i b!M8A [48/72TfudT                              outside: (412)374-4887 {
I LOCATION:          M S O -/ 0 2)2~Z._
Cover + Pages      1+   /
1 The foRowing pages are being sent from the Westinghouse Energy Center, East Tower, Monroevule, PA. If any problems occur during this tronomission, please call:
way WIN: 2844425 ( Bev ) or Outside:(412)374 -6529 COMMENTS:
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O March 17,1998 To: Jerry Wilson, NRC/NRR Jerry, I'm faxing you two versions of the AP600 CDM Section 2.3.10 for the Liquid Radwas'e System, incorporating the agreements we reached in our meeting with you on March 12th.
The first package is a strict application of the meeting agreement, whereby we change the first item in the ITAAC Table 2.3.10-4, deleting the words " applicable portions' and refer to the Design Description portion of Section 2.3.10 to perform the inspection of the functional arrangement. Section 2.3.10 is shown in it's entirety, and includes the addition of the component location Table 2.3.10-5 and notes that we need to make additional changes to the functional arrangement Figure 2.3.10-1.
ne second package is a modified application of the meeting agreements, whereby we believe we meet the intentions of our agreement, but using a different approach.
We have three issues with the strict application of the meeting agreements which reference the Design Description portion of Section 23.10 in the Design Commitment and Acceptance Criteria columns of the ITAAC Table:
: 1) TM reference to the Design Commitment (DC) is still circular, i..e., the DC in the ITAAC refers to DD, which includes the DC, which is in the ITAAC table, etc. We believe this may result in some confusion when the ITAACs are verified.
: 2) lin our approach, the DCs in the Design Description must be the same as in the ITAAC table, therefore, we have lost our reference to the Figure and to the newly added component location table!
: 3) ne verification of the DC in the Acceptance Criteria is open to interpretation and verification may become subjective and therefore, ambiguous.
What we propose instead is shown in the two change pages of our modified proposal:
: 1) To address the issue of the circular argument, we add two subsections to the Design Description section: System Purpose and Design Committnents. Den we include a sentence in the System Purpose that the WLS is desnbed by the Design Commitments given in this Section 2.3.10. His avoids a circular reference and clearly establishes that the DCs embody the system description.
: 2) Item I of the Design Description deletes " applicable portions" and is expanded to include the system location Table.
This picks up the reference to the Figure and the component location Table in the Design Description..
: 3) Using the same DC in the ITAAC table, the Acceptance Criteria includes conformity to the functional arrangement and the component locations.
I We believe that we meet the intention of the meeting agreement to include the Design Description in the functional inspection of the system. He inspection is completed by verifying the functional arrangement, the location of the system components and the DCs themselves , which are the most-significant features of the system.
1 Please provide a copy of this fax to Jim Lyons. I would like to discuss this approach with both of you tomorrow before we proceed with major changes to the AP600 CDM.
Gene i

e AP600 CDM Section 2.3.10. Draft Revison 4
{
With Strict interpretation of Meeting Agreements incorporated i
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LIQUID RADWASTE SYSTEM g=          -
Revision: Craft 4 Applying Strict interpretation of 3/12 Mtg Agreement                                                             ~
Effective: 3/16/98 l
2.3.10 Liquid Radwaste System Design Description l The liquid radwaste system (WLS) receives, stores. processes, samples, monitors, and discharges radioactive wastewater.
l The WLS has components which receive and store radioactive or potentially radioactive liquid I
waste; the Reactor Coolant (RC) Drain Tank and the Containment Sump. Monitoring of the liquid l waste is performed prior to discharge. The WLS components have collection and storage capacity l to process waste volumes expected during normal operation and during anticipated operational
\      l occurrences.
!      I    1.
The functional arrangement cf the app:: cab:c pcnicas of the WLS is shown in Tigam 2.3.31 as l        described in the Design Description portion of this Section 2.3.10.
l l          2. a) The components identified in Table 2.3.10-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
!               b) The piping identified in Table 2.3.10-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.
l l      l        c) The piping identified in Table 2.3.10-2 as ASME Code Section III is designed using the I                 certified seismic design floor response spectra input.
1
: 3. a) Pressure boundary welds in components identified in Table 2.310-1 as ASME Code Section l                         III meet ASME Code Section III requirements.
b) Pressure boundary welds in piping identified in Table 2.3-10-2 as ASME Code Section III meet ASME Code Section III requirements.
l          4. a) The components identified in Table 2.3.10-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
b) The piping identified in Table 2.3.10-2 as ASME Code Section III retains its pressure l                       boundary integrity at its design pressure.
: 5. The seismic Category I equipment identified in Table 2.3.10-1 can withstand seismic design basis loads without loss of safety function.
l          6. a) Each of the lines identified in Table 2.3.10-2 for which functional capability is required meets j                       the requirements for functional capability.
l b) The piping identified in Table 2.3.10-2 as ASME Code Section III is constructed of the material specified.
r 2.3.10-1 MIM                                                                                           c:VTAACSVov4Vt020310.wpf:1t431798 1
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Certified Design Material UQUID RADWASTE SYSTEM                                                                            jar T2 Revision: Draft 4 - Applying Strict interpretation of 3/12 Mtg Agreement                         '
Effective: 3/16/98
: 7. The WLS provides the following safety-related functions:
a) The WLS preserves containment integrity by isolation of the WLS lines penetrating the l                            containment.
b) Check valves in drain lines to the containment sump prevent cross flooding of compartments.
: 8. The WLS provides the nonsafety-related functions of:
a) Detecting unidentified leaks within containment to the containment sump.
b) Controlling releases of radioactive materials in liquid effluents.
: 9. Controls exist in the MCR to cause the remotely operated valve identified in Table 2.3.10-3 to perform its active function.
: 10. The check valves identified in Table 2.3.10-1 perform an active safety related function to change position as indicated in the table.
Inspections, Tests, Analyses, and Acceptance Criteria Table 2.3.10-4 specifies the inspections, tests, analyses, and associated acceptance criteria for the WLS.
2.3.10-2 W6M@0m                                                          oNTAAesvev4wo20310.wpf.ib 03179s

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Ccrtifl:d D:: sign Mct:ri:1 LIQUID RADWASTE SYSTEM                                                                                                                               E=     M Ravision: Draft 4 Applying Strict interpretation of 3/12 Mtg Agreement                                                                               E      $
Effective: 3/16/98 Table 2.3.10 2 Line Name      Line No.      ASME Section 111                                Functional Capability Required WLS Drain from PXS                                      L%2                 Yes                                                  Yes Compartment A WLS Drain from PXS                                       LO63                Yes                                                  Yes Compartment B WLS Drain from CVS                                       LO61                Yes                                                  Yes Companment Table 2.3.10-3 Equipment Name                 Tag No.                                               Control Function WLS Effluent Discharge Isolation                                     WLS-PL-V223                                                    Close Valve 1
2.3.10-4 Ed!lMM                                                                              oNTAACSvev4WO20310.wpf:1b431798 t                                                    _ _ _ _ _ _ _ _ _ _

C;rtifi:d D3 sign Mit:ri:1 LIQUID RADWASTE SYSTEM t=     ~~i Revision: Draft 4 Applying Strict interpretation of 3/12 Mtg Agreement E
Effective: 3/16/98 i
\
'                                                                                                                                                           \
I i
Table 2.3.10-4                                                   l Inspections. Tests, Analyses, and Acceptance Criteria Design Commitment                 Inspections, Tests, Analyses            Acceptance Criteria
{
l l   1. The functional arrangement of      Inspection of the as built system   The as built WLS confaram 2;i           '
l   ec app!;ceMc pcnbas of the            will be performed.                  ec fenc;icaal aireagcn cn; Ac n i    WLS is shown in TW 2.3.10-1                                               h T;;uce 2.3.;0-1 is as described I   as described in the Design                                                in the Design Description l    Description portion of this                                               portion of this Section 2.3.10.
I    Section 2.3.10.
l                                         2.a) The components identified in     Inspection will be conducted of     De ASME Code Section III Table 2.3.10-1 as ASME Code           the as-built components as          design report exists for the as Section III are designed and          documented in the ASME design       built components identified in constructed in accordance with        reports.                            Table 2.3.10-1 as ASME Code
(                                        ASME Code Section IH                                                       Section III.
requirements.
2.b) ne piping identified in          Inspection will be conducted of     De ASME Code Section IH l                                        Table 2.3.10-2 as ASME Code            the as-built piping as documented   design reports exist for the as.
I                                        Section IU is designed and             in the ASME design reports.         built piping identified in constructed in accordance with                                             Table 2.3.10-2 as ASME Code ASME Code Section IH                                                       Section III.                            l requirements.
l    2.c) ne piping identified in           Inspection will be conducted of     An as built ASME Code Section l    Table 2.3.10-2 as ASME Code            the ASME design reports for the     III design report exists and l    Section III is designed using the      piping identified in Table          confirms that the applicable as-l                                   l    certified seismic design floor         2.3.10-2.                           built piping identified in Table l    response spectra.
2.3.10-2 has been designed using I
the certified seismic design floor I
response spectra.
l                                        3.a) Pressure boundary welds in        Inspection of the as built pressure A report exists and concludes that components identified in              boundary welds will be               the ASME Code Section IH Table 2.3.10-1 as ASME Code           performed in accordance with the     requirements are met for non.
Section III meet ASME Code            ASME Code Section III.               destructive examination of Section IH requirements.                                                   pressure boundary welds.
l                                        3.b) Pressure boundary welds in        Inspection of the as-built pressure A report exists and concludes that l                                        piping identified in Table 2.3.10-2'  boundary welds will be               the ASME Code Section III as ASME Code Section III meet         performed in accordance with the     requirements are met for non-ASME Code Section III                 ASME Code Section IH.                destructive examination of requirements.                                                              pressure boundary welds.
2.3.10 5 W6Sdfl@00S8                                                          oNTAACSVev@t020310 wpf;1b o31798 l

C rtifiId Dnign M:tsrir.1
  ^
LIQUID RADWASTE SYSTEM jF   ~;
Revision: Draft 4 Applying Strict interpretation of 3/12 Mtg Agreement
* E!
Effective: 3/16/98
_     e Table 2.3.10 4 (cont.)
Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment                    Inspections, Tests, Analyses                                  Acceptance Criteria 4.a) The components identified         A hydrostatic test will be                          A report exists and concludes that in Table 2.3.10-1 as ASME Code          performed on the components                        the results of the hydrostatic test Section 111 retain their pressure      required by the ASME Code                           of the components identified in boundary integrity at their design     Section III to be hydrostatically                  Table 2.3.10-1 as ASME Code pressure.                               tested.
Section III conform with the requirements of the ASME Code Section Ill.
4.b) The piping identified in          A hydrostatic test will be                         A report exists and concludes that Table 2.3.10-2 as ASME Code             performed on the piping required                    the results of the hydrostatic test Section 111 retains its pressure       by the ASME Code Section III to                    of the piping identified in boundary integrity at its design       be hydrostatically tested.                         Table 2.3.10-2 as ASME Code pressure.
Section III conform with the requirements of the ASME Code Section III.
: 5. The seismic Category I               i) Inspection will be performed to                 i) The seismic Category I equipment identified in                 verify that the seismic Category I                 equipment identified in Table 2.3.10-1 can withstand            equipment identified in                            Table 2.3.10-1 is located on the seismic design basis loads              Table 2.3.10-1 is located on the                   Nuclear Island.
without loss of safety function.        Nuclear Island.
ii) Type tests, analyses, or a                     ii) A report exists and concludes combination of type tests and                      that the seismic Category I analyses of seismic Category I                     equipment can withstand seismic equipment will be performed.                       design basis loads without loss of safety function.
iii) Inspection will be performed                  iii) A report exists and concludes for the existence of a report                      that the as installed equipment verifying that the as-installed                    including anchorage is equipment including anchorage is                   seismically bounded by the tested seismically bounded by the tested                  or analyzed conditions.
or analyzed conditions.
6.a) Each of the lines identified       Inspection will be peifnrmed for                   A report exists and concludes that                                               j in Table 2.3.10-2 for which             the existence of s report                          each of the as built lines                                                       {
functional capability is required       concluding that the as-built lines                 identified in Table 2.3.10-2 for meets the requirements for                                                                                                                                                  !
meets the requirements for                         which functional capability is functional capability.                  functional capability.                                                                                                              {
required meets the requirements for functional capability.
l W   W85tlngt100$8                                                                                                                               2.3.104
                                                             "                                                                                            oN T AAC S\rev4\n020310.wpf: 1 t>C31798 i   _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . __ __                                               _.                                                                                                         ._ _ _ _ . . _ _ .

C;rtift:d D: sign M;t:ri;l LlQUID RADWASTE SYSTEM                                                                                                     E.. .
Revision: Draft 4 Applying Strict interpretation of 3/12 Mig Agreement                                                     "      3 Effective: 3/16/98 Table 2.3.10-4 (cont.)
Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment                  Inspections. Tests, Analyses                Acceptance Criteria 6.b) The piping identified in          Inspection will be performed of        A report exists and concludes that Table 2.3.10-2 as ASME Code            the as-built piping material as        the piping identified in Section 111 is constructed of the     documented in the ASME material         Table 2.3.10-2 ASME Code                             '
material specified.                   reports.                                Section 111 is constructed of the material specified.                                  }
7.a) ne WLS preserves                 See Certified Design Material.          See Certified Design Material, containment integrity by isolation    subsection 2.2.1, Containment           subsection 2.2.1, Containment of the WLS lines penetrating the       Systern.                               System.
containment.
7.b) Check valves in drain lines      Refer to item 10 in this table.         Refer to item 10 in this table.
to the containment sump present cross flooding of compartments.
8.a) The WLS provides the             i) Inspection will be performed         i) Nonsafety.related displays of nonsafety-related function of         for retrievability of the displays of   WLS containment sump level detecting unidentified leaks within    containment sump level channels         channels WLS-034 and WLS-035 -
containment to the containment         WLS-034 and WLS-035 in the              can be retrieved in the MCR.
sump.                                 MCR.
ii) Testing will be performed by        ii) A report exists and concludes adding water to the sump and            that sump level channels observing display of sump level.        WLS-034 and WLS-035 can detect a change of 1.7520.1 inches.
8.b) The WLS provides the             Tests will be performed to              A simulated high radiation signal nonsafety-related function of          confirm that a simulated high           causes the discharge control controlling releases of radioactive    radiation signal causes the             isolation valve materials in liquid effluents.         discharge isolation valve               WLS-PL-V223 to close.
WLS-PL-V223 to close.
: 9. Controls exist in the MCR to        Stroke testing will be performed        Controls in the MCR operate to cause the remotely operated valve      on the remotely operated valve          cause the remotely operated valve identified in Table 2.3.10-3 to        listed in Table 2.3.10-3 using          to perform its active safety perform its active function.           controls in the MCR.                    function.
: 10. He check valves identified        Exercise testing of the check           Each check valve changes in Table 2.3.10-1 perform an           valves active safety functions          position.
active safety.related function to      identified in Table 2.3.10-1 will change position as indicated in        be performed.
the table.
2.3.10-7 W85tingtI00$8 o:uTAAesirev4'uto20310.wpt:1b.o31798

-__                  __--_ - --_--- ------ - - - - - - - - -                                                   ~        ~-        -
A Certified Dasign Materisi
    ~
LIQUID RADWASTE SYSTEM 155 =;
Revision: Draft 4 - Applying Strict interpretation of 3/12 Mtg Agreement
* E Effective: 3/16/98 l
Table 2.3.10 5 l
I                                                                                                                 Component Component Name                               l'ag No.                  Location I                             WLS Drainfrom Passive Core Cooling System                WLS PL-V071B               Containment l                           (PXS) Compartment A Check Valve l                            WLS Drainfrom PXS Compartment A Check Valve               WLS-PL-V072B               Containment i                             WLS Drain from PXS Compartment B Check Valve              WLS PL-V071C               Containment l                            WLS Drain from PXS Compartment B Check Valve                                                             l WLS-PL-VO72C               Containment       \
l WLS Drainfrom Chemicaland Volume Control                    WLS-PL- V071A              Containment l                          System (CVS) Compartment Check Valve l                           WLS Drain from CVS Compartment Check Valve WLS-PL-V072A              Containment l
I                           WLS Effluent Holdup Tanks fBD                   Auxilliary Building WLS Waste Holdup Tanks f        TBD      )       Auxilliary Building I                            WLS lon Exchangers
(        TBD    l         Auxilliary Building l                           WLS Monitor Tanks                                                   TW               Auxilliary Building l                          WLS Effluent Discharge isolation Valve
                                                                                                /        WLS PL V223           Auxilliary Building i
ru s               naa             mei
[ W85tlDgh0US8                                                                                              2.3.10-8 o:VTAACSvev4w020310 wpf:1b431798

Certifisd D: sign Metarl:1 1.10U10 RADWASTE SYSTEM Revision: Draft 4. Applying Strict interpretation of 3/12 Mtg Agreement d
si Effective: 3/16198 1
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                                                                                   >-                                               Figure 2.3.101 e      e          I                     Liquid Radwaste System 2.3.10-9 c:VTAACSVev4Vt020310 wpt:1b431798

t AP600 CDM Section 2.3.10, Draft Revison 4 With Westinghouse proposed modifications to 3/12 meeting agreements (Change Pages Only!)
l l
l l
l l
I w                                                     _ _ - - _ - _ . - - _ - _ _ _ - _ . _ - . _ _ _ . _ _ _ . _ . - _ _ - - - _ - _ . . . - _ - _ _   ._ _ . _ - - - _ _ . _  _ -_ _ _ _ _ _ - _ _ .

R CartifiId DI:ign Mit:ri;l LIQUID RADWASTE SYSTEM jii" "g Revision: Draft 4 - Modified to incorporate reference to DCs, Figure and Location                       =
Effective: 3/16/98                                                                              _
2.3.10 Liquid Radwaste System Design Description l System Purpose l The liquid radwaste system (WLS) receives, stores, processes, samples, monitors, and discharges radioactive wastewater.
l The WLS has components which receive and store radioactive or potentially radioactive liquid
    \ waste; the Reactor Coolant (RC) Drain Tank and the Containment Sump. Monitoring of the liquid l waste is performed prior to discharge. The WLS components have collection and storage capacity l to process waste volumes expected during normal operation and during anticipated operational I occurrences.
I 1 The WLS is described by the Design Commitments portion of this Section 2.3.10.
l Design Commitments l    1. The functional arrangement of thc epp!!cabic pes;en; of the WLS is as shown in Figure 2.3.10-1 l        and the component locations of the WLS are as shown in Table 2.3.10-5.
: 2. a) The components identified in Table 2.3.10-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.
b) The piping identified in Table 2.3.10 2 as ASME Code Section III is designed and constmeted in accordance with ASME Code Section III requirements.
I        c) The piping identified in Table 2.3.10-2 as ASME Code Section III is designed using the I            certified seismic design floor response spectra input.
: 3. a) Fressure boundary welds in components identified in Table 2.310-1 as ASME Code Section III meet ASME Code Section III requirements.
b) Pressure boundary welds in piping identified in Table 2.3-10-2 as ASME Code Section III meet ASME Code Section III requirements.
: 4. a) The components identified in Table 2.3.10-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.
l l            b) The piping identified in Table 2.3.10-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.
: 5. The seismic Category I equipment identified in Table 2.3.10-1 can withstand seismic design basis loads without loss of safety function.
l t
2.3.10-1 W8Mi$0088                                                    c:uTAAcssrev4;ito20310 wpt:ib.031798

l
  .                                                                                                   Csrtiflid Dxign M;t:ri;l LIQUID RADWASTE SYSTEM h
j Revision: Draft 4 - Modified to incorporate reference to DCs, Figure and Location                                   ut Effective: 3/16/98                                                                                          _
Table 2.3.10-4 Inspections, Tests Analyses, and Acceptance Criteria                                       1 Design Commitment                Inspections, Tests, Analyses                 Acceptance Criteria l    1. He functional arrangement of     Inspection of the as built system       he as-built WLS conforms with           1 l   the applicabic paracra of the        will be performed,                      the functional arrangement shown l   WLS is as shown in                                                                                                   l in Figure 2.3.10-1 and the l
l   Figure 2.3.10-1 and the                                                      as-built WLS components are             !
I   component locations of the WLS                                               located as shown in Table l   are as shown in Table 2.3.10 S.                                              2.3.10-S.
2.a) ne components identified in     Inspection will be conducted of         ne ASME Code Section III Table 2.3.10-1 as ASME Code          the as-built components as              design report exists for the as Section III are designed and         documented in the ASME design           built components identified in constructed in accordance with       reports.                                Table 2.3.10-1 as ASME Code ASME Code Section III                                                        Section Ill.
requirements.
2.b) The piping identified in        Inspection will be conducted of         The ASME Code Section III Table 2.3.10-2 as ASME Code           the as-built piping as documented       design reports exist for the as-Section III is designed and          in the ASME design reports.             built piping identified in constructed in accordance with                                                Table 2.3.10-2 as ASME Code             !
ASME Code Section III                                                         Section III.
requirements.
I   2.c) ne piping identified in          Inspection will be conducted of         An as-built ASME Code Section l   Table 2.3.10-2 as ASME Code           the ASME design reports for the         III design report exists and l   Section III is designed using the     piping identified in Table              confirms that the applicable as-I   certified seismic design floor        2.3.10-2.                               built piping identified in Table l   response spectra.                                                             2.3.10-2 has been designed using I                                                                                 the certified seismic design floor I                                                                                 response spectra.
3.a) Pressure boundary welds in       Inspection of the as-built pressure     A report exists and concludes that components identified in              boundary welds will be                  the ASME Code Section III Table 2.3.10-1 as ASME Code           performed in accordance with the        requirements are met for non-Section III meet ASME Code            ASME Code Section III.                  destructive examination of Section III requirements,                                                     pressure boundary welds.
3.b) Pressure boundary welds in ,     Inspection of the as built pressure     A report exists and concludes that piping identified in Table 2.3.10-2   boundary welds will be                  the ASME Code Section III as ASME Code Section III meet         performed in accordance with the        requirements are met for non-ASME Code Section III                 ASME Code Section III.                  destructive examination of requirements.                                                                 pressure boundary welds.
2.3.10-5 W8Stiflg!)00S8 o:\iTAAcssrev4sno20310.wpt:1b4317ss

FAX COVER SHEET W          Westinghouse RECIPIENT INFORMATION                               SENDER INFORMATION DATE:                3/If[9[                           Name:             5ee    F u +o TO:                   Tom      Ke.q q o q               LOCATION:        ENERGY CENTER - EAST 3oI[iif-()Lo PHONE:                                                  PHONE:
Office: 412-374 Yo A.Y COMPANY:                                                Facsimile:       win:        284-5535 b kf-.-                                        outside: (412)374-5535 LOCATION:
Cover + Pages       1+       [o The following pages are being sent from the Westinghouse Energy Center, East Tower, Monroeville, PA. If any problems occur during this transmission, please call:
WIN: 284-5489 (Wanda)/4031 (Delina) or Outside (412)374-5489/4031.
COMMENTS:
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                                                                       ,h7 y e P5 9 .' r'';- pP    .i i
       .                    7. Instrumentation rad Controls            {n,) j j f^{ j .,'"      j
                                                                                = . _ ... &                                                          ,
The control cabinets perform nonsafety-related instmmentation and contml functions using both discrete (on/off) and modulating (analog) type ztuation devices.
The nonsafety-related monitor bus, which horizontally doides the figure, is a high speed.                     <
redundant communications network that links systems of importance to the operator.
Safety-related systems are connected to the monitor bus through qualified isolation duices so that their functions are not compromised by failures elsewhere.
Plant protection, control, and monitoring systems feed real-time data into the bus for use by the control room and the computer system.
The upper portion of the figure depicts the control rooms and distributed computer system.
De main control room is implemented as a set of compact operator consoles featuring color graphic displays and soft control input devices. The graphics are supponed by a set of microprocessor-based graphics workstations that take their input from the monitor bus. An advanced alarm system, implemented in a similar technology, is also provided.
The computer system is implemented in a distributed architecture. The working elements of the distributed computer system are graphics workstations, although their graphics capability is secondary to their computing performance. The distributed computer system obtains its input hem the monitor bus and delivers its output over the bus to other users.
There is another grouping of the systems shown on this figure. They are the seven sets of systems enclosed by the dotted line boxes. These are groups of systems that share similar characteristics, making it convenient to treat them together in this document. These systems are the following:
Pmtection and safety monitoring system
* Special monitoring system
* Plant contml system
* Operations and control centers system
* Diverse actuation system Data display and processing system AQ
* Incore instrumentation system I            WCAP-13633 (Reference 12) describes the diversity and defense-in-depth features of the I           AP600 instrumentation and contml architecture.
                                                             -p                     _-        -
y Protection and Safety Monitoring System The protection and safety monitoring system provides the safety-relarut functions necessary to contml the plant during normal operation, to shutdown the plant, and to maintain the plant in a safe shutdown condition. The protection and safety monitonng system controls safety-related components in the plant that are operated from the main contml room or remote shutdown workstation.
Revision:
T Westhghouse                                       7.1-3

RE Eiij
.              T                                                                7. Instrumentation cod Controts nmq Eq;ipment is environmentally qualified to meet the accidcat conditions through which it operates to mitigate the consequences of the accident. Equipment is seismically qualified to meet design basis earthquake levels.
De digital equipment design has additional design margin to accommodate a loss of the normal HVAC. Safety-related digital equipment is protected by the passive HVAC upon any failure or degradation of the active HVAC. He passive HVAC limits the rate of temperature rise in the rooms containing the digital equipment. De cabinets containing the digital equipment are provided with temperature sensors which pmvide an alarm if intemal cabinet temperatures reach an excessive value. In addition, the equipment is qualified at a temperature which envelope the worse case temperature for which the equipment must continue to function. Details of the equipment design are provided in WCAP-13382 (Reference 3).
Electromagnetic design, testing, and qualification of the digital equipment is performed in accordance with guidance provided in the following standards:
Electrostatic discharge (ESD) immunity in accordance with EC 1000 4-2 Radio frequency interference (RFI) immunity in accordance with EC 1000-4-3 and MIL-STD-461C and MIL-STD-462 Electrical fast transient (EFT) immunity in accordance with EC 1000-4-4                  i Surge immunity in acconiance with EC 1000-4-5, IEEE C62.45-1992, and ANSI /IEEE C37.90.1-1989 RFI emission in accordance with MIL-STD-461C and MIL-STD-462 Conducted RFI immunity in accordance with MIL-STD-461C and MIL-STD-462 b]
* Groundmg and shielding in accordance with EEE 1050-1989
                                                 +           -
                                                                   -       -- =             :
l l
An example of the manner in which these standards are used in the testmg of the digital l       L
           \ equipment
                 .          is provided in WCAP-11340             (Reference
                                                                        - __ 11).
u%vy                          __ M De design conforms to Paragraphs 4.3,4.4, and 4.5 of EEE 279-1971. Conformance is dienewd in subsections 7.1.4.2.3 through 7.1.4.2.5.
l l
7.1.4.1.7    Design Basis: Prtdection Against Equipment Malfuncticars 1
ne ability of the safeJy-related system to initiate and accomplish protective functions is maintamed despite credible equipment malfunctions within the safety-related system. De safety system meets the single failure criterion. De following specific design bases apply:
Revision:
7.1-36                          T Westinghouse

e i       7. Instrrm=tation end Controls 7.1.6        Combined License Information Combined License applicants referencing the AP600 certified design will provide a calculation of setpoints for protective functions consistent with the methodology presented in Reference 9.
7.1.7        References
: 1. EEE 603-1991, "EEE Criteria for Safety Systems for Nuclear Power Generator Stations."
: 2. EEE 796-1983, "EEE Microcomputer System Bus."
: 3. WCAP-13382 (P), WCAP-13391 (NP), "AP600 Instrumentation and Contml Hardware Description."
: 4. WCAP-13383 Revision 1 (NP), "AP600 Instmmentation and Control Hardware and Software Design, Verification, and Validation Process Report."
: 5. EEE 279-1971, "IEEE Criteria for Protection Systems for Nuclear Power Generating Stations."
: 6. EEE 384-1981, "EEE Criteria for Independence or Class IE Equipment and Circuits."
: 7. WCAP-8897 (P), WCAP-8898 (NP), " Bypass Logic for the Westinghouse Integrated Protection System."
: 8. WCAP-14080 (P), WCAP-14081 (NP), "AP600 Instmmentation and Control Software Architecture and Operation Description," Revision 0.
: 9. WCAP-14605 (P), WCAP-14606 (NP), " Westinghouse Setpoint Methodology for D                  Protection Systems, AP600."                                                                   l I              10. 10 CFR 21 " Reporting of Defects and Noncompliance."
f                                w I               11. WCAP-11340 (P), " Noise, Fault, Surge, and Radio Frequency Interference Test Report."
l                                                                                                                 l I               12. WCAP-13633(P),WCAP-13634(NP),"AP600InstmmentationandControlDefense-in-l                     Depth and Diversity Report."
                                                                           ^              -
Revision:
3 Westhghouse                                       7.1-49

a
: 7. Instrumentation cod Controls Condition 1 results from the coincidence of pressurizer pressure below the Low setpoint in any two of the four divisions.
Condition 2 results from the coincidence of two of the four divisions of compensated steam line pressure below the Low setpoint in either of the two steam lines. The steam line pressure signal is lead-lag compensated to improve system response.
Condition 3 results from the coincidence of two of the four divisions of reactor coolant system cold leg temperature below the Low setpoint in any loop.
Condition 4 results from the coincidence of two of the four divisions of containment pressure l               above the High-2 setpoint.
Condition 5 consists of two momentary controls. Manual actuation of either of the two controls will trip the reactor and generate a safeguards actuation signal.
To permit startup and cooldown, the safeguards actuation signals generated from low pressurizer pressure, low steam line pressure, or low reactor coolant irjet temperature can be manually blocked when pressudzer pressure is below the P-11 setpoint. 'Ihe signal is automatically unblocked when the pressurizer pressure is above the P-11 setpoint.
Separate momentary controls are provided, each of which will manually reset the safeguards actuation signal in a single division. Manual reset of a safeguards actuation signal in coincidence with reactor trip (P-4) blocks the safeguards actuation signal. Absence of P-4 automatically resets the blocking function. 'Ihe safeguards actuation signal is manually reset basal on a preset delay following initiation. Resetting the signal does not reposition any safeguards actuated equipment, since individual components are required to latch in and seal Mg                         on the safeguards actuation signal.
In addition to actuating safety related functions, a safeguards actuation signal also resets the pressurizer level control setpoint and blocks pressurizer heater operation.
The logic relating to the development of the safeguards actuation signal is illustrated in Figure 7.2-1, sheets 9 and i1.
7.3.1.2      Engineered Safety Feature Descriptions The followmg subsections provide a functional description of the signals and initiating logic for each engmeered safety feature. Table 7.3-1 lists tle signals and summanzes the coincidence logic used to generate the safeguards actuation signal or initiate each engineered safety feature. Table 7.3-2 describes the pennissives and intedocks relating to the engineered    ,
safety features. Table 7.3-3 lists the system level manual input to the engineered safety         !
feature-l Revision:
y Westhghouse                                       7.3-3                                                     l

T
: 7. Inst.rumrtation cod Controls 7.3.1.2.21 Spent Fuel Pool Isolation A signal for isolating the spent fuel pool lines is generated upon the coincidence of spent fuel poollevel below the Low setpoint in two of three divisions. His helps to maintain the water inventory in the spent fuel pool due to line leakage. De functional logic relating to this is illustrated in Figure 7.2-1, sheet 13.
l            7.3.1.2.22 Chenscal and Volume Control System Letdown Isolation i
A signal to isolate the letdown valves of the chemical and volume control system is generated i                upon the occunence of a Low-l hot leg level in either of the two hot leg loops. This helps l                         to maintain reactor system inventory. He functional logic relating to this is illustrated in
{
l Abb q                   Figure 7.2-1, sheet 16. Dese letdown valves are also closed by the contamment isolation function as described in subsection 7.3.1.2.1.
l                  L                              _
,       1   7.3.1.2.23 Pressurizer Heater Block l
l l                                                                                                             D Signals for blocking the operation of the pressurizer heaters are generated from any of the         f l                  following conditions:
[
l                  1. Core makeup tank injection alignment signal (subsection 7.3.1.2.3) i i     l                   2. High-3 pressurizer water level k  I i     i l
                \i        Division A of the protection and safety monitoring system pmvides actuation signals to five load center ci."mit breakers which provide the power feed to five pitssurizer heater electrical        k l
I control centers. When these five power feed breakers are opened, all electrical power is               j f      removed form ali pressurizer heaters. In addition, Division C of the protection and safety               j
                                                                                                                                    )
l    l l
monitonng system provides a separate signal to the plant control system. His separate signal l    I                   is used to command the plant control system to open the molded-case circuit breakers which l   l                    provide a power feed to each individual pressurizer heater. His arrangement provides for i               !    complete blockmg of the pressurizer heaters, even if a single component failure occurs.
l   I
!   l                    ne functional logic relating to the pressurizer heater block is illustrated in Figure 7.2-1, l   l                    sheets 6 and 12.                                 _             _ _ _ _
l                                        f                                       -
7.3.1.3       Blocks, Permissives, and Interlocks for Engineered Safbty Features Actuation he intedo::ks used for engineered safety features actuation are designated as "P-xx" permissives and are listed in Table 7.3-2.
7.3.1.4      Bypasses of Engineered Safety Features Actuation i
7he channels used in engineered safety features actuation that can be manually bypassed are indicated in Table 7.3-1.         A description of this bypass capability is provided in subsection 7.1.2.10. De actuation logic is not bypassed for test. During tests, the actuation i
Revision:
Y W85thgh00se                                       7.3-19

g
: 7. Instrumentation tod Controls Table 7.3-1 (Sheet 8 of 8)
ENGINEERED SAFETY FEATURES ACTUATION SIGNALS No. of Channels /         Actuation Actuation Signal              Switches             Logic            Permissives and Interlocks
: 22. Open IRWST Containment Recirculation Valves In Series with Check Valves (Figure 7.21, Sheet 15)
: a. Enended undervoltage to          2/ charger      1/2 per charger                   None Class IE battery chargers
* and 2/4 charger
: 23. Open All IRWST Containment Recirculation Valves (Figure 7.21, Sheet 16)
: b. Safeguards actuation                            (See items la through le) signal (automatic or manual) coincident with DcMe.$ pag                               Low IRWST lev                       4              2/4 BYP                       None NSL ~Td
                                           @w-3 setpob DeQ egyof {g Mg(e,                             4
: c. Manualinitiation               4 switches         2/4 switches                 _
None        gg N
24.
Chemical and Volume Control System Letdown Isolatio(Figure 7.2-1, Sheet 16)                  rio{ Q g
: a. Low-1 hot leg level             1 per loop             1/2                        None l
2S. Pressurizer Hester Block (Figure 7.2-1, Sheets 6 and 12) \
l     . a. Core makeup tank                                 (See items 6a through 6e)           N l            injection I        b. High-3 pressurizer level              4             2/4 BYP'        Manual block permitted below P-19      i I
Automatically unblocked above P-19 j
                               &ls
: 1. 2/4-BYP indicates automatic bypass logic. "Ihe logic is 2 out of 4 with no bypasses: 2 out of 3 with one bypass:
1 out of 2 with two bypasses; and. automatically actuated with three or four bypasses.
: 2. Any two channels from either tank not in same division.
: 3. Two switches must be actuated simultaneously.
: 4. Also. closes power-operated relief block valve of respective steam generator.
: 5. The two-out-of-four logic is based on undervoltage to the battery chargers for divisions A or C coincident with an undervoltage to the battery chargers for divisions B or D.
: 6. Any two channels from either loop not in same division.
: 7. Any two channels from either line not in same division.
Revision:
7.3-34                                T Westinghouse

'4 l
l                                  March 20,1998 i
                                 'To:                Jerry Wilson NRR Jerry, Attached are the following proposed changes to the AP600 CDM:
: 1)               A revised definition for the Functional Arrangement of a system in Section 1.1, Definitions, page 1.0-1.
: 2)                A revised legend for the figures under " Miscellaneous" in Section 1.3, Figure Legend, page 1.0 8.
: 3)                A revised Section 2.3.10, Liquid Radwaste System, pages 2.3.10-1 through 2.3.10-9 l believe we have incorporated the agreements of the March 12th meeting and as we discussed on our telecon yesterday.
Please note we have made some revisions to the narrative of the Design Description in Section 2.3.10 to better describe the intended function of the WLS. We also now refer to the Figure and Component Location Table in this section.
l                                The first item in the ITAAC taole is the inspection of the functional arrangement with reference to the Section as we agreed.                                                            l Also, we prefer that the Component Location Table controls the location of the components and not the figure. The figure shows the functional arrangement of the components and whether the system crosses any important boundary, such as the containment. Therefore, the figure shows IRC and ORC as originally proposed.
Please call me on Monday as to whether this format is acceptable to the staff.
Thanks, l                                                                                                                                   i Gene

INTRODUCTION                                                                                            ss =
Revision:                                                                                               F 4'Dredi,,(/q1 Effective: Wia&dGE 1/se                                                                                  _
1,0 Introduction 1.1 Definitions The following definitions apply to terms used in the design descriptions and associated inspections, tests, analyses, and acceptance criteria (ITAAC).
Acceptance Criteria means the performance, physical condition, or analysis result for a structure, system, or component that demonstrates that the design commitment is met.
Analysis means a calculation, mathematical computation, or engineering or technical evaluation.
Engineering or technical evaluations could include, but are not limited to, comparisons with operating experience or design of similar structures, systems, or components.
As-built means the physical properties of a structure, system, or component following the completion of its installation or construction activities at its final location at the plant site.
Cable means an electrical conductor with or without insulation, or a combination of insulated electrical conductors.
Design Commitment means that ponion of the design description that is verified by ITAAC.
Design Description means that portion of the design that is certified.
Division (for electrical systems or equipment) is the designation applied to a given safety related system or set of components that is physically, electrically, and functionally independent from other redundant sets of components.
I Functional Arrangement (for a system) means the major conipcncnts, intcccenncctions bctv.ccn I major cenipcacnts, end connccGcn; te ceci ays;cni; sa; ccllcctivcly physical arrangement of I structures, systems, and components to provide the service for which the system is intended and which are described in the design description.
Heavy Load means a load whose weight is greater than the combined weight of a single spent fuel assembly and its handling device.
Inspect or Inspection means visual observations, physical examinations, or reviews of records based on visual observation or physical examination that compare the structure, system, or component condition to one or more design commitments. Examples include walkdowns, configuration checks, measurements of dimensions, or nondestructive examinations.
Inspect for Retrievability of a display means to visually observe that the specified information appears on a monitor when summoned by the operator.
L, is the maximum allowable containment leakage as defined in 10 CFR 50 Appendix J.
i Wam Westinghouse                                                           m:\ap600\lTAACS\rev3\rt01.wpf:032098

Certified Design Material l INTRODUCTION Ere Revision: /I Dr*N N                                                                                                     5 Effective: E444W97 *)/34/t)
MJSCfLLANEOUS A component that is part of the system functional arrangement shown on the figure and is included in the design commitments for the system.                                 b80M Db k.
A component that is part of the p - - - - - _                  _.g.
Cogpg          g system functional arrangement shown                 _ , , , , _                                    l_ _ ,
on the figure.
l g,                              l L__g______J A system or component that is not                                    ~ " " -
part of the system functional                                     g~b W ' A ""--""""'-M bM*W NW arrangement shown on the figure.                    _ , ,!                                          l l   SV WTM h C.A4any e4           I"" - -
A functional connection to another r      - - -- - - -- -            1 system that is not part of the system                                              S V fv"r M
                                                                              ,,,,,,,,,_4 functional arrangement shown on the                                           r   4 cdsu yM figure.
ASME CODE CLASS BREAK An ASWE Code class break is identified by a single line to the designated location for the class break, os shown in the example below (see note 1).
IAsuc coot san 0N 5 CMSSl k!]
I                 X                                   N                            :
NOTES:
: 1. The beoder, 'ASWE Code Section til Class *, must appear at least once on each figure on which ASME class breaks are shown, but need not appear at every class break shown on o fqure.
                 @ Indicates Non-ASWE Code Section Il T Wed@0use                                                                             m:wpsoouTAAesvevuoi.wpt:osboss

Ccrtift:d Drign M;t;ri;l Ll2UID RADWASTE SYSTEM                                                                                 F-      -
Revision: Draft 4                                                                                      -
Effective: 3/20/98                                                                                       _
2.3.10 1lquid Radwaste System Design Description i The liquid radwaste system (WLS) receives stores, processes, samples, monitors, and discharges radioactive wastewater.
l The WLS has components which receive, process and store radioactive or potentially radioactive l liquid wastefrom the Reactor Coolant (RC) Drain Tank, the Containment Sump and the Auxiliary i Building Sump expected during normal operation and during anticipated operational occurences.
I ofonitoring of the liquid waste is also performed prior to discharge.
l The WLS is as shown in Figure 2.3.101 and the component locations of the WLS are as shown in l Table 2.3.10 5.
I    1. The functional arrangement of the applicabic pcr;icas cf ;he WLS is as shown la Tlgurc 2.2.10-1 I         described in the Design Description of this Section 2.3.10.
: 2. a) The components identified in Table 2.3.10-1 as ASME Code Section 111 are designed and constructed in accordance with ASME Code Section III requirements.
b) The piping identified in Table 2.3.10-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.
I         c) The piping identified in Table 2.3.10-2 as ASME Code Section III is designed using the l             certified seismic design floor response spectra input.
: 3. a) Pressure boundary welds in components identified in Table 2.310-1 as ASME Code Section III meet ASME Code Section III requirements.
b) Pressure boundary welds in piping identified in Table 2.3-10 2 as ASME Code Section III meet ASME Code Section III requirements.
: 4. a) The components identified in Table 2.3.10-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.                                                               l b) The piping identified in Table 2.3.10-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.
: 5. The seismic Category I equipment identified in Table 2.3.10-1 can withstand seismic design basis loads without loss of safety function.
: 6. a) Each of the lines identified in Table 2.3.10-2 for which functional capability is required meets the requirements for functional capability.                                                               l 2.3.10-1 j                                                         D                                                                    o:\lTAACsvev4\no20310.wpt:1t432098  l l
1

e C:rtifi:d Dxign M tsrirl LIQUID RADWASTE SYSTEM                                                                                                                              djs      ==
Revision: Draft 4                                                                                                                                   =               =
Effective: 3/20/98                                                                                                                                   _
b) The piping identified in Table 2.3.10-2 as ASME Code Section III is constructed of the material specified.
: 7.                            The WLS provides the following safety related functions:
a) The WLS preserves containment integrity by isolation of the WLS lines penetrating the containment.
b) Check valves in drain lines to the containment sump prevent cross flooding of compartments.
: 8.                            The WLS provides the nonsafety-related functions of:
a) Detecting unidentified leaks within containment to the containment sump.
b) Controlling releases of radioactive materials in liquid effluents.
: 9. Controls exist in the MCR to cause the remotely operated valve identified in Table 2.3.10-3 to perform its active function.
: 10. The check valves identified in Table 2.3.10-1 perform an active safety related function to change position as indicated in the table.
Inspections, Tests, Analyses, and Acceptance Criteria Table 2.3.10-4 specifies the inspections, tests, analyses, and associated acceptance criteria for the WLS.
2.3.10-2 l
MhM                                                     o:VT AACSvev4Vt020310.wpf.1 b-032098

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I                                                                                                                i C rtifi d D:cign Mitari:1 LIQUID RADWASTE SYSTEM                                                                     a     =g Revision: Draft 4                                                                                  =
l Effective: 3/20/98                                                                          _        .
l Table 2.3.10 2 Line Name               Line No.       ASME Section III  Functional Capability Required WLS Drain from PXS               LO62                Yes                     Yes Compartment A WLS Drain from PXS               LO63                Yes                     Yes Compartment B WLS Drain from CVS               LM1                 Yes                     Yes Compartment Table 2.3.10-3 l
Equipment Name                           Tag No.                 Control Function             8 WLS Effluent Discharge Isolation              WLS-PL-V223                     Close                  i Valve 1
i t
2.3.10-4 MIM                                                         o:VTAACSvev4WO20310.wpt:1b 032098 l
u____-_____

6 Certifisd Design Mstarial '
LIQUID RADWASTE SYSTEM                                                                                       == m     i Revision: Draft 4                                                                                            ~
Effective: 3/20/98 Table 2.3.10-4 Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment                  Inspections. Tests. Analyses             Acceptance Criteria l    I. The functional arrangement of       Inspection of the as built system  The as built WLS conforms with I   ec cpplicebic peruca; cf ;hc            will be performed.                  the functional arrangement shown l   WLS is as sown in                                                           in I;ga 2.3.1^ l as described in l   r;g.ic 2.3.1% described in the                                             the Design Description Portion I   Design Description portion of this                                         of this Section 2.3.10.
l   Section 2.3.10.
2.a) De components identified in        Inspection will be conducted of    The ASME Code Section III Table 2.3.10-1 as ASME Code             the as-built components as         design report exists for the as Section III are designed and           documented in the ASME design       built components identified in constructed in accordance with         reports.                            Table 2.3.10-1 as ASME Code ASME Code Section III                                                      Section III.
requirements.
2.b) The piping identified in          Inspection will be conducted of     he ASME Code Section III Table 2.3.10-2 as ASME Code             the as-built piping as documented   design reports exist for the as-Section III is designed and             in the ASME design reports.         built piping identified in constructed in accordance with                                              Table 2.3.10-2 as ASME Code ASME Code Section III                                                       Section III.
requirements.
I    2.c) De piping identified in            Inspection will be conducted of    An as-built ASME Code Section i    Table 2.3.10-2 as ASME Code             the ASME design reports for the     III design repon exists and l    Section III is designed using the      piping identified in Table          confirms that the applicable as-I    certified seismic design floor         2.3.10-2.                           built piping identified in Table I    response spectra.
2.3.10-2 has been designed using l
the cenified seismic design floor I
response spectra.
3.a) Pressure boundary welds in        Inspection of the as-built pressure A repon exists and concludes that components identified in               boundary welds will be              the ASME Code Section III Table 2.310-1 as ASME Code             performed in accordance with the    requirements are met for non-Section III meet ASME Code             ASME Code Section III.              destructive examination of Section III requirements.                                                  pressure boundary welds.
3.b) Pressure boundary welds in        Inspection of the as-built pressure A repon exists and concludes that piping identified in Table 2.3.10-2     boundary welds will be              the ASME Code Section III as ASME Code Section III meet           performed in accordance with the    requirements are met for non-ASME Code Section III                   ASME Code Section III.              destructive examination of requirements.                                                               pressure boundary welds.
MIM                                                                                                 2.3.10 5 c :\lT AAC Sirov4\it020310.wpf: 1 t432096

I Csrtifisd Dssign Material LIQUID RADWASTE SYSTEM                                                                                      =       "=
Revision: Draft 4                                                                                                    =
Effective: 3/20/98                                                                                           _
Table 2.3.10 4 (cont.)
Inspections, Tests, Analyses, and Acceptance Criteria l               Design Commitment                     inspections. Tests, Analyses          Acceptance Criteria               5 4.a) The components identified         A hydrostatic test will be         A report exists and concludes that in Table 2.3.10-1 as ASME Code         performed on the components        the results of the hydrostatic test Section III retain their pressure      required by the ASME Code          of the components identified in boundary integrity at their design     Section III to be hydrostatically  Table 2.3.101 as ASME Code pressure.                              tested.                            Section ill conform with the requirements of the ASME Code Section III.
4.b) The piping identified in          A hydrostatic test will be         A report exists and concludes that Table 2.3.10-2 as ASME Code            performed on the piping required   the results of the hydrostatic test Section III retains its pressure       by the ASME Code Section III to    of the piping identified in boundary integrity at its design       be hydrostatically tested.         Table 2.3.10-2 as ASME Code pressure.                                                                 Section III conform with the requirements of the ASME Code Section III.
: 5. The seismic Category I              i) Inspection will be performed to i) "Ihe seismic Category I equipment identified in                verify that the seismic Category I equipment identified in Table 2.3.10-1 can withstand           equipment identified in            Table 2.3.10-1 is located on the seismic design basis loads             Table 2.3.10-1 is located on the   Nuclear Island.
without loss of safety function.       Nuclear Island.
ii) Type tests, analyses, or a     ii) A report exists and concludes cornbination of type tests and     that the seismic Category I analyses of seismic Category I     equipment can withstand seismic equipment will be performed.       design basis loads without loss of safety function.
iii) Inspection will be performed  iii) A report exists and conclu6s for the existence of a report      that the as installed equipment verifying that the as installed    including anchorage is equipment including anchorage is   seismically bounded by the tested seismically bounded by the tested  or analyzed conditions.
or analyzed conditions.
6.a) Each of the lines identified         Inspection will be performed for   A report exists and concludes that in Table 2.3.10-2 for which              the existence of a report          each of the as built lines functional capability is required         concluding that the as-built lines identified in Table 2.3.10-2 for meets the requirements for                 meets the requirements for         which functional capability is functional capability.                    functional capability,             required meets the requirements for functional capability.
2.3.10-6 M fl@ 00S8                                                           o:\irAAcssrev4sno20310.wpt:1643209a

Certifisd Dssign Matsrial LIQUID RADWASTE SYSTEM                                                                                       E=-   ~;;
Revision: Draft 4                                                                                                   5 Effective: 3/?0/98                                                                                            _
Table 2.3.10 4 (cont.)
l                                Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment                   inspections. Tests, Analyses             Acceptance Criteria 6.b) The piping identified in          Inspection will be performed of       A report exists and concludes that Table 2.3.10-2 as ASME Code             the as-built piping matenal as        the piping identified in Section 111 is constructed of the      documented in the ASME material       Table 2.3.10-2 ASME Code material specified.                    reports.                              Section 111 is constructed of the material specified.
7.a) ne WLS preserves                   See Certified Design Material.        See Certified Design Material, containment integrity by isolation      subsection 2.2.1, Containment         subsection 2.2.1, Containment of the WLS lines penetrating the        System.                               System.
containment.
7.b) Check valves in drain lines       Refer to item 10 in this table.        Refer to item 10 in this table.
to the containment sump prevent cross flooding of compartments.
8.a) The WLS provides the              i) Inspection will be performed        i) Nonsafety-related displays of nonsafety related function of          for retrievability of the displays of  WLS containment sump level detecting unidentified leaks within    containment sump level channels       channels WLS-034 and WLS-035 containment to the containment         WLS-034 and WLS-035 in the            can be retrieved in the MCR.
sump.                                  MCR.
ii) Testing will be performed by      ii) A report exists and concludes adding water to the sump and          that sump level channels observing display of sump level.      WLS-034 and WLS-035 can detect a change of 1.7520.1 inches.
8.b) The WLS provides the             Tests will be performed to             A simulated high radiation signal nonsafety-related function of          confirm that a simulated high          causes the discharge control controlling releases of radioactive    radiation signal causes the            isolation valve materials in liquid effluents.         discharge isolation valve              WLS-PL-V223 to close.
WLS-PL-V223 to close.
: 9. Controls exist in the MCR to        Stroke testing will be performed       Controls in the MCR operate to cause the remotely operated valve      on the remotely operated valve         cause the remotely operated valve identified in Table 2.3.10-3 to        listed in Table 2.3.10-3 using         to perform its active safety perform its active function.           controls in the MCR.                   function.
: 10. He check valves identified        Exercise testing of the check          Each check valve changes in Table 2.3.10-1 perform an           valves active safety functions         position.
active safety-related function to      identified in Table 2.3.10-1 will change position as indicated in         be performed.
the table.
2.3.10-7 M T @ 00S8                                                              o:s:TAAes\rev4stio2031o.wpf:1tA32098

l                                                                                                                                                                                                                                                                    l Ccrtifl:d D sign Mit: rill l
LlOUID RADWASTE SYSTEM                                                                                                                                                                                             =           :=a Revision: Draft 4 Effective: 3/20/98                                                                                                                                                                                                       _
l                                                                          Table 2.3.10-5 l
Component                                                             8 l                                 Component Name                                                                                 Tag No.                           Location l   WLS Drain from Passive Core Cooling System                                                       WLS-PL V0718                                              Containment l    (PXS) Compartment A Check Valve l    WLS Drain from PXS Compartment A Check Valve                                                      WLS-PL V072B                                             Containment l    WLS Drain from PXS Compartment B Check Valve                                                      WLS-PL V071C                                             Containment l    WLS Drain from PXS Compartment B Check Valve                                                      WLS PL-V072C                                             Containment l    WLS Drain from Chemical and Volume Control                                                        WLS PL-V071A                                             Containment l    System (CVS) Compartment Check Valve l    WLS Drain from CVS Compartment Check Valve                                                        WLS PL-V072A                                             Containment 1
l    WLS Reactor Coolant Drain Tank                                                                                  WLS MT 01                                   Containment                                                            '
l    WLS Containment Sump                                                                                            WLS MT 02                                   Containment I    WLS Degasifier Column                                                                                          WLS-MV 01                                                        Aux l                                                                                                                                                              iliary Building l    WLS Effluent Holdup Tanks                                                                                 WLS MT 05A                                    Auxiliary Building l                                                                                                              WLS MT-058 l    WLS Waste Holdup Tanks                                                                                    WLS MT 06A                                    Auxiliary Building l                                                                                                              WLS-MT-068 l    WLS Waste Pre Filter                                                                                           WLS MV-06                                Auxiliary Bs ilding l    WLS lon Exchangers                                                                                              WLS MV-03                               Auxiliary Building l                                                                                                              WLS MV 04A l                                                                                                              WLS-MV-04B l                                                                                                              WLS-MV 04C l    WLS Waste After Filter                                                                                          WLS MV 07                               Auxiliary Building l    WLS Monitor Tanks                                                                                         WLS MT 07A                                    Auxiliary Building l                                                                                                               WLS MT-078 l                                                                                                               WLS MT 07C l    WLS Effluent Discharge isolation Valve                                                                   WLS-PL-V223                                    Auxiliary Buildin 2.3.10-6 MIM                                                                                                                                  c:vTAACSVev4WO20310.wpf:1b432098 I
L_____________                         _ _ _

lI Ccrtifl:d Oseign Mct:ri:1 l
1.lOUID RADWASTE SYSTEM                                                                                                                                                    nti:  n.ni I
Revision: Draft 4 i                                                                                                        5BM                                                                                                              EE
;                                      Effective: W44AM. 3/go/%                                                                                                                                                    _
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l Figure 2.3.101 Liquid Radwaste System 2.3.10.)d 9 NbYO                                                                                                                                     o:\lTAACS\rev4\it020310 wpf:1b-032098

f
  . i bW     l Westinghouse                                                                                                                                                  FAX COVER SHEET D
RECIPIENT INFORMATION                                                                                                                                                         SENDER INFORMATION DATE:                                             3/13/9g                                                                                                                         Name:            Su e_    Fa,tf3 TO:                                               13,'ll                                                                 4v[ky u                                                  LOCATION:       ENERGY CENTER - EAST PHONE:                                     So j . gj f- f f 4 /                                                                                                                    PHONE:          Office: 412-374 N d f COMPANY:                                                                                                                                                                           Facsimile:      win:        284-5535 OkC -                                                                                                _
outside: (412)374-5535 LOCATION:
Cover + Pages           1+
The following pages are being sent from the Westinghouse Energy Center, East Tower, Monroeville, PA. If any problems occur during this transmission, please call:
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y, y o PIease.                                                                     Hxve l % 'e., F So % No s ei                                                  '
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i .                                                                                                                                                                                                                                                           J.J.4 1
Table 3.3.21 (page 6 ef 12)
   ,                                                                                                                                                                        Engineersd safeguards Actuatica systsc Instrumentation A99LlCABLE MODES OR OTHER SPECIFIED       REQUIRED FUNCTION                                                           SURvt!LLANCE        ALLOWASLE      TRIP CONDITION $      CHANN(L5    CONDITIONS   REQUIREMENT 5         VALUt      SETPOINT
: 10.                                                                AD5 Stage 4 Actuation l
'                                                                                                                                       a. Manual Initiation                     1.2.3.4        2 switch        t,o      SR   3.3.2.3 Coincident with                          sets                                                      N/A 5.6(9)         2 switch       c.x        SR  3.3.2.3 sets                                                      N/A aC5 wide Range           1.2.3.4            4           s,o i
Pressure - Low.                                                  $n  3.3.2.1                     [a 1200 I
or                                                                SR  3.3.2.4                      psig)
SR  3.3.2.5 5A  3.3.2.6 5.6(9)             4          s,x SR  3.3.2.1                     (a 1200 SR  3.3.2.4                      psig)
SR  3.3.2.5 54  3.3.2.6 ADS   Stages 1, 2 &functions 3 Actuation          Refer toandFunction   9 (stages 1. 2 & 3 Actuation) for in'tiating requirements
: b. Cut Level - Low 2                        1.2.3.4        4 per tank      s.o        la  3.3.2.1                       a 20K SR  3.3.2.4                  volu(me level 5R  3.3.2.5                      span)
SR  3.3.2.6 5CC)         4 per tank      s.v        Sa  3.3.2.1 SR  3.3.2.4                       a 20K Sa  3.3.2.5                  volu[me     level SR  3.3.2.6                      span)
Coincident with         1.2.3.4             4          s.0        la  3.3.2.1 acs wide Range Pressure - Low.                                                   Sa  3.3.2.4 and                                                               SR  3.3.2.5                     [a 1200 sa  3.3.2.5                      psig)
SIC}              4          s,v        Sa  3.3.2.1 Sa  3.3.2.4 54   3.3.2.5 Sa 3.3.2.6                      [a 1200 psig)
Coincident with     aefer to Function 9 (AD5 Stages 1. 2 & 3 Actuation) for initiating functions and A(p \                                                                                                                             Aos stages 1. 2 & requirements 3 Actuation (c)                                                                                                                                                                                      (continued) n o, , - n s, , m. . . . . . .. ..u . .. 6n (3)                                                                with upper internals in place,';f                         :'r"r_; :;;"; ?;;; ,; .. i ii
                                                                                                                                                           .WM 7tfSSutoavA LE M t > Ze *4 ,,                                                vgo. t/C 2 t=
i j
l b AP600 S p01\ap400\t ech seec\160 M M2. rot-000097 3.3 34                               08/97 Amen (hent 0 i

car A0 anstruirenLdL10n 3.3.2 Table 1.3.21 (page 11 ef 12) tagineered Safeguards Actuation Systee Instrumentation APPLICAsLE u0ots Oruta SPECIFILO          at0Vlat0                     $Uavt!LLAMCE       AL LChrASLt          fatt FUNCTION                               CONDITIONS          CHAMhtL5        COM0! TION 5 atQutatMENTS          VALut         SETPOINT
: 20.                                                                     in Control acom isolation and Air Supply Initiation
: 4. Control e                   Air         1,2,3,4              2               F         Sa   1.3.2.1                       (s 2:10'8 Supply)2 8diation
                                                                                                                                              .Mp                                                                                    sa   3.3.2.4                       Cu ries /m i la   3.3.2.5                           Dose Sa   3.3.2.6                      Equivalent 1 131)
Note (h)              2               G.K       Saf t.3.2.1                        ( 2106l Ja" 3. 3. 2. 4                         ries /a la   3.1.2.5                           Ocse la   3.3.2.6                      teutvalent I 131) l                                                                                                                                       b. tattery Charger                            1.2,3,4              4               8,0       5a   3.3.2.3 l                                                                                                                                             Input volta                  -
divisions                      la   3.3.2.4                       (al4)v*)
Low hote (h)                              G,a       la   3. . 3 d    sions                     la    .3.2.4                           343 v.)
: 21.                                                                     miliary sera and Purification Lfne Isolation
(/                                                                            a. Pressurizer water                            1.2                4               8.L       sa   3.3. .                         [20      )
Level - Low 1                                                                          la 3     .2.4 5       3.2.5 1.3.2.6
: 22.                                                                  In-Containee nefuelin                      er Storage nk (InwST)
Injec n Line valve Act          ion
                                                                                                                                          ,   manual Initiation                     1.2,3,4U)          2 sai               t.m       sa 3     .2.3                          m/A 4*) 5 M                                               331/3                             L/A b.
AoS4                     gte                                 $$ch sAos 4thsds  stage 6'fetuatun gl                                                                       Actua                              aeferlofu.nctio and reavire ents.
for initiating  f. crions
  ![
   /
     \                                                                                                                                  c. Coincident aC5 Loop 1 and 2 Mot 4(a)5.5M
                                                                                                                                                                                        ,            i per loop           4.'r 86 la   3.1.2.1 1.3.2.4
[. 3 in tes Level . Low L Sa sa   3.3.2.5                     above insive M.
la   1.3.2.6                      surface of the t
                                                                                                                                                                                                          ~                                                                legs g,,3 g 23,                                                                  lawsf C tainment                                                                                                                               &ht nectre ation valve Aclu ice manual taiti                   on     1,2, 3,4 U         2 switch            E.m       sa   1.     .3                         =/a sets                                                -
4(")    .6h         2 switc             G,v       5    3.3.2.3                            m/a sets I
: b. Safeguards                               er to Function 1 afeguards ACtuati              for all initia g functions Actuation "nSy
  .                                                                 7                                                                        s nd requirements,
                                                                                                                                                                                                                              /                    /
     .)3 D /                                                                                                                                                               /                   /                       /                                                 continued) p                                                       @ -. r . .. . ./.. : . , , y; .Q. ; _: ~ :                                                y _ .-. -- ';
(h)                                                                During move t of irradiate                          vel assemblie          AA/D artwg             ALT 7ed#ad                  efd.nre7 a)                                                                  with the C5 not being c ed by the nor                                   assiduai neat menovat yste. ca=5).
(n)                                                                 with e aC5 being coo d by the RMS l
OI 75 $ /5'2 b                    AP600 1p01\apeop\techseec\lec30102 A7 102797 3.3 39                               08/97 Amendment 0 l

4 C.SrA3 anStn.centation 3.3.2 Table 3.3.21 (page 11 of 12)
Engineered safeguards Actuation Systee Instrumentation APPLICAstt m00E5 OTMta SPECIF110       atQUlstO                   Suavt1LLANCE        AllonAs L E FUNCTION               CON 0!? IONS     CHANhtL5                                                           TatP CONDITIONS     tt0UtatutNTS           VALut         stipotwT
: 20.                                                                Main Control noon Isolation and Air supply Initiation
: a. Control aoom Air              1.2,3,4             2          F.o             3.3.2.1 Supply nadiation                                                  SR SR  3.3.2.4 (s 2:10''
                                                                                                                                                                                 - Migh 2                                                          la  3.3.2.5 curies /e' Dose la  3.3.2.6                      touivalent 1 131) hote (h)             2          C.R         SR  3.1.2.1 Sa  3.3.2.4                        (s 2:10''3 curtes/m 54  3.3.2.5                            oose sa  3.3.2.6                      Equivalent 1 131]
: b. sattery Charger                1.2.3.4             4          s.o         sa  3.3.2.3 Input voltage -                       divistons                   sa  3.3.2.4                        (a343 v']
Low note (h)             4          C.R         54  3.3.2.3 divisions                   la  3.3.2.4                      (a 143 v+]
: 21.                                                                 Auxiliary spray and Purification Line Isolation
: a. Pressurizer water                1.2               4          s,L         Sa  3.3.2.1 Level - tow 1                                                      la  3.3.2.4                         (20.0E')
Sa  3.3.2.5 Sa  3.3.2.6
: 22.                                                                 In Containment aefueling water storage Tank (tawst)
Injection Line valve Actuation
: 4.        Manual Initiation     1.2. 3.4S N      2 switch        E.N         Sa  3.3.2.3                            N/A
                                                                                                                                                                                                      #)5 M               ""ca                     s s 3 2.3                              L/A
: b. A05 4th stage Actuation nefer lo kunClion and reeutrements.
AD5sds  G f Ctuation for initiating functions 4th Stage
                                                                                                                                                                                                                                           \'
: c. Coincident aC5              4(").5.6h        1 per loo       A. y             3.3.2.1 Loop 1 and 2 not                                                   Sa                                  (a 3 in
                                                                                                                                                                                                                                     %                 3.3.2.4 aboveinstde M sa Leg Level - Low 1,                                                 la  3.3.2.5 sa  3.3.2.6                      surface of the et
                                                                                                                                                                                                                                                                                           '95                        bcdryl0[
: 23.                                                                 tawST Containment nectrculation valve hl Actuation
: a. manual Initiation            1. 2. 3. 4(N     2 switch        E.=         Sa 1.1.2.3                              m/A sets 4("),$.6          2 switch        C.Y         Sa  3. 3. 2. 3                          m/A sets i                                                                         b. Safeguards                nefer to runction 1 (Safeguards Actuation) for all initiating functions Actuation "Mg(/                                                                                                   --                                                     s and requirements.
j-
! ~
MD /                                                                                                                                                                                                                                                        (continued)
                                                                                                ,,K
(                                                   [,, . m omr ........:. .. ,a . i . 1 x-m         x ...... :_ 5 (h)                                                                During sovement of irradiated fuel assembliesy AA10 ardtiu4 cg derr&meL/L                                 Mr +fe.ff t,7 (j)                                                                with the ACS not being cooled by the morea) assidual Meat mesoval Systes (am5).
l (n)                                                                with the ACS being cooled by the RMS.
1 Of756tf2                                l l
b AP600                                                                                 3.3 39                                08/97 Amendment 0 teena.4 sueoi cueciam.ar temt                                                                                                                                                          Q l
4 t

e CONDITION                         REQUIRED ACTION                COMPLETION TIME BB. One channel inoperable. B B. I .1 Place channel in bypass.        6 hours AND BB.I.2 Continuously monitor hot leg       6 hours level.

e-BB.1 and BB.I.2 With one channel inoperable, the inoperable channel must be placed in bypass and the hot leg level continuously monitored.
If one channel is placed in bypass, automatic actuation will not occur. Continuous monitoring of the hot leg level provides sufficient information to permit timely operator action to ensure that IRWST injection and ADS Stage 4 actuation can occur, if needed to mitigate events requiring RCS makeup, boration or core cooling.
: l.                                    Operator action to manually initiate IRWST injection and ADS Stage 4 actuation is assumed in the analysis of l
                                    . shutdown events (reference 11). It is also credited in the shutdown PRA (reference 12) when automatic actuation is not available.
l 1
i

l l                    DCP/NRC1119 l
117d97
        ~~
OITS 6152 RAI 480.1125F RAI 480.1127F RAI 480.1162F i
3/98      Revised Bases - Insert on page B 3.3-115 Y.1.1. Y.1.2. Y.2. and Y.3 If the Required Action and the associated Completion Time of the first Condition listed in Table 3.3.21 is not met while in MODE 4, with RCS cooling provided by the RNS, MODE 5, or MODE 6, the plant must be placed in a MODE in which the likelihood and consequen s of an event are minimized. If in MODE 4, this is accomplished by placing the plant in MODE 5 within 12 hours. The 12 hours is a reasonable dme to reach MODE 5 from MODE 4 with RCS cooling provided by the RNS (approximately 350*F) in an ordedy manner without challenging plant systems.
If in MODE 4 or 5, Required Action Y.1.2 requires inida6on of action within 12 hours to cloes the RCS pressure boundary and establish > 20% pressurizer level. The 12 hour Completion Tirne allows transition to MODE 5 in accordance with Y.1.1, if needed, prior to initia6ng action to open the RCS pressure boundary, i                                                           if in MODE 6, Required Acbon Y.2 requires the plant to be maintainod in MODE 6 and l
'                                                           initiation of action to establish the reactor cavity water level 2: 23 feet above the top of the reactor vessel flange.
Required Achons Y.1 and Y.2 minimize the consequences of a loss of decay heat removal
!                                                           event by optimizing conditions for RCS cooling in MODE 5 using the PRHR HX or in MODE 6 l
using IRWST injeebort Addi6onally, maximizing RCS inventory and maintaining RCS temperature as low as pracecal further minirnze the consequences of a loss of decay heat removal event. Closng the RCS pressure boundary in MODE 5 assures that PRHR HX cooling is available. Additionally, the potential for a enbeality event is minimized by suspension of posithe reactkity additions.
4 8
(.-                                                                                                                        '
                                                                                                                                                              ~..

  ,                                                                                             o a . ,> . c j BASES ACTIONS                       F.1. F.2.1, and F.2.2 (continued) unable to meet single failure criterion. Restoring all channels to OPERABLE status ansures that a single failure will not prey;nt the protective Function.
Alternatively, radiation monitor (s) which provide equivalent information and control room isolation and air supply initiation manual controls may be verified to be OPERABLE.              1 These provisions for operator action can replace one channel             !
of radiation detection and system actuation. The 72 hour 1
Completion Time is reasonable considering that there is one remaining channel OPERABLE and the low probability of an event occurring during this interval.
l l
1 G.1 MO                    l I
With one switch, switch set, channel, or ivision inoperable.             (
the system level initiation capability        reduced below that        I required to meet single failure criter n. Therefore, the required switch, switch set, channel,       division must be returned to OPERABLE status within 72 hours. The specified              !
Completion Time is reasonable considering the remaining switch, switch set, channel, or division is capable of performing manual initiation.
orrs acz H.1 With one channel inoperable, the ino>erable channel must be placed in a trip condition within 61ours.
Condition H is applicable to the PRHR heat exchangers Ng                                       rrow range water level low coincident with          l i
actuation starwp feeaw onpater, low (Function 13.b). With one startup feedwater channel inoperable, the inoperable channel must be placed in a trip condition within 6 hours. If one channel is tripped, the interlock condition is satisfied. The specified Completion Time is reasonable considering the time required to complete this action.
it1on H 1s ciso applicable to Fu injection line valve actuation (o i d .c. I annel is tripped, the logic become        -
of one and is unable to meet single failu          erion. A single failure.of (continued)
(
b AP600                                          B 3.3 107                    0   7" Amenchent b IPC1\techspec\16030502.r97-08229F

i BASES                                                                                 -
ACTIONS                         H.1                (continued) remaining channel could cause s                                                                                    )
ous I '      injection. The specified Completion Time is                                                                                     ona e considering that there is one remainin                                                                                        1 OPERABLE and the low probability of                                                                                        nt occurring during this interval.
I.1 and I.2 f
Condition I applies to IRWST containment recirculation valve actuation on safeguards actuation coincident with IRWST level Low 3 (Function 23.b). With one IRWST level channel i
'                                       inoperable, the one inoperable channel must be placed in a bypass condition within 6 hours. With two channels ino>erable, one channel must be placed in a bypass condition witlin 6 hours and the remaining ino)erable channel must be placed in a trip condition within 61ours.                                                                                      If one or two channels are inoperable, the logic becomes two out of three while still meeting single failure criterion (a failure in one of the three or one of the two remaining channels will i
not prevent the protective Function.) However, with one-
!                                       channel in bypass and one channel in trip, a single failure in one of the two remaining channels coincident with safeguards actuation could cause a s)urious actuation. The 6 hours allowed to place the inopera>1e channel (s) in the bypassed or tripped condition is justified in Reference 6.
J.1 and J.2 Condition .1 a; plies to the P 6. P-11 P 12, and P 19 interlocks. With one or two required channel (s) inoperable, the associated interlock must be verified to be in its required state for the existing plant condition within
: 1. hour, or any Function channels associated with inoperable interlocks ) laced in a bypassed condition within hours.
Verifying tie interlock state manually accompi                                                                                             s the l                                        interlock role.
7 If one or two associated, Function channels are by logic becomes two out of three or one out of-two, passed, the respectively, while still meeting single failure criterion (a failure in one of the three or one of the two remaining
!                                        channels will not prevent the protective Function.) However, 4
(continued)
(~                                                                                                                                                         , ' p as G s st.
         @ AP600                                                                                                                           B 3.3 108                   08/9f Amendnent 0 s pe1\techspec\140MBet . 707-082297 i

?
W         Westinghouse                          FAX COVER SHEET e
RECIP1ENT INFORMATION                               SENDER INFORMATION DATE:             M Ageg 26 19cg            r          Name:          4, P,pc y , /g 4,_,,g n                         _
TO:                  jaetv b ht_ g                     LOCATION:                        ENERGY CENTER - EAST PHONE:                3cy _. m g . > 2 '7 4             PHONE:
Office: 412-374 5 310                 l COMPANY:                                                                                                                       I Facsimile:                       win:                         284-5535 Nf(c / A/gg                                                         outside: (412)374-5535 I
{
LOCATION:
Cover + Pages        1+      3 The following pages are being sent from the Westinghouse Energy Center, East Tower, Monroeville, PA. If any problems occur during this transmission, please call:
WIN: 284 5489 (Wanda)/4031 (Defina) or Outside (412)374 5489/4031.
i COMMENTS:
5 ors 3ecr                                                                                                                   '
I TF, A c.  -    C enr, c> er       ne syv c. bes oc,a Gn-a Resra~ge $P5cRA see      Avrcre

1#
1                                                                                                                          3 To : Mr. Jerry Wilson, NRC / NRR                                       March 26,1998 Jerry, Westinghouse is currently in the process of preparing Revision 4 of the AP600 Certified Design Material to incorporate modifications previously discussed with and approved by the NRC. We would like to schedule a conference call with the staff to discuss the ITACC item pertaining to the identification of the " certified seismic design floor response spectra".
RAI 640.143 stated the following :
Question: 640.143 Hecause the final seismic amplified response spectra has not been used in the preliminary piping design, Westinghouse proposed to add a COL action item to have the COL applicant verify the final as-built piping design by using the final seismic input loadings. The staff has determined that a COL action item is not appropriate for this            i verification, and that the verification must be accomplished through ITAAC.                      l Westinghouse is requested to develop ITAAC for those applicable piping systems where the final seismic input loadings will need to be verified by the COI, applicant.
The response provided by Westinghouse b DCP/NRC 1183 identified that Westinghouse agreed with the above item and that Sections 2.1.2 (RCS),2.2.2(PCS),2.2.3(PXS).
2.2.4(SGS), 2.2.5(VES), 2.3.2(r'VS). 2.3.6(RNS), 2.3.7(SFS), 2.3.10(WLS), and 2.3.13(PSS) i would be revised to reflect the following :                                                     I i
Typical response for each applicable system l
Insert item 2.e)
The piping identified in Table 2.1.2-2 as ASME Code Section 111 is designed using the certified seismic design floor response spectra input.
1 l
l l
L__________.____. . _ _ . _ _ - _ - . .

i 2/3 Table 2.1.2-4 Inspections, Tests, Analyses, and Acceptance Criteria insert Item 2.e)
Design Commitment                 Inspections, Tests, Analyses        Acceptance Criteria 2.e) The piping identified in Table      Inspection will be conducted   An as-built ASME Code 2.1.2-2 as ASME Code Section III        of the ASME design reports      Section III design report is designed using the certified         for the piping identified in    exists and confirms that the seismic design floor response           Table 2.1.2-2.                   applicable as-built piping spectra.                                                                 identified in Table 2.1.2-2 has been designed using the certified seismic design floor response spectra.
Basd on further management review of this response, the following details were identified :
: 1)    The certified design floor response spectra is contained in AP600 document GW-S2R-002 Revision 2, Nuclear Island Structures Safe Shutdown Earthquake Seismic Response Report.
Revision 2 was generated to revise the vertical spectra in the shield Building Roof to reflect post 72 hour requirements and the addition of snow loads.
This change impacts on a select number of piping systems in the PCS system.
: 2)     Excluding the PCS system, all other systems that have been analyzed based on Revision 1 of the Seismic Response Report reflect analysis based on the final seismic amplified response spectra, therefore this ITAAC item is redundant and not applicable for these systems.
: 3)     Review of all systems identified above indicates that except for the five systems identified below, all piping seismic analyses have been performed to Revision 1 spectra -
ITAAC Section           2.1.2 RCS : Reactor Coolant System ITAAC Sectiori          2.2.2 PCS : Passive Containment Cooling System
* ITAAC Section           2.2.3 PXS : Passive Core Cooling System                            j ITAAC Section           2.2.4 SGS: Steam Generator System ITAAC Section           2.3.2 CVS Chemical and Volume Control System I
* Seismic analysis performed based on Rev 1, Rev 2 is required.                            !
3

i 3/
                                                                                                                             ,3 Based on our review of the seismic analyses, it is our position that the above ITAAC item should only be included in the five systems identified in item 3. The remaining systems have been evaluated to the fm' al seismic amplified response spect 1 and is therefore not applicable.
Please contact us at your earliest convince so that we can schedule a phone call to discuss this issue in more decil and address any questions that you may have.
Regards, e
W ,i p     -
                                           ,4 A , ...       .          ~
Gene Piplica                          Kevin Accornero I
i l
1 1
l

i    @ Westinghouse                                                 FAX COVER SHEET                I Reciplent Information                           Sender information Date:         3 /g /fg                         Name:      D. Lindgren To:         Joe Sebrosky                       location:  WEC E 330 Phone:                                         Phone:
(301) 415-1132                                (412) 374 4856 Facimile:                                      Facimile:
(310) 415-2002                                Bell: (412) 374 4887 Company:    U.S.NRC                                       WIN 284 4887 Location:   Rockville, MD Cover + Pages      1+3 The following pages are being sent from the Westinghouse Energy Center, Monroeville, PA.
If there are any problems during this transmission, please call the sender or WIN 284-6529 or Bell (412) 374-6529.
Comments:
                 '~T746 S 5           f:M va55                 Shw W &                     c A *Crs
        " Q lS Gussri3D                       )'BT S79KT> A,y'              A bib W'LL h e lv 85 t/ ,           12_
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1

l
: 3. Desig3 cf Structures, Ccmponents, Equipmert, cnd Syst:ms                                                                                                                           ns I 4 I
l 43 INTANZ
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l Figure 3H.5-11 (Sheet 2 of 8)                                     '
i l
l Shield Building Roof Typical Reinforcement Revision: 22
,   W Westingh00$8                                                                                                                                                            APril 6,1998 l                                                                                         3H-61 1                                                                                                                                                                                                 ;

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: 3. Design cf Struct:res, Ccmponents, Equipment, c:d Syst1ms                                                                 -
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Revision: 22   l W Westinghouse                                                                  3H-65                                                                                                      April 6,1998

hW         Westinghouse                          FAX COVER SHEET RECIPIENT INFORMATION                                SENDER INFORMATION DATE:               MOM d6, /99f                        NAME:            6c7vE [/#4./ u)
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Omce. [Y/2) 379-fflo COMPANY:                                                Facsimile:       win-          284-4887 Md b [^/d/f                                          outside: (412)374 4887 LOCATION:            A/r// rf & a r Cover + Pages       1 + C:9.3                                                                   I The following pages are being sent from the Westinghouse Energy Center, East Tower, Monroev0le, PA. If any problems occur during this transmission, please call:                    j 6/2ft                                                                              '
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J

RESPONSES TO NRC RECUEST FOR ADDITIONAL INFORMATION Eii
                                                                                                                                                                                                               =
WE is OITS 6642       ITAAC Meeting Open Item RAI for AP600 ITAAC from Plant Systems Branch (NRR/SPLB)
: 1) Generic actions for non-ITAAC entries in the AP600 CDM a) Identify applicable SSAR section.
b) Describe system purpose.
c) Review selection criteria from SSAR Section 14.3 as applicable.
d) Conclude why no design description or ITAAC is required.
e) Provide cross references if system components are in other ITAAC.

===Response===
An evaluation has been performed to systematically review the AP600 system 5 not included in Revision 3 of the AP600 Certified Design Material (CDM). This open item is a result of staff feedback at the ITAAC Task Group Meeting held on December 18-19, 1997. This evaluation applies the modified approach to the development of CDM for the AP600 as described in our response to RAI 640.166 in our letter DCP/NRCl272 dated February 27,1998 and as agreed in our meeting with the staff on March 12,1998. As a result of this evaluation, modifications will be made to the entries in the AP600 CDM, Revision 4.
a) AP600 systems have been tabulated in Table 6642-1 in alphabetical order by the system designator followed by the system name. The systems in Table 66421 are identified from the AP600 SSAR, Table 1.7-2 andin the AP600 Certified Design Matenal(CDM), Table of Contents. Applicable SSAR and CDM sections are identified, providing a cross reference for systems between the SSAR and the CDM.
In Table 1.7-2, systems with an "N/A" as the SSAR Section entry indicates that the system fu nction and description are not included in the SSAR. However, for these systems in Table 6642-1, a SSAR section is listed which describes an interface or use of that system.
Systems which are in the CDM but have no entry for the section are shown as underlined in Table 6642-1. Systems which are not in the CDM are shown with a double underline.
b) Table 6642 2 consists of those system designators in Table 66421 that either have a CDM section identified but have no entry in the section (underline) or have no section in the CDM (Agghk underline). A brief statement of the system function is given in the second column. The functicas were obtained from the SSAR sections describing the system or, if no functional description in the                                                                                                           j SSAR, the system description documentation.
OITS 6642-1 r

RESPONSES TO NRC REQUEST FOR ADDITIONAL. INFORMATION
                                                                                                                                                                                   ~ EE 5
c) The CDM selection criteria from SSAR Section 14.3.2.1 was reviewed for each of the systems in Table 6642 2 to identify if additional ITAAC are required.
First, the following four queries were made with respect to each of the systems:
Are there any features or functions classified as Class A, B, or C?
Are there any defense-in-depth features or functions provided?
For nonsafety-related systems, are there any features or functions credited for mitigation of design basis events?
For nonsafety-related systems, are there any features or functions that have been identified for additional regulatory oversight?
If the answer to any of these questions is yes, then certified design description and ITAAC addressing the system feature or function will be included in the AP600 CDM Revision 4. The results of these inquiries are summarized (Yes or No) in the third column (Safety, DID, NSS) of Table 6642-2.
Next, the following questions were considered:
l Are any features or functions necessary to satisfy the NRC's regulations in Parts 20,50,52,73 and 100?
l Are there any features or functions that represent an important assumption for probabilistic risk assessment?
Are any features or functions important in preventing or mitigating severe accidents?                                I Are there any features or functions that have a significant impact on the safety and operation of the plant Are any features or functions the subject of a provision in the Technical Specifications.                           I If the answer to any of the above questions is yes, then a design de                                                                     cion and ITAAC were  l l                           prepared using the appropriate functions stated in the SSAR. The results o application of these last five criteria are summarized (Yes or No) in column 4 (Miscellaneous Criteria) of Table 6642-2.
!                           For systems that are wholly or partially out of the scope of the AP600 certified design, a note is added l                           to the system function block in Table 6642 2. Therefore, the AP600 ITAAC screening criteria is not j                           applicable and the third and fourth columns contains dashes (--) instead of a Yes or a No.
OITS 6642-2

d RESPONSES TO NRC REQUEST FCR ADDITIONAL INFORMATION MEM35
:   g For comparison purposes, the fifth column of Table 6642 2 indicates whether or not (Yes or No) certined design material is included in ABB/CE System 80+ CDM (Reference 6642-1).
d) The last column of Table 6642-2 indicates the proposed disposition of the system in the AP600 CDM Revision 4. If any of the criteria from SSAR Chapter 14 were found to apply, then a design description and appropriate ITAAC will be included in the AP600 CDM Revision 4. In some cases, components of one system are included in the ITAAC of another system in the CDM. If so, cross.
references will be provided. If the system is in the scope of the AP600 design certification, but does not require a design description, then a CDM section will be included in Revision 4, but no entry is required. If the system is outside of the scope of the AP600 design certification, then the system will be omitted from the AP600 CDM Revision 4. The results are summarized in Table 6642-2 as follows:
Include Section        Include a section in the AP600 CDM with a Design Description and, if required, applicable Inspections, Tests and Acceptance Criteria (ITAAC).
Reference Section      Provide a reference to another system in the CDM, identifying the component.
or feature and the reference section number.
No Entry              include a section in the AP600 CDM only, with no entry.
No Section            Delete the existing CDM, if any. This will occur if the designated system is not within the scope of the AP600 design certification.
e) See the response to item d) above.
The following sections that have no design description or ITAAC in the AP600 CDM Revision 3 will be modified in Revision 4 of the AP600 CDM:
: 1) Add design description and ITAAC:
2.4.2 Main Turbine System 2.5.9 Seismic Monitoring System (per response to RAI 640.184)
: 2) Add a new section with no entry:
2.3.29 Radioactive Waste Drain System i
OITS 6642-3 i
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: 3) Cross-reference systems with components having design description and ITAAC in other systems:
From Section                                                                                                                                       To Section
                                    ' 2.3.18 Plant Gas System                                                                                                                             3.3     Buildings l
2.3.22 Containment Leak Rate Test System                                                                                                           2.2.1   Containment System 2.4.3    Main Steam System                                                                                                                         2.2.4   Steam Generator System 2.4.4    Steam Generator Blowdown System                                                                                                           2.2.1   Containment System 2.2.4   Steam Generator System 2.4.5    Condenser Air Removal System                                                                                                              3.5     Radiation Monitoring 2.4.7    Circulating Water System                                                                                                                  3.5     Radiation Monitoring 2.4.12 Gland Seal System                                                                                                                           2.4.2   Main Turbine System 2.5.8    Radiation Monitoring System (System-based)                                                                                                3.5     Radiation Monitoring 2.5.10 Main Turbine Control and Diagnostics System                                                                                                 2.4.2   Main Turbine System 2.6.11 Main Generation System                                                                                                                      2.4.2   Main Turbine System 2.7.8 Radwaste Building HVAC System                                                                                                                3.5     Radiation Monitoring 2.7.10 Health Physics / Hot Machine Shop HVAC System 3.5                                                                                                   Radiation Monitoring 2.3.29 Radioactive Waste Drain System                                                                                                              2.3.10 Liquid Radwas'.e System
: 4) Delete the system title:
2.3.23 Storm Drain System 2.3.25 Gravity and Roof Drain Collection System 2.3.26 Raw Water System 2.3.27 Sanitary Drainage System 2.6.8    Cathodic Protection System 2.6.10 Closed Circuit TV System 2.6.12 Excitation and Voltage Regulation System The remaining sections with no entry will remain as in CDM Revision 3.

==References:==
6642-1                           "The System 80' Standard Plant Design Contori Document," Volume 1, ABB
                                                             ! wmbustion Engineering, Inc., February 1995.
SSAR Revision:                               SSAR Table 1.7-2 will be revised to be consistent with the approach for the Al'600 CDM systems.
ITAAC Revision:                              As described in Table 6642 2.
OITS 6642-4 w __ - -_                                ._-- -

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TABLE 66421          AP600 SYSTEM DESIGNATORS, TITLES, AND SSAR REVISION 20 and CDM REVISION 3 SECTIONS SSAR       CDM System          System                                             Rev 20      Rev 3 Designator      Title                                              Section    Section ASS             Auxiliary Steam Sucolv System                       10.4.10    2.4.8 1
1 BDS             Steam Generator Blowdown System                      10.4.8    2.4.4 Note: See SGS and CNS for isolation function.
CAS             Compressed and Instrument Air Systems                9.3.1     2.3.15 CCS             Component Cooling Water System                       9.2.2      2.3.1 l
4 CDS             Condensate System                                    10.4.7     2.4.6 CES             Condenser Tube Cleaning System                     10.4.1.2.1   2.4.9 10.4.5.2.3 l
CFS             Turbine Island Chemical Feed System                 10.4.11    2.4.10 CMS             Condenser Air Removal System                         10.4.2     2.4.5 CNS             Containment System                                    6.2.3     2.2.1 CPS             Condensate Polishing System                           10.4.6    2.4.11 CVS             Chemical and Volume Control System                    9.3.6      2.3.2 W westingh0use l
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                                                                                                        !!*  -:g TABLE 66421     AP600 SYSTEM DESIGNATORS, TITLES, AND SSAR REVISION 20 and CDM REVISION 3 SECTIONS j
i SSAR      CDM System     System                                           Rev 20     Rev 3 Designator Title                                            Section   Section CWS        Circulating Water System                          10.4.5     2.4.7 Note: Condenser only.
DAS        Diverse Actuation System                            7.7      2.5.1 DDS        Data Display and Processing System              7.1 & 7.7    2.5.4 l
DOS        Standby Diesel & Aux. Boiler Fuel Oil System      9.5.4      2.3.3 DRS        Storm Drain System                                None      2.3.23 DTS        Demineralized Water Treatment System              9.2.3     2.3.24 DWS        Demineralized Water Transfer and Storage System   9.2.4     2.3.14 ECS        Main ac Power System                              8.3.1      2.6.1 EDS        Non Class IE de and UPS System                     8.3.2     2.6.2 EFS        Communication Systems                             9.5.2     2.3.19 EGS        Grounding and Lightning Protection System        8.3.1.1     2.6.6 OITS 6642-6 3 Westinghouse

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l TABLE 66421     AP600 SYSTEM DESIGNATORS, TITLES, AND SSAR REVISION 20 and CDM REVISION 3 SECTIONS SSAR        CDM System     System                                      Rev 20      Rev 3 Designator Title                                       Section    Section EHS        Soecial Process Heat Tracing System         8.3.1.1      2.6.7 ELS        Plant Lighting System                        9.5.3       2.6.5 EQS        Cathodic Drotection System None        2.6.8 FHS         Fuel Handling and Refueling System             9.1       2.1,1 FPS         Fire Protection System                       9.5.1       2.3.4 Note: Includes a containment spray function  6.5.2 FWS         Main and Startup Feedwater System            10.4.7      2.4.1 10.4.9 GSS         Cihasi Seal System                           1. 0.4.3   2.4.12 HCS         Generator Hydrogen and CO, Systems            10.2      2.4.13 l
l HDS         Heater Drain System                          10.4.7     2.4.14 HSS         Hydrogen Seal Oil System                      10.2      2.4.15     I IDS         Class 1E de and UPS System                   8.3.2       2.6.3 i
OITS 6642-7 T Westinghouse                                                                 l j
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_ _ - _ _ _ _ _ _ _ _ _ ._                                                                                l

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RESPONSES TO NRC REQUEST FOR ADDITIONAL INFORMATION
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TABLE 66421      AP600 SYSTEM DESIGNATORS, TITLES, AND SSAR REVISION 20 and CDM REVISION 3 SECTIONS SSAR         CDM System      System                                                                     Rev 20         Rev 3 Designator  Title                                                                    Section         Section IIS         In-core Instmnientation System                                                    4.4.6    2.5.5 LOS         Main Turbine and.Denerator Lube Oil System                                        10.2    2.4.16 MES         Meteorological / Environmental Monitorine System                                  2.3.3   None MHS         Mechanical Handling System                                                         9.1     2.3.5 MSS         Main Steam System                                                                  10.3    2.4.3 MTS         Main Turbine System                                                                10.2    2.4.2 OCS         Operation and Control Centers System                                   Chap 18             2.5.7     l PCS         Passive Containment Cooling System                                                6.2.2    2.2.2 PGS         Plant Gas Systems                                                                 9.3.2   2.3.18 PLS         Plant Control System                                                7.1 & 7.7              2.5.3 PMS         Protection and Safety Monitoring System                                    Chap 7          2.5.2 OITS 6642-8 Y Westingflouse

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RESPONSES TO NRC REQUEST FOR ADDITIONAL INFORMATION
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TABLE 66421                                                                                                           AP600 SYSTEM DESIGNATORS, TITLES, AND SSAR REVISION 20 and CDM REVISION 3 SECTIONS SSAR        CDM System .                                                                                   System                                                               Rev 20      Rev 3 Designator                                                                                Title                                                               Section     Section PSS                                                                                         Primary Sampling System                                              9.3.3      2.3.13 PWS                                                                                        Potable Water System                                                  9.2.5      2.3.16 PXS                                                                                        Passive Core Cooling System                                            6.3        2.2.3 RCS                                                                                        Reactor Coolant System                                                 5.1        2.1.2 RDS                                                                                         Gravity and Roof Drain Collection System                              None       2.3.25 RMS                                                                                         Radiation Monitoring System (System Based)                            11.5        2.5.8 RMS                                                                                         Radiation Monitoring System (Non-System Based)                         11.5        3.5      1 RNS                                                                                        Normal Residual Heat Removal System                                    5.4.7       2.3.6 RWS                                                                                         Raw Water System                                                    9.2.1.2.2    2.3.26 9.2.1.2.3.1 9.2.3 9.2.5 T westinghouse

RESPONSES TO NRC REQUEST FOR ADDITIONAL INFORMATION un.- :::
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TABLE 66421                                               AP600 SYSTEM DESIGNATORS, TITLES, AND SSAR REVISION 20 and CDM REVISION 3 SECTIONS SSAR      CDS1        l System                  System                                                                                                                                                                                                                 Rev 20    Rev 3 Designator              Title                                                                                                                                                                                                                 Section   Section RXS                     Reactor System                                                                                                                                                                                                           5.3     2.1.3 Includes:
Reactor Vessel                                                                                                                                                                             5.3 Reactor Internals                                                                                                                                                                         3.9.5 Control Rod Drive Mechanism                                                                                                                                                               3.9.4 Rod Control Cluster Assemblies                                                                                                                                                          4.2.2.?.1 Fuel Assembly Structure                                                                                                                                                                  4.2.2.2 SDS                     Sanitarv Drainage System                                                                                                                                                                                                9.2.6    2.3.27 SES                    Plant Security System                                                                                                                                                                                                     13.6    2.6.9 SFS                    Spent Fuel Pool Cooling System                                                                                                                                                                                           9.1.3    2.3.7 SGS                    Steam Generator System                                                                                                                                                                                                            2.2.4 Includes ponions of :
Main Steam System                                                                                                                                                                             10.3 Main Feedwater System                                                                                                                                                                        10.4.7 Stanup Feedwater System                                                                                                                                                                     10.4.9 l
SJS                    Seismic Monitoring System                                                                                                                                                                                                3.7.4    2.5.9 Note: ITAAC will be included in CDM Revision 4 per response to RAI 640.184 SMS                    Special Monitoring System                                                                                                                                                                                               4.4.6.4    2.5.6 W Westinghouse o --- - -- --

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RESPONSES TO NRC REQUEST FOR ADDITIONAL INFORMATION TABLE 66421     AP600 SYSTEM DESIGNATORS, TITLES, AND SSAR REVISION 20 and CDM REVISION 3 SECTIONS SSAR                                    CDM System     System                                                       Rev 20                                     Rev3 Designator Title                                                      Section                                     Section SSS         Secondarv Samnling Syrtent_                                          9.3.4                             2.3.21 SWS         Service Water System                                                  9.2.1                             2.3.8 TCS        Turbine Buildine Closed Cooling Water System                           9.2.8                            2.3.20 9.2.9.2.2 TDS         Turbine Island Vents. Drains. & Relief System                10.4.6.3                                  2.3.28 10.4.2.2.1 10.4.3.1.2 10.4.3.2.2 TOS         Main Turbine control and Diagnostics System                   10.2.2.4                                 2.5.10 TVS         Closed Circuit TV System                                                    13.6                       2.6.10 VAS         Radiologically Centrolled Area Ventilation System                       9.4.3                           2.7.5 VBS         Nuclear Island Nonradioactive Ventilation System                         9.4.1                          2.7.1 VCS         Containment Recirculation Cooling System                                  9.4.6                         2.7.7 VES         MCR Emergency Habitability System                                                 6.4                    2.2.5     ,
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TABLE 66421     AP600 SYSTEM DESIGNATORS, TITLES, AND SSAR REVISION 20 and CDM REVISION 3 SECTIONS SSAR                                             CDM System     System                                                             Rev 20                                             Rev 3 Designator Title                                                             Section                                            Section VFS        Containment Air Filtration System                                         9.4.7                                       2.7.6 VHS        Health Physics / Hot Machine Shoo HVAC System                          9.4.11                                         2.7.10 VLS        Containment Hydrogen Control System                                        6.2.4                                       2.3.9 VRS        Radwaste Buildir.g HVAC System                                             9.4.8                                       2.7.8 VTS        Imhine Building Ventilation Svstem                                         9.4.9                                       2.7.9 VUS        Containment Leak Rate Test System                                          6.2.5                                      2.3.22 VWS        Central Chilled Water System                                               92.7                                        2.7.2 VXS        Annex / Auxiliary Non-Radioactive Ventilation                              9.4.2                                       2.7.3 System VYS         Hot Water Heating System                                               9.2.10                                        2.7.11 VZS         Diesel Generator Building Ventilation System                            9.4.10                                        2.7.4 WGS         Gaseous Radwaste System                                                        11.3                                  2.3.11 OITS 6642-12

i RESPONSES TO NRC REQUEST FOR ADDITIONAL INFORMATION
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l l                                                          TABLE 66421                     AP600 SYSTEM DESIGNATORS, TITLES, AND SSAR REVISION 20 and CDM REVISION 3 SECTIONS                                                                                                                                                                    I SSAR                    CDM System                     System                                                                                                                   Rev 20                  Rev 3 Designator                 Title                                                                                                                    Section                Section l                                                          WLS                        Liquid Radwaste System                                                                                                    11.2                   2.3.10 WRS                        Radioactive Waste Drain System                                                                                            9.3.5                  None 11.2 WSS                        Solid Radwaste System                                                                                                     i 1.4                  2.3.12
:                                                          WWS                        Waste Water System                                                                                                        9.2.9                  2.3.17 ZAS                        Main Generation System                                                                                                     8.1                   2.6.11 l
ZBS                        Transmission Switchvard & Offsite Power System                                                                             8.2                   None ZOS                        Onsite Standby Power System                                                                                               8.2.1                   2.6.4 8.3.1 ZVS                        Excitation and Voltage Regulation System                                                                                 10.2.2.3                2.6.12 OITS 6642-13 l
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_ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ .             . _ . _ _ _ . _                 __                                                         _                 _ _ . _ _ _ . . . _ . _ _ _                              __   _____._______._________________a

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  ;                                                                                    3. Design cf Structures, Ccmpone-ts, Equipment cnd Systems l                                                                                 Table 3.11 1 (Sheet 12 of 47)
ENVIRONMENTALLY QUALIFIED ELECTRICAL AND MECIIANICAL EQUIPMENT l
Operating Envir.                        Time         Qualification AP600                Zone              Function     Required    Program Description                  Tag No.              (Note 2)          (Note 1)     (Note 5)    (Note 6)
TRANSMITTERS j                                         PCS Water Delivery Flow      PCS JE FT 001        9                 PAMS         2 wks            E PCS Water Delivery Flow      PCS JE FT 002        9                 PAMS         2 wks            E PCS Water Delivery Flow      PCS JE FT 003        9                 PAMS         2 wks            E PCS Storage Tank Water Level PCS JE LT 010        9                 PAMS         2 wks            E PCS Storage Tank Water level PCS JE LT Oil        9                 PAMS         2 wks            E PRHR HX Mow                  PXS JE FT 049A        I                PAMS         4 mos             E*
PRHR HX Flow                 PXS JE FT 049B       1                 PAMS         4 nxm             E*
RCS Cald Leg 1 A Row         RCS JE FT 101 A      I                 RT            Note 3           E RCS Cold leg l A Flow        RCS JE FT 101B        i                RT            Note 3           E RCS Cold Leg l A Flow        RCS JE FT 10lc        I                 RT           Note 3           E RCS Cold Leg l A Row         RCS JE FT 10lD        I                 RT           Note 3           E RCS Cold leg IB Flow         RCS JE FT 102A       1                  RT           Note 3           E       )
RCS Cold leg IB Flow         RCS JE FT 102B        i                 RT           Note 3           E       I RCS Cold leg IB Flow         RCS JE FT 102C        l                 RT           Note 3           E l                                         RCS Cold leg IB Flow         RCS JE FT 102D        I                 RT           Note 3           E RCS Cold leg 2A Flow         RCS JE FT 103A        I                 RT           Note 3           E RCS Cold leg 2A Flow         RCS JE FT 103B        i                 RT           Note 3           E RCS Cold leg 2A Flow         RCS JE FT 103C        l                 RT           Note 3           E RCS Cold leg 2A Flow         RCS JE FT 103D        I                 RT           Note 3            E      j RCS Cold leg 2B Flow         RCS JE FT 104A        1                 RT           Note 3            E RCS Cold Leg 2B Flow         RCS JE FT 104B        i                 RT           Note 3            E RCS Cold leg 2B Flow         RCS JE FT 104C        1                 RT           Note 3            E RCS Cold Leg 2B Flow         RCS JE FT 104D        t                 RT           Note 3            E l SGI Startup Feed *ater Flow    SGS JE FT 055A       2                  ESF          5 nun             E PAMS         2 wks l SGI Startup Feedwater Flow     SGS JE FT 055B        2                 ESF          5 nun             E PAMS         2 wks l SG2 Startup Feedwaaer Flow     SGS JE FT 056A        2                 ESF          5 nun             E PAMS         2 wks I SG2 Statup Feedwaaer Plow      SGS'JE FT 056B        2                 ESF          5 nun             E PAMS         2 wks Plant Vent Flow              VFS JE FT 101         7                 PAMS         2 wks             E+
I i                                         Revision: 22 April 6,1998                                         3.11-18                             W Westinghouse

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;      3. Design cf Structures, Ccmponents, Eq:1pme:t cod Systems                                E Table 3.11-1 (Sheet 15 of 47)
ENVIRONMENTALLY QUALIFIED ELECTRICAL AND MECilANICAL EQUIPMENT l
Operating Envir.                     Time      Qualification                                           -
AP600                Zone              Function Required  Program Description                   Tag No.              (Note 2)          (Note 1) (Note 5)  (Note 6)
RCS Wide Range Pressure       RCS JE PT 140A       I                 PAMS     4 rnos         E*
UF       S un                                                              ,
RCS Wide Range Pressure       RCS JE PT 140B       1                 PAMS     4 mos          E*                                                 {
ESF      5 man                                                             i RCS Wide Range Pressure       RCS JE PT 140C       1                 PAMS     4 mas          E*                                                 !
ESF      5 nun                                                             1 RCS Wide Range Pressure       RCS JE PT 140D       I                 PAMS     4 mos          E*
ESF      5 nun                                                             l l
PZR Pressure                  RCS JE PT 191 A       1                RT        5 nun          E*                                                l ESF       5 nun                                                            j PAMS    4 mos PZR Pressure                  RCS JE PT 1918       i                 RT        5 nun          E*
UF       S un                                                             j PAMS     4 mos                                                            i PZR Pressure                  RCS JE PT 191C        1                 RT       5 nun          E*
UF       S an                                                             I PAMS     4 mas                                                            l PZR Pressure                  RCS JE PT 19lD        I                 RT       5 nun          E*
ESF      5 nun PAMS     4 mos                                                            ]
l l Main Steamhne SGI Pressure      SGS JE PT 030         1\    \
ESF PAMS 5 nun 2wb E*
l Maan Steamhne SGI Pressurc      SGS JE PT 031        2                  ESF      5 nun          E PAMS     2 wks l
Main Steamhne SGI Pressure    SGS JE PT 032         1                 ESF      5 min          E*                                                l PAMS     2 wks l   Maan Sicarnhne SGI Pressure   SGS JE PT 033        2                  ESF      5 nun           E PAMS     2 wks l   Mam Steamhne SG2 Pressure     SGS JE PT 034         1 \               ESF      5 nun           E*
PAMS     2 wks l   Main Sicamhne SG2 Pressure    SGS JE PT 035         2                 ESF       5 nun          E l
PAMS     2wb                                                                l l   Main Steamhne 502 Pressure    SGS JE PT 036    i    !                 ESF       5 nun          E*
PAMS      2 wks l   Main Sicamhne SG2 Pvessee     SGS JE PT 037         2                 ESF       5 nun          E PAMS      2 wks Main Control Room Difheennal  VES JE PT 004A        3                 ESF       2 wks          E Pressure Main Control Room Differennal VES JE PT 004B        3                 ESF       2 wks          E Pressure i
I Revision: 22
[ WSStingh00$8                                                                       April 6,1998 3.11 21

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o P%c 1 ocj To :Mr. Jerry Wilson, NRC / NRR March 30.1998 Jerry, Based on our phone call yesterday afternoon, attached is the proposed modification to the SSAR with respect to the Section 3.9.3 as it pertains to as-built reconciliation. Before we initiate a formal change to the SSAR and CDM, we would like to schedule ar.other conference call with the staff to discuss these changes.-
Based on our discussion, the completion of the seismic analysis utilizing the certified design floor response spectra as described in Section 3.7.2 has been added to Section 3.9.3 as a specific as-built reconciliation item. This proposed modification would then eliminate the need for the following ITAAC items :
Section 2.1.2          Ite m 2.e Section 2.2.1          Item 2.c Section 2.2.2         Item 2.c Section 2.2.3          Item 2.d Section 2.2.4          Item 2.c
                                    'Section 2.2.5          Item 2.c Section 2.3.2          Item 2.d Section 2.3.6          Item 2.d Section 2.3.7         Item 2.b Section 2.3.10        Item 2.c Section 2.3.13        Item 2.b I
In addition, we would also like you to consider the proposed changes that identify the Class 1 Fatigue analyses and the time-history seismic analyses for the RCL loop piping as specific as-built reconciliation items. We believe these changes are consistent with your recom nended change for the confirmation of seismic response spectra, and would therefore       '
capture all of these items as part of the ITAAC verification for the existence of an ASME Section III design report for the as-built piping identified.
This proposed modification would then eliminate the need for the following ITAAC items :
Section 2.1.2 -       Item 2.c l
Section 2.1.2         Item 2.d Section 2.2.3         Item 2.c Section 2.3.2         Item 2.c '                                                        j Section 2.3.6         Item 2.c

No 2a3 1
Please contact us at your earliest convince so that we can schedule a phone call to discuss these issues in more detail and address any questions that you may have.
l        Regards, l                           q    -
j                                                                                                                              -r Gene Piplied                                                      evin Accornero l
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Pw 3 - 3 SSAR SECTION 3.9.3 Paragraph 4                                                                                    l The ASME Code, Section III requires that a design specification be prepared for ASME Class 1,2, and 3 components. The specification conforms to and is certified to the requirements of ASME Code, Section III. The Code also requires a design report for safety-related components, to demonstrate that the as-built component meets the requirements of the relevant ASME Design Specification and the applicable ASME Code. The design specifications and design reports will be completed by the Combined License applicant or his agent. Design specifications for ASME Class 1,2, and 3 components and piping are prepared utilizing procedures to meet the ASME Code. The design report includes as-built reconciliation. The as-built reconciliation includes evaluation of the ASME Code fatigue analysis for Class 1 pipe, pipe break dynamic loads, completion of the small bore piping analysis, the reconciliation to the certified design floor response spectra, confirmation of the reactor coolant loop time history seismic analyses, changes in support locations, and the construction deviations.
PROPOSED MODIFICATION The ASME Code, Section III requires that a design specification be prepared for ASME Class 1,2, and 3 components. The specification conforms to and is certified to the requirements of ASME Code, Section III. The Code also requires a design report for safety-related components, to demonstrate that the as-built component meets the requirements of the relevant ASME Design Specification and the applicable ASME Code. The design specifications and design reports will be completed by the Combined License applicant or his agent. Design specifications for ASME Class 1,2, and 3 components and piping are prepared utilizing procedures to meet the ASME Code. The design report includes as-built reconciliation.
The as built reconciliation includes the evaluation of pipe break dynamic loads, changes in support locations, construction deviations, and the completion of the small bore piping analysis. Confirmation of the following is also included in the as-built reconciliation of the safety related piping and components :
Completion of the ASME Code fatigue analysis for Class 1 pipe for the following systems:    Reactor Coolant System (RCS), Passive Core Cooling System (PXS),
l                        Chemical and Volume Control System (CVS), Normal Residual Heat Removal System (RNS),
Completion of the time-history seismic analysis for the reactor coolant loop piping (hot legs, cold legs) that accounts for the i 15 percent peak broadening as described in Section 3.7.2.5, Completion of the seismic analyses utilizing the certified design floor response spectra described in Section 3.7.2 for the following systems: Reactor Coolant System (RCS),
Passive Containment Cooling System (PCS), Passive Core Cooling System (PXS),
Chemical and Volume Control System (CVS), Steam Generator (SGS).
l e__________________________   . _ .

o Westinghouse                        FAX COVER SHEET W
RECIPIENT INFORMATION                            SENDER INFORMATION OATE:              /d4ded 7 7, /99h                  NAME:            (fevr,@Atc4 TO:                                                  LOCATION:         ENERGY CENTER -
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I RESPONSES TO NRC RESUEST FOR ADDITIONAL INFORMATION
: 3) Cross-reference systems with components having design description and ITAAC in other systems:
From Section                                              To Section 2.3.18 Plant Gas System                                   3.3     Buildings 2.3.22 Containment Leak Rate Test System                  2.2.1   Containment System 2.4.3   Main Steam System                                 2.2.4   Steam Generator System 2.4.4   Steam Generator Blowdown System                   2.2.1   Containment System 2.2.4   Steam Generator System 2.4.5   Condenser Air Removal System                      3.5     Radiation Monitoring 2.4.7   Circulating Water System 2.4.12 Gland Seal System
                                                             @  2.4.2 Main Turbine System 7 Main Turbine System 2.5.8   Radiation Monitoring System (System based)        3.5     Radiation Monitoring 2.5.10 Main Turbine Control and Diagnostics System        22 2    Main Turbine System 2.6.11 Main Generation System                           Q.6.1 Main ac Power Syh 2.7.8   Radwaste Building HVAC System                     3.5     Radiation Monitoring 2.7.10 Health Physics / Hot Machine Shop HVAC System 3.5          Radiation Monitoring 2.3.29 Radioactive Waste Drain System                     2.3.10 Liquid Radwaste System
: 4) Delete the system title:
2.3.23 Storm Drain System 2 3.25 Gravity and Roof Drain Collection System 2.3.26 Raw Water System 2.3.27 Sanitary Drainage System 2.6.8   Cathodic Protection System 2.6.10 Closed Circuit TV System 2.6.12 Excitation and Voltage Regulation System The remaining sections with no entry will remain as in CDM Revision 3.

==References:==
6642-1       "'Ihe System 80+ Standard Plant Design Contori Document," Volume 1, ABB Combustion Engineering, Inc., February 1995.
SSAR Revision:           SSAR Table 1.7-2 will be revised to be consistent with the approach for the AP600 CDM systems.
ITAAC Revision:          As described in Table 6642 2.
OITS 6642-4 1
                                                                                                       \

I 1
                                 @ Westinghouse                                                           FAX COVER SHEET Recipient Information                                  Sender Information Date:            , /;,/5 j                           Name:          D. Lindgren To:            Joe Sebrosky                          Location:      WEC E 330 Phone:                                                Phone:
(301) 415-1132                                       (412) 374 4856 Facimile:                                             Facimile:
(310) 415 2002                                       Bel: (412) 374 4887 Company:        U.S.NRC                                              WIN 284 4887 Location:       Rockville, MD Cover + Pages            1+
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Westinghouse            FAX COVER SHEET f
RECIPIENT INFORMATION                   SENDER INFORMATION DATE:                           3/3I/ 9 Y             NAME:              3ee      Pato TO:                                                    LOCATION:        ENERGY CENTER .
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* 3 NRC FSER OPEN ITEM Question: 480.ll59F (OITS #6583)
A technical specification equivalent to standard technical specification STS 3.9.4 specifying the status of containment penetration requirements during core alterations and movement of irradiated fuel assemblies within containment should be provided (similar to current AP600 TS 3.6.8 with applicability during core alterations).
Response (Revision 2):
The Standard Technical Specifications include a technical specification for containment penetrations during core alterations. The BASES of this specification explains that the applicable safety analysis that requires this specification is for fuel handling accidents. Many operating plants then assume that the containment is closed when performing the offsite dose analyses for this event. However, the AP600 fuel handling accident offsite dose analyses do not require containment closure to meet the specified limits. Therefore, ap' plication of the accepted technical specification screening criteria does not capture containment closure during fuel movement, and no corresponding specification was incorporated.
Nevertheless, the NRC steff has requested that Westinghouse include a technical speficication for -
containment during core alterations. Per this request, Westinghouse has added Technical Specification 3.9.5 that specifies the status of containment during core alterations and movement of irradiated fuel smmblies within containment. The technical specification is based on STS 3.9.4 with some modifications based on AP600 differences.
The proposed status of the containment openings during core alterations and movement ofirradiated fuel is different from STS 3.9.4 as discussed below:
Equipment Hatches STS 3.9.4 requires the containment equipment hatches to be closed and held in place by four bolts. In the AP600 technical specification, the equipment hatch must be closed, or if open, an alternative barrier between the fuel and the outside atmosphere shall be in place or capable of being established within 15 minutes. The alternate barrier may consist of the staging area in the auxiliary building outside the equipment hatches provided that the doors in the staging area are closed to the annex building or the outside atmosphere. The alternate barrier may also consist of a temporary equipment hatch cover. In addition, if the containment equipment hatch is open, the containment air filtration system (VFS) shall be operable to provide for monitoring of air borne radioactivity and filtration of containment atmosphere..
Justification:                                                                                            I l
480.1159F-1 T Westinghouse                                                                             Revision 2

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                                                                                                               )
NRC FSER OPEN ITEM      l As discussed above, the AP600 offsite dose analysis does not assume the containment equipment             i hatches are closed, and therefore the technical specification screening criteria are not met.
Furthermore, unlike many current plants, the containment equipment hatches do not open direc:ly to the outside atmosphere, but open into a staging area in the auxiliary building. The alternate boundary prevents the egress of airbome fission products from being released to the atmosphere if the equipment hatches were open during a fuel handling accident. The operation of the VFS provides for monitoring of radioactivity releases from containment following a fuel handling accident.
Other Penetrations l                                                                                                              l STS 3.9.4 requires one door in each airlock closed. In the AP600 technical specification, one door in      !
each air-lock is closed or, if open, the VFS is operable to provide a filtered exhaust of the containment atmosphere. AP600 technical specification 3.9.5 also stipulates that the VFS is operable if the            {
l temporary penetrations are open.
Justification:
l   In addition to the justification above, the operability of the VFS will reduce the consequences of a fuel handling accident by filtering the containment atmosphere. These penetrations open into the auxiliary building. Upon detection of high radiation, these portions of the auxiliary building are serviced by the l
VFS which will provide containment air filtration of these areas. Operation of the VFS in combination with the auxiliary building enclosure provide a sufficient alternate barrier to the release of radioactivity directly to the environment.
A P600 ++5! 79c2 tie 39 5 !: 2 tim in addition to the above justifications provided for the deviation from the Standard Technical Specifications, the AP600 has made many improvements in l   shutdown safety. The AP600 passive safety systems are operable during all modes of operation including shutdown. Unlike current and evolutionary plants, technical specifications for the AP600 safety systems have been included for all shutdown modes. Passive safety systems designed to j   operate during shutdown are major contributors to the large reduction in AP600 shutdown risk. The AP600 shutdown probabilistic risk assessment calculates a core damage frequency from internal events I
at shutdown of 9E-8 which is orders of magnitude smaller than current plants.
Per subsequent discussions with the NRC staff, two approaches were outlined by the NRC for J
resolution of this issue. The first approach was to adopt the standard technical specification for the     i AP600. The second approach was to modify the proposed TS 3.9.5 per NRC staff comments, and to              I include an additional Technical Specification for the fuel handling area ventilation systems similar to the standard technical specification for Fuel Building HVAC Systems. Westinghouse has chosen this          j l   second approach. His response submits the revised TS 3.9.5 and a proposed TS 3.9.6 which covers the Radiologically Contolled Area Ventilation System (VAS) and Containment Air Filtration System (VFS) during fuel movement in the fuel handling area.
1 SSAR Revision:             Technical Specification 3.9.5 and 3.9.6.
480.1159F-2 Revision 2                                                                                  U5M 1
l

   ,                                                                                          l Containmen   Pent:rni:ns   1 3.9.5 i 3.9 REFUELING OPERATIONS 3.9.5 Containment Penetrations LC0 3.9.5      The containment penetrations shall be in the following status;
: a. The equipment hatches closed and held in place by (four) bolts or, if open, an alternative barrier between the            j containment atmosphere and the outside atmosphere shall be inplace, and the containment air filtration system (VFS) shall be operating to provide for monitoring of air-borne        i radioactivity in the co'itainment:                               1
: b. One door in each air lock closed or, if open, the VFS shall be operating;
: c. The containment spare penetrations closed or, if open, the VFS shall be operating:
: d. Each penetration providing direct access from the containment atmosphere to the outside atmosphere either:
: 1. closed by a manual or automatic isolation valve, blind flange or equivalent. or
: 2. capable of being closed by an OPERABLE Containment Isolation signal.
APPLICABILITY:     During CORE ALTERATIONS During movement of irradiated fuel assemblies within containment.
ACTIONS miem>
CONDITION                     REQUIRED ACTION          COMPLETION TIME A. One or more                A.1      Suspend CORE            Immediately containment                         ALTERATIONS.
penetrations not in required status.           AND A.2      Suspend movement of     Immediately irradiated fuel assemblies within i
containment.
AP600                                    3.9-1    DRAET             March 31, 1998 l-

1
                 .                                       containe.ent Penetrations 3.9.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1     Verify each required containment               7 days penetration is in the required status. If one or more of the required containment penetrations is open, one train of VFS shall be operating.
SR 3.9.5.2     Verify each required containment purge and     In accordance exhaust valve actuates to the isolation        with the position on an actual or simulated             Inservice Test actuation signal.                              Program 1
1 AP600                                 3.9-2   DRAFT              March 31, 1998

Containment Penetrations B 3.9.5 B 3.9 REFUELING OPERATIONS B 3.9.5 Containment Penetrations BASES
                                                                                        = -. =
BACKGROUND     During CORE ALTERATIONS or movement of irradiated fuel assemblies within containment, a release of fission product radioactivity within containment will be restricted from escaping to the environment when the LCO requirements are met.
In MODES 1. 2. 3. and 4. this is accomplished by maintaining containment OPERABLE as described in LC0 3.6.1. " Containment."
In MODES 5 and 6. this is accomplished by providing closure capability of containment penetrations as described in LC0 3.6.8. " Containment." In MODE 6. the potential for containment pressurization as e result of an accident is not likely:
therefore, requirements to isolate the containment from the outside atmosphere can be less stringent. The LC0 requirements are referred to as " containment closure" rather than
                                         " containment OPERABILITY." Containment closure means that all potential escape paths are closed or capable of being closed.
Since there is no potential for containment pressurization. the Appendix J leakage criteria and tests are not required.
The containment serves to contain fission product radioactivity that may be released from the reactor core following an accident, such that offsite radiation exposures are maintained within the requirements of 10 CFR 50.34. For a fuel handling accident. the AP600 doca analysis does not rely on containment closure to meet the offsite radiation exposure limits. This LC0 is provided as an additional level of defense against the possibility of a fission product release from a fuel handling accident during CORE ALTERATIONS.
The containment equipment hatches which are part of the containment pressure boundary, provide a means for moving large equipment and components into and out of containment. During CORE ALTERATIONS or movement of irradiated fuel assemblies within containment. an equipment hatch is considered closed if the hatch cover is held in place by at least (four] bolts.
Good engi.neering practice dictates that the bolts required by this LCO be approximately equally spaced.
If the equipment hatch is open an alternative barrier between the fuel and the outside atmosphere shall be in place or capable of being established within 15 minutes. Each containment equipment hatch opens into a staging area in the auxiliary building. These staging areas contain doors that open to the radiologically controlled areas of the annex (continued) l l                         AP600                                 B 3.9-1          DRAFT      March 31, 1998 l

(
BACKGROUND building. The. annex building contains a door that opens to the outside atmosphere. The alternate barrier may consist of the e
staging area in the auxiliary building, or may consist of the staging' areas in the auxiliary building and the radiolog1cally controlled areas in the annex building provided the doors from the annex building to the outside atmosphere are closed. The alternate barrier may also consist of a temporary equipment hatch cover that provides equivalent isolation capability. The alternate boundary prevents the airborne fission products from being readily released to the atmosphere if the equipment hatches were open during a fuel handling accident.
If an equipment hatch is open during CORE ALTERATIONS. the i              containment air filtration system (VFS) shall be operating to provide for monitoring of air-borne radioactivity. This system services the containment and upon detection of high radiation, also services the fuel area and the auxiliary building staging areas. The operation of the VFS provides for monitoring of radioactivity releases from containment following a fuel handling accident and, if operating, will provide filtration of the containment atmosphere.
If two doors in a personnel air lock. or spare containment penetration are open during CORE ALTERATIONS. then the containment air filtration system (VFS) shall be operating to.
monitor for the release of radioactivity and to provide filtration of the air inside containment to minimize the consequences of a fuel handling accident. These penetrations open into the auxiliary building. Upon detection of high radiation in the exhaust air from the auxiliary building, these portions of the auxiliary building are serviced by the VFS which will provide filtered exhaust of these areas.
Considering that these penetrations open into the auxiliary building and not directly to the atmosphere and that the VFS is in operation, an alternate barrier to the release of radioactivity directly to the environment is provided.
(continued)
AP600                              B 3.9-2          DRAFT              March 31, 1998

Containment Per:9trations l                                                    ,                          R 3.9.5 l
* BASES l     APPLICABLE      For the AP600. there are no safety analyses that SAFETY ANALYSES require containment closure during CORE ALTERATIONS or movement of irradiated fuel assemblies within containment.
l other than those discussed in LC0 3.6.8. Fuel handling accidents. analyzed in Reference 1. include dropping a single irradiated fuel assembly and handling tool or a heavy object onto other irradiated fuel assemblies.        The requirements of LC0 3.9.4. " Refueling Cavity Water Level ."
ensure that the release of fission product radioactivity, subsequent to a fuel handling accident, results in doses that are well within the guideline values specified in 10 CFR 50.34. Standard Review Plan. Section 15.7.4. Rev. 1 (Reference 2), defines "well within" to be 25% or less of l
the limiting dose guideline values.
This . specification is included in accordance with NRC direction per Reference 3.
l     LC0             This LC0 provides defense-in-depth against the consequences of a fuel handling accident in containment by limiting the l
potential escape paths for fission product radioactivity released within containment. This LC0 recuires the containment equipment hatches to be closec or if open, requires an alternate barrier be established. This LC0 requires that if an equipment hatch, personnel air lock, or spare containment penetration is open during CORE ALTERATIONS. then the containment air filtration system (VFS) shall be in operation to monitor for the release of radioactivity and to provide filtration of the air inside containment to reduce the consequences of a fuel handling accident.
i (continued)
AP600                               B 3.9-3          DRAFT       March 31, 1998

Containment Penetrations B 3.9.5 BASES APPLICABILITY The containment penetration requirements are applicable during CORE ALTERATIONS or movement of irradiated fuel assemblies within containment because this is when there is a potential for a fuel handling accident. In MODES 1. 2. 3. and 4 containment penetration requirements are addressed by LCO 3.6.1. In MODES 5 and 6. when CORE ALTERATIONS or movement of irradiated fuel assemblies within containment are not being conducted. the potential for a fuel handling accident does not exist. Containment closure capability in Modes 5 and 6 are addressed by LC0 3.6.8.
ACTIONS     A.1 and A.2 If the containment equipment hatch or air locks, or any containment penetration that provides direct access from the containment atmosphere to the outside atmosphere are not in the required status, the unit must be placed in a condition where the isolation fur.ction is not needed. This is accomplished by immediately suspending CORE ALTERATIONS and movement of irradiated fuel assemblies within containment. Performance.of these actions shall not preclude completion of movement of a component to a safe position.
(continued)
AP600                              B 3.9-4          DRAFT      March 31, 1998

Containment Penetrations B 3.9.5
,       BASES SURVEILLANCE             SR 3.9.5.1 REQUIREMENTS This Surveillance demonstrates that each of the containment penetrations required to be in its closed position is in that Josition or the VFS is operating. In the case of the equipment latches, this surveillance also requires that an alternate barrier is in place or capable of being in place within 15 minutes. The Surveillance on the open purge and exhaust valves will demonstrate that the valves are not blocked from closing.
If containment is open, the operators can close the containment purge and exhaust from the control room upon high radiation detected in containment. Also the Surveillance will demonstrate that each valve is capable of being closed by an OPERABLE containment purge and exhaust isolation signal The Surveillance is performed every 7 days during CORE ALTERATIONS or movement of irradiated fuel assemblies within contain,,;ent. Tne Surveillance interval is selected to be commensurate with the normal duration of time to complete fuel handling operations. A surveillance before the start of refueling operations will provide two or three surveillance verifications during the applicable period for this LCO.
i                                SR 3.9.5.2 This Surveillance demonstrates that each containment purge and exhaust valve actuates to its isolation position on manual initiation. The Frequency is in accordance with the Inservice Testing Program.
REFERENCES               1. AP600 SSAR. Section 15.7.4
: 2. NUREG-0800. Section 15.7.4. Rev.1. July 1981.
l
!                                3. NRC Request for Additional Information (RAI) 480.1159F        ]
                 .. :=. . - . . --
                                                  ==:_-=_._                             _
l (continued)
       .AP600                                            B 3.9-5       DRAFT       March 31, 1998 1
!-                                                                                                  l b

t' VAS and VFS l
3.9.6 l                                               '3.9  REFUELING OPERATIONS-l                                                3.9.6 Radiologically Contolled Area Ventilation System (VAS) and Containment Air Filtration System (VFS) l                                               .LCO 3.9.6           VAS shall be operating and VFS shall be OPERABLE.
                                                                     ............................ Notes..-........................
: 1. This LC0 applies to the VAS subsystem that services the fuel handling area of the auxiliary building, t.
7
                                               ' APPLICABILITY:      During movement of irradiated fuel assemblies in the fuel i-                                                                        building.
ACTIONS' CONDITION REQUIRED ACTION.         COMPLETION TIME' f
l                                                 A. Both trains of VAS          A.1      Suspend movement of    Immediately subsystem not                        irradiated fuel operating                            assemblies in the fuel building.
0_R r                                                     Both trains of VFS l                                                     not OPERABLE.
l
(
l l
l
{
AP600-                                3.9-30 DRAFT                    March 27. 1988 1

VAS and VFS 3.9.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1              Operate each VFS train for > 10 continuous  Within 31 days hours with the heaters operating,           prior to fuel movement l
l                        SR 3.9.6.2              Verify the VAS fuel handling area subsystem 24 months i
aligns to the VFS filtered exhaust on an actual or simulated actuation signal.
SR 3.9.6.3              Verify one VFS exhaust train can maintain a 24 months on a negative pressure in the fuel handling area STAGGERED TEST with respect to atmospheric pressure during  BASIS the post-accident mode of operation.
l AP600                                       3.9-31 ORAFT                 March 27. 1988

VAS and W5                                                                     1 B 3.9.6 B 3.9 REFUELING OPERATIONS B 3.9.6 Radiologically Contolled Area Ventilation System (VAS) and Containment Air Filtration System (VFS)
BASES
_=     -
BACKGROUND                                                     The radiologically controlled area ventilation system (VAS) serves the fuel handling area of the auxiliary building, and the radiologically controlled portions of the auxiliary and annex buildings. except for the health physics and hot machine shop areas which are provided with a separate ventilation system (VHS). If high airborne radioactivity is detected in the exhaust air from the auxiliary or annex buildings, the VAS supply and exhaust duct isolation dampers automatically close to isolate the affected area from the outside environment and starts the containment air exhaust air subsystem. The VFS prevents exfiltration of unfiltered airborne radioactivity by maintaining the isolated zone at a slightly negative pressure with respect to the outside environment and adjacent unaffected plant areas.                                              The airflow rate through the exhaust fan is maintained at a constant value by modulating the fan inlet vanes. An outside air makeup damaer modulates to control the exhaust airflow rate througn tie HEPA and charcoal filters to maintain the isolated area (s) at a slightly negative pressure' relative to the clean areas.
For a fuel handling accident, the AP600 dose analysis does not rely on the operability of the VAS or VFS to meet the offsite radiation exposure limits. This LCO is 3rovided as i                                                                                                                          an additional level of defense against the possi)ility of a l                                                                                                                          fission product release from a fuel handling accident. If I
the VFS exhaust air filtration units are operational and ac power is available. they may be used to support post-event recovery operations. The plant vent high range radiation detectors monitor effuents discharged from the plant vent to the environment.
The containment air filtration system consists of two 100 percent capacity supply air handling units, a ducted supply and exhaust air system with containment isolation valves andpiping, registers.. exhaust fans. . filtration units.
automatic controls and accessories.
(continued)
AP600                                                                                        B 3.7-66 DRAFT                            March 31. 1998

VAS and VFS                   I B 3.9.6 1    ,
l                                BASES (continued)
BACKGROUND                              The filtration units are connected to a ducted system with (continued)                            1 solation dampers to provide HEPA filtration and charcoal adsorption of exhaust air from the containment. fuel handling area. radiologically controlled areas of the auxiliary and annex buildings. A gaseous radiation monitor is located downstream of the exhaust air filtration units in the common ductwork to provide an alarm if abnormal gaseous releases are detected. The plant vent exhaust flow is monitored for gaseous, particulate and iodine releases to the environment. During conditions of abnormal airborne radioactivity in the fuel handling area. auxiliary and/or annex buildings, the VFS exhaust air filtration units provide filtered exhaust to minimize unfiltered offsite releases.
The VAS is described in SSAR section 9.4.3 and the VFS is described in SSAR section 9.4.7. (References 1 and 2).
APPLICABLE                                The VAS and VFS are not required to mitigate the SAFETY ANALYSES                           consequences of the limiting Design Basis Accident (DBA).
which is a fuel handling accident. The analysis of the fuel handling accident, given in Reference 3. assumes that all fuel rods in an assembly are damaged. The DBA analysis of the fuel handling accident does not assume that the VAS or VFS provides a filtered exhaust, and their operation would reduce the consequences of the fuel handling accident.
This specification is included in accordance with NRC direction per Reference 3.                                                                              .
LC0                                       One train of the VAS is required to be operating to provide for monitoring of potential releases from the fuel area.                                                  {
One train of the VFS is required to be OPERABLE to reduce                                                 l the consequences of a fuel handling accident by filtering the fuel building atmosphere.
The VAS is considered operating when the subsystem that services the fuel area of the auxiliary building is                                                       l operating. The VFS is considered OPERABLE when its                                                        i associated:                                                                                               l 1
(continued)
:                              AP600                                                     8 3.7-67 DRAFT                       March 31. 1998

l'                                                                                           .
VAS and VFS B 3.9.6 i,
BASES (continued)
LC0               a. Fan is OPERABLE:                                                                           l l                                                                             (continued)
: b. HEPA filter and charcoal adsorber are not excessively                                      ;
restricting flow, and are capable of performing their                                      i filtration function: and
: c. Heater, ductwork, valves. and dampers are OPERABLE.
and air circulation can be maintained.
APPLICABILITY      During movement of irradiated fuel in the fuel handling area, the VAS is operating to monitor radioactivity in the fuel area of the auxiliary building, and the VFS is OPERABLE to alleviate the potential consequences of a fuel handling accident.                                                                                        i ACTIONS             A.1                                                                                              ;
With both trains of VAS inoperable, action must be taken to start one train of VAS immediately. If the system is not placed in o3eration this action requires suspension of fuel
;                                                                                               movement w1ich precludes a fuel handling accident. This i
does not preclude the movement of fuel assemblies to a safe                                      ,
position.                                                                                         '
l When two trains of the VFS are inoperable during movement of irradiated fuel assemblies in the fuel building, action must
!                                                                                               be taken to place the unit in a condition in which the LC0 does not apply.                              Action must be taken immediately to suspend         j l                                                                                               movement of irradiated fuel assemblies in the fuel building.
This does not preclude the movement of fuel to a safe                                            i position.                                                                                        i l                                                                                                                                                                                                l SURVEILLANCE        SR 3.9.6.1 REQUIREMENTS               .                                                                                         ,
i                                                                                               Standby systems should be checked Periodically to ensure that they function properly. As tie environmental and normal operating conditions on this system are not severe.
l testing each train within one month prior to fuel movement l_                                                                                              provides an adequate check on this system. Operation of the (continued)
,                                                                          AP600                                B 3.7-68 DRAFT                                                 March 31. 1998

l                                                                                                                                                                                                                                                           -
VAS and VFS l           '.                                                                                                                                                                                                                                                                                                                                                                                B 3.9.6 i i BASES (continued)
SURVEILLANCE                                                                                                                                                           heater dries out any moisture accumulated in the charcoal REQUIREMENTS                                                                                                                                                            from humidity in the ambient air.
(continued)
SR 3.9.6.2 This SR verifies that the VAS fuel handling area subsystem aligns to the VFS and that the VFS train starts and operates on an actual or simulated actuation signal. The 24 month l                                                                                                                                                                                                                                                                                   Frequency is consistent with Reference 4.
1 SR 3.9.6.3 l                                                                                                                                                                                                                                                                                  This SR verifies the integrity of the fuel handling area of
                                                                                                                                                                                                                                                                             .the auxiliary building enclosure. The ability of the VAS l                                                                                                                                                                                                                                                                                  and VFS to maintain negative pressure in the fuel handling i                                                                                                                                                                                                                                                                                  area of the auxiliary building with respect to potentially i
uncontaminated adjacent areas is periodically tested to verify proper function of the VAS and VFS. During the post-accident mode of operation, the VAS fuel handling area '
subsystem aligns to the VFS filtered exhaust subsystem, and the VFS is designed to maintain a slight negative pressure in the fuel handling area of the auxiliary building to prevent unfiltered and unmonitored LEAKAGE.                              The VFS is designed to maintain a slight negative pressure with respect l
to atmospheric pressure. The Frequency of 24 months is consistent with the guidance provided in NUREG-0800.
Section 6.5.1 (Ref. 5).
A 24 month Frequency (on a STAGGERED TEST BASIS) is consistent with Reference 4 i
REFERENCES                                                                                                                                                               1.                             AP600 SSAR. Section 9.4.3.
: 2.                              AP600 SSAR. Section 9.4.7.
!                                                                                                                                                                                                                                                                                  3.                              SSAR. Section 15.7.4.
: 4.                              Regulatory Guide 1.52 (Rev. 2).
: 5.                              NUREG-0800. Section 6.5.1. Rev. 2. July 1981.
: 6.                              NRC Request for Additional Information (RAI) 480.1159F
                                                                                                               .                                   .- = .. =                                                                                                                                                    --      -
                                                                                                                                                                                                                                                                                                                           ~ . . = - -
l AP600                                                                                                                                                                                                             B 3.7-69 DRAFT                    March 31. 1998 i

                             @ Westinghouse                                                 FAX COVER SHEET Recipient Information                          Sender Information
,                               Date:        3 /3, /9g                        Name:      D. Lindgren To:         Bill Huffman                      Location:  WEC E 330 Phone:                                         Phone:
(301) 415-1141                               (412) 374 4856 Facimile:                                      Facimile:
(310) 415 2002                               BeB: (412) 374 4887 Company:     U.S.NRC                                      WIN 284 4887 Location:    Rockville, MD Cover + Pages       1+    6 The following pages are being sent from the Westinghouse Energy Center, Monroeville, PA.
If there are any problems during this transmission, please call the sender or WIN 284-6529 or Bell (412) 374-6529.
comments:
ATYkAD              AA E       c/4AN666 Yo                  R E'msE srAs m s fh.u        T HE SS AR               F ~R      ~Pi4 iiv T       A ivh          w 'rnug TtlfSf              & IIA /JG F '        N '2- u 8E              w        (< E v. 2 t s
: 1. Introduction end Gsneral Description cf PI:nt Ein EE E!
Criteria      Referenced                    AP600 Section       Criteria                      Position                                            CarificatiorvSummary Description of Exceptions Reg. Guide 1.54, Rev. O, 6n3 - Quality As%rance Requirements for Protective Coatings AppIled to Water Cooled Nuclear Power Plants l General       ANSI N101.4-1972               Exception                                           Some coatings inside containment are nonsafety-related and satisfy appropriate ASTM Standards.
See subsection 6.l.2 for additional information.
Application is controlled by procedures using qualified personnel to provide a high quality I
product. The paint materials for nonsafety related l
coatings inside the containment are subject to l
10CFR Part 50 Appendix B Quality Assurance I
requirements. De standards referenced in the l
Regulatory Guide are not current. He Combined l
License applicant prepares the programs for I
                                                                                                            ;afety related coatings. see subsection 6.1.3, and 1                                                                                                                                                       l for procurement of nonsafety-related coatings       I l
inside containment. An evaluation is made to        {'
l show that failure of the nonsafety-related coatings does not prevent the function of safety related      j systems.                                             '
1 C.!            ANSI N101.41972                Exception                                           The standards referenced are not current.
I                ANSI N45.2-1971                                                                    Appropriate current standards including ASME l
i
'                                                                                                           NQA-1 are followed to develop the quality I
assurance program for safety related coatings and I
for procurement of nonsafety-rclated coatings I
inside containment.        He quality assurance I
program for safety-related coatings conforms to I
the requirements of ASME NQA-I 1983 as i                                                                                                   endorsed in Regulatory Guide 1.28.
Revision: 22 W-Westinghouse                                IA-25                                                                              APril 6,1998 w _______________________ _

e
                                                   =        .
E
                                                            ?
l                                                            1. Introduction end General Description of Pisnt e
Criteria    Referenced                       AP600 Section     Criteria                         Position                           ClarificatforvSununary Description of Exceptions l C.2           ANSI N101.4-1972                 Exception l-                                                                                  The standard referenced is not current.
Appropriate current standards are followed for l
safety related coatings.
I C.3           ANSI N101.4-1972                 Exception I
The standard referenced is not current.
Appropriate current standards are followed for i
safety-related coatings.
I    C.4         ANSI N101.4-1972                 Conforms I
The standard referenced is not current. Guidance for the control of cleaning and other material I
used on stainless steel material is provided in l
Regulatory Guides 1.37 and 1.44. Subsections l
l 5.2.3.4 and 6.1.1.2 address the control of processes used on stainless material for safety-I related piping and components.
Revision: 22 April 6,1998                                      1 A-26                                                  [ WB5tilighouse
: 6. Engineered Sciety Factures                                                                                                                          I l~6.1.2.1.6               Quality Assurance Features l                         A nun.ber of quality assurance features provide confidence that the coating systems inside the containment, on the exterior of the containment vessel and in potentially contaminated areas outside containment will perform as intended. These features enhance the ALARA program l                         and enhance corrosion resistance. The features are discussed in the following paragraphs.
Revision: 22 Y W85tingh0088                                                                                                                             6.1-9 April 6,1998

n .: :m:                                                                                                                                                                                   I
: 6. Engineered Safety Fectures Safety related coatings ne quality assurance program for safety-related coatings conforms to the requirements of ASME NQA t-1983 as endorsed in Regulatory Guide 1.28. Safety related coatings meet the pertinen: provisions of 10CFR Pan 50 Appendix B to 10CFR Part 50. He safety-related coatings are consistent with the positions of Regulatory Guide 1.54, " Quality Assurance Requirements for Protective Coatings Applied to Water-Cooled Nuclear Power Plants" He safety-related coatings used in the AP600 are tested for radiation tolerance for performance under design basis accident conditions. Where decontaminability is desired, the coatings are evaluated for decontaminability. He coating applicator submits and follows acceptable procedures to control surface preparation, application of coatings and inspection of coatings.
De painters are qualified and certified, and the inspectors are qualified and certified.
The safety-related inorganic zine coating used on the inside and outside surface of the containment shell is inspected using a non-destructive dry film thickness test and a MEK rub test. Rese inspections are performed after the initial application and after recoating. Long term surveillance of the coating is provided by visual inspections performed during refueling outages. Other inspections are not required.
The procurement, application, and monitoring of safety-related coatings are controlled by a                                                                                       I program prepared by the Combined License applicant, (refer to subsection 6.1.3.2).
l l            Refer to Table 6.1-2 for identification of safety-related coating applications in the AP600.
l            Nonsafety Related Coatings The use of nonsafety-related coatings inside containment is based on the use of selected types of coatings and the properties of the coatings. To preclude the use of inappropriate coatings, the procurement of the nonsafety-related coatings used inside containment is considered safety-related.
Appendix B to 10 CFR Part 50 applies to procurement of coatings used inside containment on intemal structures, including walls, floor slabs, structural steel, and the polar crane, except for such surfaces located inside the chemical and volume control system room # 11209.
Nonsafety-related coatings used in the chemical and volume control system room are not subject to procurement under 10 CFR 50, Appendix B, because the room is connected to the containment in a limited way through a drain line. In addition, the drain line is routed to the waste liquid processing system sump which is located well below and separate from the                                                                                            i recirculation screens. The specified nonsafety-related coatings used inside containment are tested for radiation tolerance and for performance under design basis accident conditions.
l Where decontaminability is desired, the coatings are evaluated for decontaminability.
ne application, inspection and monitoring of nonsafety-related coatings used inside
!                                          containment are not classified as safety related as shown in Table 6.1-2. De application, inspection and monitoring of nonsafety-related coatings are controlled by a program prepared Revision: 22 April 6,1998                                                                                                                            6.1-10                         T Westinghouse

lt
                                                                                                                     =     m
: 6. Ergineered S:f.ty Fe-tures                                                                                      -
l by the Combined License applicant. This program is not subject to 10 CFR 50, Appendix B, l              quality assurance requirements.
l              Due to the use of modularized constmetion, a significant portion of the containment coatings are shop applied to the containment vessel and to piping, structural and equipment modules.
     !             This application of coatings under controlled shop conditions provides additional confidence that the coatings will perform as designed and as expected.
De coatings used in radiologically controlled areas outside containment are tested for radiation resistance and evaluated for decontaminability; they are not specified to be design basis accident tested. Where practical, the same coating materials are used in radiologically controlled areas outside containment as are used inside containment. This provides a high level of quality and optimizes maintenance painting over the life of the plant.
6.1.2.2     Other Organic Materials A listing of other organic materials in the containment is developed based on the specific type of equipment and the supplier selected to provide it. Materials are evaluated for potential interaction with engineered safety features to provide confidence that the performance of the engineered safety features is not unacceptably affected.
6.1.3       Combined License Information Items 6.1.3.1     Procedure Review Re Combined License applicants referencing the AP600 will address review of vendor fabrication and welding procedures or other quality assurance methods to judge conformance of austenitic stainless steels with Regulatory Guides 1.31 and 1.44.
6.1.3.2     Coating Program ne Combined License applicants referencing the AP600 will address preparation of a program to control procurement, application, and monitoring of safety-related coatings. De program for the control of the use of safety-related coatings will be consistent with subsection 6.1.2.1.6.
6.1.4       References I               1. NUREG-0797, " Safety Evaluation Report related to the operation of Comanche Peak I                     Steam Electric Station, Units I and 2."
: 2. Bolt, R. O. and J. G. Carroll, " Radiation Effects on Organic Materials", Academic Press, New York,1963, Chapter 12.
l
: 3. Parkinson, W. W. and O. Sisman, "he Use of Plastics and Elastomers in Nuclear i
Radiation", Nuclear Engineering and Design 17 (1971), pp 247-280 North-Holland Publishing Co., Amsterdam.
Revision: 22                        l l        W-Westinghouse                                   6.1-11                                              APril 6,1998 i
4 I                                                                                                                                                    >
L                                                                                                                                                    l

&[ MWWestinghouse                                 FAX COVER SHEET RECIPIENT INFORMATION                            SENDER INFORMATION DATE:             N/ AIL l, /$b                     NAME:             {M hygg TO:                                                 LOCATION:         ENERGY CENT R -
M/ b/bC8M                                   EAST    32.6           )
PHONE:            FACSIMILE:[ foe) /t$".2.179       PHONE:            Omce:(4tg D Q ,O p.
COMPANY:                                            Facsimile:        wirt Mbh                                                              284 4887 outsede: (412)374-4887 LOCATION:         @/tr( [J. seer 0-/0 b2y, sk mr,ab
    - . P.            4.     /
The fogowing pages are being sent from the Westinghouse Energy Center, East Tower, Monroevule, PA. N any problems occur during this transmission, please can:
WIN: 284 p2K Bev )er Outside:(412)374-6529 COMMENTS:
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I
: 3. Design of Struct res, Ccmponents, Equipmelt, cod Systems 1
3.9.3         ASME Code Classes 1,2, and 3 Components, Component Supports, and Core Support                              l Structures
(
Pressure-retaining components, core support structures, and component supports that are                    i safety-related are classified as Class A, B, or C (see subsection 3.2.2) and are constructed               I according to the rules of the ASME Code, Section III, Division 1.               As noted in subsection 3.2.2, Classes A, B, and C mechanical components meet the requirements of                       1 Code Classes I,2, and 3 respectively.
This subsection discusses the application of the ASME Code to safety-related components and core support structures, the operability of pumps and valves, the design and installation criteria for overpressure protection devices, automatic depressurization devices and the requirements for component supports.
Section 3.8 addresses the loads, loading combinations, and stress limits for structures, including containment.                                                                                     j i
The ASME Code, Section III requires that a design specification be prepared for ASME                       j Class I, 2, and 3 components. The specification conforms to and is cenified to the requirements of ASME Code, Section III. The Code also requires a design repon for safety-related components, to demonstrate that the as-built component meets the requirements of the relevant ASME Design Specification and the applicable ASME Code.
The design specifications and design repons will be completed by the Combir.ed License applicant or his agent. Design specifications for ASME Class 1,2, and 3 components and piping are prepared utilizing procedures that meet the ASME Code. The design repon includes as-built reconciliation.
I I                The as-built reconciliation includes the evaluation of pipe break dynamic loads, changes in I                suppon locations, construction deviations, and the completion of the small bore piping I                analysis. Confirmation of the following is also included in the as-built reconciliation of the I                safety related piping and components :
I I                -
Completion of the ASME Code fatigue analysis for Class 1 pipe for the following I                      systems: Reactor Coolant System (RCS), Passive Core Cooling System (PXS),
I                      Chemical and Volume Control System (CVS), Normal Residual Heat Removal System I                      (RNS),
I I
* Completion of the time-history seismic analysis for the reactor coolant loop piping (hot I                      legs, cold legs) that accounts for the     15 percent peak broadening as described in 1                      Section 3.7.2.5, 1
l                -
Completion of the seismic analyses utilizing the amplified floor cesponse spectra l
l                      described in Section 3.7.2 for the following systems: Reactor Coolant System (RCS),
I                      Passive Containment Cooling System (PCS), Passive Core Cooling System (PXS),
i                      Chemical and Volume Control System (CVS), Steam Generator (SGS).
Revision: 22
[ W85tirigt)0058                                 3.9-45                                     April 6,1998 t                                                                                                                   . _ _ _ _ _

p    @ Westinghouse                                                 FAX COVER SHEET i
Recipient Information l
Sender Information Date:       4/2/98                             Name:      D. Undgren To:         S. Magruder                        Location:
l                                                                WEC E 330 Phone:                                         Phone:     (412) 374 4856 Facimile:
(301) 415-2002                     Facl mile: Bell: (412) 374 4887 Company:
U.S.NRC                                       WIN 284 4887 Locadon:     Rockville MD Cover + Pages        1+   Q l   The following pages are being sent from the Westinghouse Energy Center, Monroeville, PA.
If there are any problems during this transmission, please call the sender or WIN 284-6529 or     !
Bell (412) 374 6529.
1 Comments: The table below identifies the open items closed with WCAP-13054 and
                                                                                                      )
WCAP13[559.
OITS       DSER/RAl/FSER       WCAP l     1801       3.9.3.3-2           13054
;     1803       3.9.3.3-4           13054 5000      210.229              13559
;     5759      650.2F               13559 j
5760      650.3F               13559 l    5761       650.4F               13559 5762      650.5F               13559 5763       650.6F               13559 5764       650.7F               13559 5765       650.8F               13559
!    5972       650.10F              13559 6171       210.232F             13054
;    6172       210.233F             13054 6329       650.27F              13559 6333       650.31F              13559
;    6335       650.33F              13559 6336       650.34F              13559 6637       650.37F             13559 6638       650.38F             13559 t
l

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DATE:                 /)pait 9,   /99g                Name:             % W,my TO:                     Wo Qu4/                        LOCATION:
ENERGY CENTER - EAST PHONE:                                                 PHONE:
Office: 412 374 S290 COMPANY:                                               Facsimile:       win:        284 5535 L4 f A)#.C.                                    outside: (412)374 5535 LOCATlON:
I Yki                   ~N-YISEDOL
!      C@ver + Pages          1+l The following pages are being sent from the Westinghouse Energy Center, East Tower, Monroeville, PA. If any problems occur during this transmission, please call:
WIN: 284-5489 (Wanda)/4031 (Delina) or Outside (4121374 5489/4031.
COMMENTS:
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Liquid Radwaste System Simplified Piping and Instrumentation Diagram (REF) WLS Revision: 23 Draft                                                                      11.2-44                            W W85tingh00Se L- _

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                                @ Westinghouse                                                  FAX COVER SHEET Recipient Information                            Sender Information Date:        y /u / 9g                         Name:       D. Lindgren To:         Joe Sebrosky                       location:   WEC E 330 Phone:                                         Phone:
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i (310) 415 2002                                 Belt (412) 374 4887 Company:    U.S.NRC                                        WIN 284 4887 Location:   Rockville, MD Cover + Pages       'l +  l The following pages are being sent from the Westinghouse Energy Center, Monroeville, PA.
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       @ Westinghouse                                                                                FAX COVER SHEET Recipient Information                                                   Sender information                    i Date:              y/,g/9g                                           Name:       D. Wagen i
l         To:               Joe Sebrosky                                       Location:   WEC E 330 Phone:                                                                Phone:
(301) 413-1132                                                 (412) 374 4856
                                                                                                                                          )
l        Facimile:                                                             Facimile:
(310) 415-2002                                                 Bell: (412) 374 4887 l
l        Company:           U.S.NRC                                                        WIN 284 4887                                   !
l location:          Rockville, MD Cover + Pages             1+3 The following pages are being sent from the Westinghouse Energy Center, Monroeville, PA.
l      If there are any problems during this transmission, please call the sender or WIN 284 6529 or l      Bell (412) 374 6529.
Comments:
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: 1. Introducti:n end Gen r:1 Descripti:n cf Plint 4
Criteria                              Referenced       AP600 Section                               Criteria         Position               Clarification / Summary Description of Exceptions Reg. Guide 1.54, Rev. O, 6/73 - Quality Assurance Requirements for Protective Coatings Applied to Water Cooled Nuclear Power Plants General                              ANSI N101.41972   Exception             Some coatings inside containment are nonsafety.
related and satisfy appropriate ASTM Standards.
See subsection 6.1.2 for additional information.
Application is controlled by procedures using qualified personnel to provide a high quality product. He paint materials for nonsafety-related                     j i
coatings inside the containment are subject to 10CFR Part 50 Appendix B Quality Assurance l                                                                                       requirements. De standards endorsed ::f::::::d                        I in the Regulatory Guide are not current. He j
Combined License applicant is responsible for i                                                                                       preparing peepawethe programs for safety related I                                                                                       coatings, =: ::b= de            6.!.3,   and for procurement of nonsafety-related coatings inside l                                                                                       containment.      See subsection 6.1.3 for the I                                                                                       Combined License information item.              An
: :!::d : :: rt :: de: S:: f: iter: of h:
nen=f::y ::!:::d :::dn;;; de:: ::: p::v:n* 'h:
l                                                                                                                           fune:::: ef =f::y ::!:::d :y:::=:.
l          C.I                                 ANSI N101.41972  Exception               De standards endorsed ::f::::::d are not ANSI l                                                                                  N45.21971                                current. Appropriate current standards including ASME NQA 1 are followed to develop the l                                                                                                                           quality assurance program for safety related coatings and for procurement of nonsafety-related coatings inside containment.         De quality assurance program for safety related coatings.
conforms to the requirements of ASME NQA t-1983 as endorsed in Regulatory Guide 1.28.
Revision: 23 1A 25                                              DRAFT,1998 W West lfigh00sg t                                                                                                                                                                     _.__._____..___._________o

3
                                                                                               =. =
E                                        5
: 1. Introduction and Generzl Description of Pirnt Criteria                                             Referenced       AP600 Section                                              Criteria         Position         Clarification / Summary Description of Exceptions l
Appropriate current standards for coating quality I
assurance are used in conjunction with l                                                                                                         Regulatory Guide 1.28.
I                  C.2                                                  ANSI N101.4-1972 Exception        The standard endorsed ::ferenced is not current.
I                                                                                                          Appropriate current standards are followed by the l                                                                                                          Combined License applicant for safety related coatings.                                         !
l C.3                                                                    ANSI N101.4-1972 Exception        'Ihe standard endorsed ::f::enced is not current.
l                                                                                                          Appropriate current standards are followed by the l                                                                                                          Combined License applicant for safety-related coatings.
I                  C.4                                                   ANSI N101.4-1972 Conforms         P: cand=4::f :::::d b nc: = :- Guidance for the control of cleaning and other materi:1 used on stainless steel material is provided in Regulatory Guides 1.37 and 1.44. Subsections 5.2.3.4 and 6.1.1.2 address the control of processes used on stainless material for safety-related piping and components.
I I
I Revision: 23 DRAFT,1998                                                                 1A 26                                W W85tingh00S8

m=    =E                    l
: 6. Enginnred S:fety Fec.tures                                                                                E by the Combined License applicant. This program is not subject to 10 CFR 50, Appendix B, quality assurance requirements.
Due to the use of modularized constmction, a significant portion of the containment coatings are shop applied to the containment vessel and to piping, structural and equipment modules.
This application of coatings under controlled shop conditions provides additional confidence that the coatings will perform as designed and as expected.
The coatings used in radiologically controlled areas outside containment are tested for                                i radiation resistance and evaluated for decontaminability; they are not specified to be design                       I basis accident tested. Where practical, the same coating materials are used in radiologically controlled areas outside containment as are used inside containment. This provides a high level of quality and optimizes maintenance painting over the life of the plant.
6.1.2.2       Other Organic Materials A listing of other orgalic materials in the containment is developed based on the specific type of equipment and the supplier selected to provide it. Materials are evaluated for potential                         i interaction with engineered safety features to provide confidence that the performance of the engineered safety features is not unacceptably affected.
{ !
6.1.3         Combined License Information Items 6.1.3.1       Procedure Review The Combined License applicants referencing the AP600 will address review of vendor fabrication and welding procedures or other quality assurance methods to judge conformance of austenitic stainless steels with Regulatory Guides 1.31 and 1.44.
6.1.3.2       Coating Program l
l               The Combined License applicants referencing the AP600 will provide add = p=paration of a program to control procur: ment, application, and monitoring of safety-related coatings. The                     a program for the control of the use of safety-related coatings will be consistent with subsection 6.1.2.1.6.                                                                                              ;
I 6.1.4          References                                                                                                        !
i
: 1. NUREG-0797,." Safety Evaluation Report related to the operation of Comanche Peak                            l Steam F.lectric Station, Units I and 2."                                                                     ;
: 2. Bolt, R. O. and J. G. Carroll, " Radiation Effects on Organic Materials", Academic Press, New York,1963, Chapter 12.
: 3. Parkinson, W. W. and O. Sisman, "The Use of Plastics and Elastomers ii Nuclear Radiation" Nuclear Engineering and Design 17 (1971), pp 247-280, North-Holland Publishing Co., Amsterdam.
Revisiom 23
[ Westingh00S8                                       6.1 11                                   DRAFT,1998 l
t                                                                                                                                        ,

3 s   @ Westinghouse                                                                              FAX COVER SHEET Reciplent information                                                        Sender information Date:        e.f /'j g/pg                                                   Name:      D. Lindgren To:         Joe Sebrosky                                                    location:  WEC E 330 Phone:                                                                      Phone:
(301) 415-1132                                                             (412) 374 4858 Facimlie:                                                                   Facimile:
(310) 415 2002                                                             Bell: (412) 374 4887 Company:    U.S.NRC                                                                    WIN 284 4887 Location:   Rockville, MD Cover + Pages      1+     (
The following pages are being sent from the Westinghouse Energy Center, Monroeville, PA.
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PftL       o on %sevssa on 'Yoh Af,                                                              ,ATrh&Hdb          IS 6Aov ah A     m AA nur o p           Yvt            SSAR                                 70       60M rss             tu MR s
           ) D SL          FOR         S 5irst ic.                                   A/VALfpf GJ b $>t                 '

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: 3. Design cf Structures, Ccmponrnts, Equipm:nt, and Systems i
soil profiles include a hard rock site, a soft rock site, an upper bound soft to-medium soil site and a soft-to-medium soil site. The shear wave velocity profiles and related governing parameters of the four sites considered are the following:
For the hard rock site an upper bound case for firm sites using fixed base seismic analysis.
For the soft rock site, a shear wave velocity of 2400 feet per second at the ground surface, increasing linearly to 3200 feet per second at a depth of 240 feet, and base rock at the depth of 120 feet.
For the soft-to-medium soil site, a shear wave velocity of 1000 feet per second at ground surface, increasing parabolically to 2400 feet per second at 240 feet, base rock l                   at the depth of 120 feet, and ground water is assumed at grade level.
For the upper bound soft-to-medium soil site, a shear wave velocity of 1414 feet per second at ground surface, increasing parabolically to 3394 feet per second at 240 feet, l                   base rock at the depth of 120 feet, and ground water is assumed at grade level. ,ne initial soil shear modulus profile is twice that of the soft-to-medium soil site, i
ne strain-dependent shear modulus curves for the foundation materials, together with the corresponding damping curves, are shown in Figures 3.7.1-14 and 3.7.1-15 for rock material and soil material, respectively. The shear wave velocity profile for the design soil profiles, with variation of depth to base rock,is shown in Figure 3.7.1-17.
Free field analyses are performed for each design soil profile and acceleration response 9xtra are calculated at the foundation level of the nuclear island as described in subsection 2A-6.
He envelopes of the horizontal and vertical spectra for the four design soil cases are shown in Figures 3.7.1-18 and 3.7.1-19 respectively, nese envelopes represent the seismic input at l                                                        foundation level for which the AP600 is designed. These spectra are used for comparison with the results of site specific soil amplification studies as described in subsection 2.5.2.1.
ne AP600 design for the site parameters given in Table 2-1 is implemented using analyses for the four soil conditions described above. These four soil conditions consist of competent material. They do not include profiles consisting of one or more thin layers overlying competent material (Standard Review Plan 3.7.2). The shear wave velocity parameter in Table 2-1 excludes these shallow soil sites from consideration as a part of design certification.
(                                                        ne AP600 may also be suitable at sites outside the bounds of the site parameters. Rese sites may be demonstrated to be acceptable using the methodology in subsection 2.5.2.2.
Rese site specific analyses demonstrating acceptability of the site would be submitted as part of the Combined License application. De evaluation of the suitability of these sites is not included in design certification.
He AP600 nuclear island consists of three seismic Category I structures founded on a common basemat. De three structures that make up the nuclear island are the coupled Revision: 23                                                                                                                                                                                      i Draft,1998                                                           3.76                                                                                3 W85tingh00S8                           !
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                        @ West'nghouse                                                 FAX COVER SHEET Recipient Information                           Sender Infontation Date:        y / p 7 /y g                      Name:      D. Lindgren l
To:         Bill Huffman                       Location:  WEC E 330 Phone:                                         Phone:     (412) 374 4856 (301) 415-1141 Facimile:                                      Facimile:  Bet (412) 374-4887 (310) 415-2002 Company:    U.S.NRC                                       WIN 284 4887 Location:   Rockville, MD Cover + Pages      1+l The following pages are being sent from the Westinghouse Energy Center, Monroeville, PA.
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4  @ Westinghouse                                                     FAX COVER SHEET Reciplent Information                              Sender Information Date:         L/ /2i /yg                            Name:     D. Lindgren To:          Joe Sebrosky                           Location: WEC E 330 Phone:                                              Phone:
(301) 415-1132                                   (412) 374 4856 Facimile:                                           Facimile-(310) 415-2002                                   Bet (412) 374 4887 Company:     U.S.NRC                                           WIN 284 4887 Location-    Rockville, MD Cover + Pages       1+      i The following pages are being sent from the Westinghouse Energy Center, Monroeville, PA.
If there are any problems during this transmission, please call the sender or WIN 284-6529 or Bell (412) 374-6529.
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76     i prrunz                             o   nn., e> am,                                        ,
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.i L4 i                  SRP 18.2 - Safety Parameter Display System (SPSD) (Rev. O, i1/84)
Exception   he AP600 does not have a separate Safety Parameter Display System i                                              (SPDS). Safety Parameter Display System requirements are integrated into
(.                                             the overall human system interface design to avoid the need for another system that is infrequently used. He Safety Parameter Display System is discussed in subsection 18.8.2. The human system interface design addresses the regulatory requirements for the Safety Parameter Display System included in 10 CFR 50.34 (f) (2) (iv) and NUREG-0737, Supplement 1.
1 i
: 1.                 SRP 18., Appendix A - Human Factors Review Guidelines for the Safety Parameter Display System (SPDS) (Rev. O,11/84) i
)                                  Exception   Section 5 of NUREG-0696 presents the need for human-factors engineering in the design of the Safety Parameter Display System. The Safety Parameter Display System is designed using the implementation plan described in subsection 18.8.1. His implementation plan includes the application of human factors engineering principles that address the criteria of the Human Factors Engineering Program Review Model (NUREG-0711).
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aus l Westinghouse                      FAX COVER SHEET                                 )
l RECIPIENT INFORMATION                            SENDER INFORMATION                '
OATE:                   '//;Uf9f NAME:             5 o e. F3do TO:                                                  LOCATION:        ENERGY CENTER .
8:H        HJb n                                  erst                     4 PHONE:             FACSIMiuli:                       PHONE:           Omce:gYoA7 COMPANY:                                             Facsimile:
* 284-4487
                              /0 U                                        outside: (412)374-4887 LOCATION:
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The following Pages are being sent from the Westinghouse Energy Center, East Tower, Monroevule, PA. N any problems occur during thle transmission, please cell:
WIN: 284 M% Bev )orOutside:(412)374-6529 COMMENTS:          ,
b&           :s    h e- new         s edro ,          fa. 5~ A. 3 Onla'     m;nor dL hn op S              N 3-ve.-     heAn (vtbAe-Q fo 4t te-      too < d in e  ne ea ented       d       4he-        %                   l a   ,                                  ,
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'(-          5. Reactor Coolant System and Connected Systems 5.2.5.2.2     Comrunent Cooling Water System Leakage from the reactor coolant system to the component cooling water system is detected by the component cooling water system radiation monitor, by increasing surge tank level, by high flow downstream of selected components. or by some combination of                i the preceding.                  Refer to Section 11.5, Radiation Monitoring, and subsection 9.2.2. l Component Cooling Water System.
I  5.2.5.2.3      Passive Residual lleat Removal Heat Exchanger Tubes I
l A potential identified leakage path for reactor coolant is through the passive residual heat removal I heat exchanger into the in-containment refueling water storage tank. Identified leakage from the I passive residual heat removal heat exchanger tubes is detected as follows:                                          -
I l
* High temperature in the passive residual heat removal heat exchanger, as monitored and l
alarmed by temperature detectors in the heat exchanger inlet and outlet piping alens the                l I
operators to potential leakage. The location of these instmments is selected to provide early            }
l indication of leakage considering the potential for thennal stratification. The alann serpoint is I             selected to provide early indication of leakage.
I l
* The operator then closes the passive residual heat removal heat exchanger inlet isolation valve I
and observes the pressure indication inside the passive residual heat removal heat exchanger. If I
pressure remains at reactor coolant system pressure, then tube leakage is not present, and the I
high passive residual heat removal heat exchanger temperature is indicative of leakage through I             the outlet isolation valves.
I l
* If the operator observes a reduction in pressure, then passive residual heat removal heat i             exchanger tube leakage is present. The operator then observes the change in 'he reactor                  l 1
coolant system inventory balance when the passive residual heat removal heat exchanger inlet               i l
isolation valve is closed. The difference in the reactor coolant system leakage when the                 i i
isolation valve is closed. identifies the passive residual heat removal heat exchanger tube l             leakage rate.
5.2.5.3                                  Collection and Monitoring of Unidentified Leakage Position 3 of Regulator . Guide 1.45 identifies three diverse methods of detecting unidentified leakage. AP600 use two of these three and adds a third method. To d:tect unidentified leakage inside containment, the following diverse me' hods may be utilized to quantify and assist in locating the leakage:
Containment Su'mp Level                                                    i Reactor Coolant System Inventory Balance Containment Atmosphere Radiation Mh Revision: 23 T Westinghouse-                                              5.2-27                              April 21,1998

  !c westinghouse                              FAX COVER SHEET RECIPIENT INFORMATION i
SENDER INFORMAliUN OATE:
4//'/sc 29 /9 f?                       Name:
bdNE [/' tie /)
TO:                         7c'7////           6V/ L3cp            LOCATION:
ENERGY CENTER EAST PHONE:
                                 $-/_ [30/) #tf- 22 79                  PHONE:
Office: 412 374 6ffo COMPANY:
Facsimile:
Nd                                                    win:        284 5535 outside: (4121374 5535 LOCATION:           ,        CJ//trE $wr Cover + Pages                1+
The fo!!owing pages are being sent from the Westinghouse Energy Center, East Tower, Monroeville, PA. If any problems occur during this transmission, please call:
WIN: 284 5489 (Wanda)/4031 (Defina) or Outside (412)374 5489/4031.
YCWA-f                -
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RESPONSES TO NRC REQUEST FOR ADDITIONAL INFORMATION OITS 6785 - ITAAC Open Item RAI for AP600 ITAAC from Electrical Engineering Branch (NRR/EELB)
Per telecon with the staff on 4/8/98. The NRC requested that an ITAAC be added to Section 2.6.1, Main ac Power System, to justify the assumption in the safety analysis that the RCPs receive power for at least three seconds following cenain events.

===Response===
We will revise CDM 2.6.1 as shown below.
SSAR Revision:
None ITAAC Revision:
Item 4f will be added to CDM 2.6.1 as follows:
l 4.J)                     The ECS provides a reverse power trip of the generator circuit breaker which is blockedfor at
                          \                          least 15 secondsfollowing a twbine trip.
l    4.f) The ECSprovides a                            Tests on the as built ECS          The generator circuit                     !
l    reverse power trip of the                         system will be conducted by        breaker trip signal does not              l
                          )    generator circuit breaker which                   simulating a twbine trip signal    occw until at least IS l    is blockedfor at least 15                        followed by a sinadated             seconds ayer the simulated                ,
l    secondsfollowing a twbine trip.                   reverse power condition. The       twbine trip.                              l
                          \                                                     generator circuit breaker trip                                                !
l                                                      signal will be nwnitored.
i OITS 6785-1 l

l 1'
NRC FSER OPEN ITEM g.-
                                                                                                                                                ~
                                                                                                                                                  ==
l   Open item, OITS #6784 l   Per telecon with NRC staff on 4/21/98 on pipes with fibrous insulation that may be impacted by a jet as a result of a pipe break. The staff requested the algorithm ci!acussed in SSAR subsection 6.3.2.2.7.1 item 3 be included in the AP600 Tier 1 material in Table 2.2.3-4, item 8.c.ix).
After discussion with Westinghouse, the staff agreed that additional ITAAC will not be required if Westinghouse supplements SSAR subsection 6.3.2.2.7.1, item 3 by providing discussion in the SSAR why the approach to fibrous insulation is appropriate, particularly with respect to ASME Class 1 piping and postulated pipe break locations inside containment. The discussion in the SSAR should also cover where fibrous insulation will be and woni be located.
Response:                                                                                                                                            1 SSAR subsection will be revised to provide a discussion that justifies the current ITAAC contained in CDM Table 2.2.3 4, item 8.c.ix.
SSAR Change:
Attached is the revised SSAR subsection 6.3.2.2.7.1, item 3.                                                                                         ,
1 iTAAC Change:                                                                                                                                        l 1
None F
t gg                                                                                                                            OliS #67841

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NRC FSER OPEN ITEM Revised SSAR abeection 6.3.2.2.7.1, Item 3 6.3.2.2.7   IRWST and Containment Recirculation Screens The passive core cooling systems has two different sets of screens that are used following a ' OCA; IRWST screens and con"inment recirculation screens. These screens prevent debris from entering the reactor and blocking core cooling passages during a LOCA. These screens are designed to comply with applicable licensing regulations including:
* GDC 35 of 10 CFR 50 Appendix A
* Regulatory Guide 1.82
* NUREG-0897 The operation of the passive core cooling system following a LOCA is described in subsection 6.3.2.1.3. Proper screen design, plant layout, and other factors prevent clogging of these screens by debris during accident operations.                                                                          j l
6.3.2.2.7.1 General Samen Design Crfloria                                                                                        )
: 1) Screens are designe.d to Regulatory Guide 1.82, including:
l Redundant screens are provided for each function                                                         1 Separate locations are used for redundant screens Screens are located well below containment floodup level. Each screen has a                              I coarse and a fine screen, and a debris curb Floors slope away from screens (not required for AP600)
Drains do not impinge on screens Screens can withstand accident loads and credible missiles Screens, have conservative flow areas to account for plugging. Operation of the non safety related normal residual heat removal pumps with suction from the IRWST and the containment, recirculation lines is considered in sizing screens.
System and screen performance are evaluated OITS #6784-2

o NRC FSER OPEN ITEM Mi Screens have solid top cover. Containment recirculation screens have protective plates that are located no more than 10 feet above the top of the screens and extend at least 10 feet in front and to the side of the screens.
Screens are seismically qualified Screen openings are sized to prevent blockage of core cooling Screens are designed for adequate pump performance. AP600 has no safety-related pumps.
Corrosion resistant materials are used for screens                                ,
i Access openings in screens are provided for screen inspection Screens are inspected each refueling
: 2)                                 Low screen approach velocities limit the transport of heavy debris even with operation of normal residual heat removal pumps.
: 3)                                 Metal reflective insulation is used on ASME cdsas f lines because hoy are subject to loss-of-coolant accidents. Meest mApcme houdsdon h sko used an me reacbr vesse( me mactor cocient pum me sesam generatom and on me pressurdrer because mey hew shmey brpe houisson madece areas and mey are bcased abas b hige ASME cdeas f twa As a maut, mey anr autifect bjet hphgement cdurhg bee choodont accidents WM mese restilodons # h unsey met a@nNoent amounds of f2rous debrde me be gerwraded by bee o6condent accidenes because most of me ASMK cdeas f twa em bested hands me bop coniperiments or h he pressurdrer compartment where mere are hw, Fany, houdsted tws met are not ASME cdeas f.
l                                                                                   The pesshe core coctig system usAe roome aho condsh a a@nMcent numtwr of
                                !                                                                                 ASME adese f hws These rooms aho conesh hw,1any, hennsted kws est are l                                                                                 not ASME cdsas f.
                                ]                                                                                 in ordar b pmpfde addWonst mergh, model masone houisalon h used on lines that are subject to jet impingement during loss-of coolant accidents that are not otherwise shielded from the blowdown jet. Insulation located in a spherical region within a        j distance equal to 12 inside diameters of the LOCA pipe break is assumed to be affected by this LOCA when there are intervening components, supports, structures, or other objects. in the absence of intervening components, supports, structures, or other objects insulation in a cylindrical area extending out a distance equal to 45      j inside diameters from the break along an axis that is a continuation of the pipe axis    ;
and up to 5 inside diameters in the radial direction from the axis is assumed to be affected by the LOCA. As a result, fibrous debris is not generated by loss-of-coolant l
accidents.                                                                               l OITS #6784-3

1 s l
1 NRC FSER OPEN ITEM F ~~5
: 4)  Use of coatings designed for post accident conditicns. The coatings used on surfaces located close to the containment recirculation screens are safety related.
The surfaces considered close to the screens are defined in subsection 6.3.2.2.7.3.
Refer to subsection 6.1.2.1.6.
: 5)   The IRWST is enclosed which limits debris egress to the IRWST screens.
: 6)   Containment recirculation screens are located above lowest levels of containment.
: 7)   Long settling times (> 5 hours) are provided before initiation of containment recirculation.
: 8)   Air ingestion Uy safety-related pumps is not an issue in the AP600 because there are no safety related pumps. The normal residual heat removal system pumps are evaluated to show that they can operate with minimum water levels in the IRWST and in the containment.
: 9)   A COL commitment for cleanliness program to limit debris in containment is provided.
e I
O OITS #6784 4 l
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l    e i
:  @ Westinghouse                                                  FAX COVER SHEET                '
Recipient Information                            Sender information Date:        y /7e/p g                        Name      :.J. Lhdgren To:                                           Location:
Joe Sebrosk/                                 sWEC E-330 Phone:                                        Phone (301) 415-1132                                 !412) 374 4858 Facimlie:                                     Facinde:  : Bet (412) 374 4887 (310) 415 2002 Company:    U.S.NRC                                        WIN 284 4887 location:   Rockville, MD
{
Cover + Pages      i+     l The following pages are being sent from the Westinghouse E Energy Center, Monrooville, PA.
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me           in a n                  ~an n                 ,~,           , - - ,            l T* s E         ivetov o              su    Rcv         2.s        vs     A w awss        i NM        U SN(o 'S        G o FS new           e=         m% A r/
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i                   3. Design es hr scictures, Ccmp:n:nts, Equipment, cnd Systenu i
The vertical elevation of the passive containment cooling water storage tank r::iatise to the top of the shield building cylindrical wall at the tension ring will be rmeasured before and after first filling. He change in relative elevation will be compared against the predicted deflection.
A report will be prepared summarizing the test and evaluating the results.
oA nr$Parefoce!
Tier-: are no other in-service testing, requirements for the seismic Category I shield building an: _2uxiliary building. However, during the operation of the plant the condition of these sr2c:cmres should be monitored by the Combined License applicant to provide reasonable c:n65dence that the structures are capable of fulfilling their intended functions.
3.8.4.8     Onsistruction Inspection Qnns:ruction inspection is conducted to verify the concrete wall thickness and quantity of c:nc:: rete reinforcement. 'Ihe construction inspection includes concrete wall thick: ness and 2
mnicorcement expressed in units of in /ft (linear length) equivalent when compared to standard r::nicorcement bar sections. Inspections will be measured at applicable sections e;xcluding dmgrened openings or penetrations. Inspections will confirm that each applicable section pnvindes the minimum required reinforcement and concrete thickness as sinown in "Leie:e 3.8.4-7. The minimum required reinforcement and concrete thickness repn::sents the mm= mum values to meet the design basis loads. Table 3.8.4-7 also indicates the reinforcement pcvinded which may exceed the minimum required reinforcement for the following reasons:
                                 .        Structural margin Ease of construction Use of standardized reinforcement sizes and spacing 3.8.5       Touandations 3.8.5.1     I+= n'iption or the Foundations 1
                                 "he nuclear island structures, consisting of the contamment building, shield builahog, and amiiliary building are founded on a common 6-foot-thick, cast in-place, reinforced concrete b-r foundation. The top of the foundation is at elevation 66'-6'.
Adjemining buildings, such as the radwaste building, turbe building, and annex bminng are stuc:cmrally separated from the nuclear island structures by a 2-inch gap at and below the panne. A 4-inch minimum gap is provided above grade. 'Ihis provides space to prevent              i nre=raction between the nuclear island structures and the adjacent structures during a seismic    l cvemnt. Figure 3.8.51 shows the foundations for the nuclear island structures and the .adjoimng arscxctures.
L=ststance to sliding of the concrete basemat foundation is provided by passive soill pressure   ;
me 2 soil friction. 'Ihis provides the required factor of safety against lateral movement under   !
te most stringent loading conditions.
J Revision:
W westneghouse                                       3.s-57                                 C 4. C-
                                                                                                                    ' w A Fr-

O  W l Westinghouse 4
I
           *"*                                         FAX COVER SHEET RECIPIENT INFORMATION SENDER INFORMATION DATE:                  Yf A7 [9 F'                                                    jve.
Name:                                   Futro TO:                    0,'ll H/fu n                     LOCATION:
ENERGY CENTER - EAST l   PHONE:                30I/415'- //4 (                   PHONE:
Office: 412 374 14AV I'
COMPANY:                                                Facsimile:                     win:
N((                                                                       284 5535 outside: (412)374 5535 LOCATION:
1 Cover + Pages         1+        /
The following pages are being sent from the Wesdnghouse Energy Center, East Tower, Monroeville, PA. If any problems occur during this transmission, please call:
WIN: 284 5489 (Wanda)/4031 (Delina) or Outside (412)374 5489/4031.
COMMENTS:
N ll ,
Hue ve %                    <utsel           ~T~5      3.9.5~ N 3.9.L,.
Ple x e- k v e--        4 % ru;euel ( oroMe_              ,
cmods 3 oe

Containm:nt Pcnctrations 3.9.5 o
3.9   REFUELING OPERATIONS 3.9.5   Containment Penetrations LCO   3.9.5 The containment penetrations shall be in the following status:
: a. The equipment batches closed and held in place by (four) bolts or, if open, ;; alters;tive terrie; h t ;; the cent;ir:;t ;;;.espi;;e -=' the e teid; et. eeste. e ei;11 be is pi;;e, ;;d the containment air filtration system I                           (VFS) shall be OPERABLE and operating te pie.-ide fez n ;ite.isp ef ei; beza; ;;dieesti.-ity in ti; ;;;tei r;;t;
: b. One door in each air lock closed or, if open, the VFS I                           shall be OPERABLE and operating; l                     c. The containment spare penetrations closed or, if open, I                           the VFS shall be OPERABLE and operating;
: d. Each penetration providing direct access from the containment atmosphere to the outside atmosphere either:
: 1. Closed by a manual or automatic isolation valve, blind flange, or equivalent, or
: 2. Capable of being closed by an OPERABLE Containment Isolation signal.
APPLICABILITY:     During CORE ALTERATIONS During movement of irradiated fuel assemblies within containment.
ACTIONS CONDITION                          REQUIRED ACTION                               COMPLETION TIME i
A. One or more             A.1   Suspend CORE                                                Imasediately    !
containment                  ALTERATIONS.
penetrations not in required status and     Alg2 VFS inoperable or not operating.          A.2   Suspend movement of                                         Immediately irradiated fuel assemblies within containment.
AP600                                         3 . 9 '/                          04/98 Draft Amendment P

conteinm:nt Pcn trationo 3.9.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE                          FRF,QUENCY SR     3.9.5.1              verify each required containment             7 days penetration is in the required status.      If one or more of the required containment penetrations is open, ene trai-; ef the VFS shall be OPERABLE and at le'.st one VFS exhaust fan shall be oportting.
SR     3.9.5.2              Verify each required containment           In accordance purge and exhaust valve actuates to       with the the isolation position on ;; cet-.21       Inservice Test I                              - - -
                                         ' " " ' a manual actuation         Program signal.
SR     3.9.5.3              Verify the VFS can maintain a              24 months on a negative pressure in the area              STAGGERED TEST enclosed by the containment and            BASIS alternate barrier with respect to atmospheric pressure during the post-accident mode of operation.
1 SR     3.9.5.4              operate each VFS train for ?,,10           Within 31 days      '
continuous hours with the heaters          prior to fuel operating.                                 movement.
1 1
1 l
l l
t I
AP600                                        3.9-8         04/98 Draft Amendment P AP014eenpect14030906 r06&27M

Contcinannt Penetrations B 3.9.5 o
B 3.9   REFUELING OPERATIONS B 3.9.5   Containment Penetrations RASE 5 BACKGROUND         During CORE ALTERA' AWNS or movement of irradiated fuel assemblies within containment, potential releases of fission product radioactivity within containment are monitored and filtered or are will i; restricted from escaping to the environment when the LCO requirements are met. In MODES 1, 2, 3, and 4, thie i; ;;;;;plist;0 g                    by ;;ist;ising ;;;teinz:st tr: " L: ;; 0;;;;it;0 in I
    ]                    containment operability is addressed in LCO 3.6.1,
                         " Containment." In MODES 5 and 6, this i; ;;;._,li;i;0 by ;;.. icing closure capability of containment penetrations ;; 0;;; 15;0- is addressed in LCO 3.6.8, i                        " Containment Penetrations."             ; ZOO; f, ti; pet;;tiel
(                        f;; cest;izz:st p;;;;;;i;; tie; ;; ; ;;;;1t ;f ;;
!                        ;;;id;;; i; ;;; lii;1y, ti;;;fere, ;;;;iz:_:st; te i;elete the cesteinz:10 fre; the esteid; etweephere ;;;
b; le;; etsisgest. The "00 req;i;: :ste ;;e ref;;;;0 te
                         ;; ;e;;;irr::t cle;;;e ;; tie; t'                      -
                                                                                    ;esteinz:_t Orr::.:    l. -  0;;teir:: ci;; ;; xx ; ti;; ;11 pet;;;iel ;;;;p; peti; ;;; ;;;;;0 e; -;;;;il; ef i;ing l
61;;;0. Since there is no potential for containment l                    pressurization, the Appendix J leakage criteria and I                    tests are not required in Nodes 5 and 6.
The containment serves to contain fission product                                         I radioactivity that may be released from the reactor core following an accident, such that offsite radiation l
exposures are maintained within the requirements of 10 CFR 50.34. For a fuel handling accident, the AP600                                     .
dose analysis does not rely on containment closure to meet the offsite radiation exposure limits. This LCO is provided as an additional level of defense against the                                    j possibility of a fission product release from a fuel handling accident during CORE ALTERATIONS.
The containment equisement hatches, which are part of the containment pressure boundary, provide a means for moving large equipment and components into and out of containstant. During CORE ALTERATIONS or movement of irradiated fuel assemblies within containment, an equipment hatch is considered closed if the hatch cover is held in place by at least (four) bolts. Good engineering practice dictates that the bolts required by this LCO be approximately equally spaced.
(continued)
(   AP600                            B 3.9-14                           04/98 Draft Amendment P
             ,  m.  .                                                                                              ,
I

Containa:nt Ponotrations D 3.9.5 e
BASES BACKGROvau       If the equipment hatch is open, an alternative barrier (continued)   between the fuel and the outside atmosphere shall be in place e; ;;,111; ef being ;;;aili;ind withia 15 sinetee.
Each containment equipment hatch opens into a staging        ,
area in the auxiliary building. These staging areas            .
contain doors that open to the radiologically controlled
{
areae of the annex building. The annex building contains a door that opens to the outside atmosphere.
The alternate barrier may consist of the staging area in the auxiliary building, or may consist of the staging areas in the auxiliary building and the radiologically controlled areas in the annex building provided the doors from the annex building to the outside atmosphere are closed. The alternate barrier may also consist of a temporary equipment batch cover that provides equivalent isolation capability. The alternate boundary prevents the airborne fission products from being readily released to the atmosphere if the equipment hatches were open during a fuel handling accident.
If an equipment hatch is open during CORE ALTERATIONS or during movement of irradiated fuel assemblies within containment, the containment air ffitration system (VFS) shall be OPERABLE, and at least one exhaust fan shall be operating to provide for monitoring of air-borne radioactivity. This rystem services the containment,   ~
and upon detection of high radiation, also services the fuel area and the auxiliary building staging areas.
Upon detection of high radiation, the operators would isolate the containment purge supply, and the VFS exhaust fan would continue to operate. The operation of the VFS exhaust fans provides the system with the ability for monitoring of radioactivity releases from containment following a fuel handling accident and, if operating, will provide filtration of the containment atmosphere.
If ;;. fee.e is a personnel air lock or spare containment penetration are is open during CORE ALTEI1ATIONS or during movement of irradiated fuel assemblies within containment, then the containment air filtration system (VFS) shall be OPERABLE and operating to monitor for the release of radioactivity and to provide filtration of the air inside containment be air' ';; ti; ;;;;;;;:;;;; er ; 0;;; '- ' ling ;;;if;;;.
These penetrations open into the auxiliary building.
Upon detection of high radiation in the exhaust air from      j the auxiliary building, ties; pe;;i;;; cf ti; ;_ ilia-y L ildi;g ;; ;;. 1;;O by ti; VFS wheeb will provide filtered exhaust of these areas. Considering that these penetrations open into the auxiliary building and not directly to the atmosphere, and that the VFS is in             ,
operation, an alternate barrier to the release of               l radioactivity directly to the environment is pA9NddWP4)         l l
AP600                        3 3.9-15            04/98 Draft Amendment P
  .,_,-          a i
m

Containannt Penstrat lons 3 3.9.5 BASES APPLICABLE      For.the AP600, there are no safety analyses that SAFETY ANALYSES require containment closure during CORE ALTERATIONS or movement of irradiated fuel assemblies within containment, other than those discussed in LCO 3.6.8.
Fuel handling accidents, analyzed in Reference 1, include dropping a single irradiated fuel assembly and handling tool or a heavy object onto other irradiated fuel assemblies. The requirements of LCO 3.9.4,
                        " Refueling Cavity Water Level," ensure that the release of fission product radioactivity, subsequent to a fuel handling accident, results in doses that are well within the guideline values specified in 10 CFR 50.34.
Standard Review Plan, Section 15.7.4, Rev. 1 (Reference 2), defines "well within" to be 25% or less of the limiting dose guideline values.
This specification is included in accordance with NRC direction per Reference 3.
LCO             This LCO provides defense-in-depth against the consequences of a fuel handling accident in containment by limiting the potential escape paths for fission product radioactivity released within containment. Tb6e LCO ;;;;__s-ire; the ;;;;;izz:st eg;i;1:1; istsi;; te b5
_.___,             _ _ _ _    __-_,-__ __ _._____t___        .,__  e_
This LCO requires that if an equipment hatch, personnel air lock, or spare containment penetration is open during CORE ALTERATIONS or movement of irradiated fuel assemblies within containment, then the containment air filtration system (VFS) shall be I                 OPERABLE and i; eperatie; operating to monitor for the release of radioactivity and to provide filtration of the air inside containment te ;;d;;e ti; ;;;;;;;;;;;; ef
                        ; fuel ':1' ling ;;;ife;;.
The VFS is considered OPERABLE when
: a. One VFS exhaust fan is OPERATIONAL; the associated l
EEPA filter and charcoal adsorber are not                          i excessively restricting flow, and are capable of performing their filtration functions and the associated heater and ductwork are OPERATIONAL, and air circulation can be maintained;
: b. An alternative barrier between the containment
!                              atmosphere and the outside atmosphere is in place.
The alternate barrier may consi-t of the staging i                              area in the auxiliary building, or may consist of l                              the staging areas in the auxiliary building and the radiologically controlled areas in the annex (continueal
(    AP600                               3 3.9-16          04/98      Draft Amendment P
        . _ ,, -     vm i
I l..                _  _              .-

1 Containa:nt Pen trations B 3.9.5      j
,                                                                                                                                             i BASES LCO                building provided the doors from the annex building (continued)      to the outside atmosphere are closed.
Doors in the alternate barrier which are normally closed may be opened for short periods of time for           {
ingress and egress. The alternate barrier may also           l consist of a temporary equipment hatch cover that provides equivalent isolation capability.
APPLICABILITY  The containment penetration requirements are applicable during CORE ALTERATIONS or movement of irradiated fuel assemblies within containment because this is when there is a potential for a fuel handling accident. In MODES 1, 2, 3, and 4, containment penetration requirements are addressed by LCO 3.6.1. In MODES 5 and 6, when CORE ALTERATIONS or movement of irradiated fuel assemblies within containment are not being conducted, the potential for a fuel handling accident does not exist. Containment closure capability in MODES 5 and 6 are addresned by LCO 3.6.8..
ACTIONS        A.1 and A.2 If the containment equipment hatch or air locks, or any containment penetration that provides direct access from the containment atmosphere to the outside atmosphere is not in the required status, or the VF5 is inoperable or not operating when required, the unit must be placed in a condition where the isolation function is not needed.
This is accomplished by immediately suspending CORE ALTERATIONS and movement of irradiated fuel assemblies within containment. Performance of these actions shall not preclude completion of movement of a component to a safe position.
SURVEILLANCE   S1   3.9.5.1 I REQUIREMENTS This Surveillance denometretes verifies that each of the                  !
containment penetrations required to be in ive closed position is in that position or the VF5 is OPRMBLE and operating. :; ti; ;;;; ef ti; egei,,z-_; i ;;ic er For j
the VFS to be considered OPERABLE, this surveillance             I also requires that an alternate barrier is in place er           l s a d l; ef i.i;; i; ,1;;; witti; 1" si;;;;;.                    1 (continued)
                                                              @ Ar600                         B 3.9-17          04/98 Draft Amendment F
_           -m

Containm:nt PenotrctionD        {
D 3.9.5  {.
l BASES'                                                                                                        l SURVEILLANCE  SR   3.9.5.1 (continued)                                                                       !
REQUIREMENTS The Surveillance on the open purge and exhaust valves will demonstrate that the valves are not blocked from closing. If centeinz:n; is ep;; peastratica; ;;e sic;;d, the sperater; ;;; cles; the centeinz:st p;;ge
                  ;;d     ' eet free the ;estrel rees upe; high ;;distie; detected i; centainz:;;.      A1:e the Ou;c.ill;;;; will                                       '
d: :;et;;te that ;;;h velve i; ;;patie of heing sic;;d by ;; Or nA : cesteinx;;; p;ge ;;d e;haust i;ciatie; ei guel .
SR   3.9.5.2 This Surveillance demonstrates that each containment purge and exhaust valve actuates to its isolation position on manual initiation. The Frequency is in accordance with the Inservice Testing Program.
SR    3.9.5.3 This SR verifies the ability of the VFS to maintain negative pressure in the containment and the portions of the auxiliary and / or annex building that comprise the envelope defined as the alternate barrier with respect to potentially uncontaminated adjacent areas. Doors in the alternate barrier which are normally closed may~be opened for ingress and egress. The VFS provides filtered exhaust of the containment, and the radiologically controlled portions of the auxiliary building. The Frequency of 24 months is consistent with the guidance provided in NUREG-0800, Section 6.5.1 (Ref. 4).
SR    3.9.5.(
The VFs should be checked periodically to ensure that it functions properly. As the operating conditions on this system are not severe, testing each train within one i                 month prior to fuel movement provides an adequate check on this system. Operation of the heater dries out any moisture accumulated in the charcoal from humidity in the ambient air.
REr mr_s-r s! 1. AP600 SSAR, Section 15.7.4.
: 2. NUREG-0800, Section 15.7.4, Rev. 1, July 1981.
: 3. NRC Request for Additional Information (RAI) 480.1159F.
: 4. NUREG-0800, Section 6.5.1, Rev. 2, July 1981.
i AP600                       5 3.9-18                                     04/98 Draft Amendment P o,_,--

Wh8-1 mad-VFS 3.9.6 3.9    REFUELING OPERATIONS 3.9.6     % dielegieelli Ceetselled Asee Veetiletier. Oyetee. 'VAO)      r.d Containment Air Filtration System (VFS) l LCO    3.9.6          VA0 .; hell he eyesetir.g  r.'. One VFS exhaust subsystem shall be OPERABLE.
::0"";
nie 1.00 esyliae te the VA0 e heiet s that ;e..iese the f el                                                             i her.dlieg ;;ee ef the esiliari heil'.ir.i, .
APPLICABILITY:        During movement of irradiated fuel assemblies in the fuel building.
ACTIONS CONDITION                     REQUIRED ACTION             COMPLETION TIME A.      Lth t.eir.e ef VA:        A.1   Suspend movement of             Imunediat ely edeiet s eet                    irradiated fuel eperat ir.g                     assemblies in the fuel building.
2B uth t.ei e ef Required VFS exhaust subsystems inoperable.
AP600                                  3.9-9                04/98 Draft Amendment P Apoiww.cueosoeotene
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _               _ _ ~

                                                                                                           ._, 973 3.9.6 SURVEILLANCE REQUIREMEFfS SURVEILLANCE                             FREQUENCY SR    3.9.6.1        Operate each VFS trade exhaust subsystem     Within 31 days for 1 10 continuous hours with the           prior to fuel heaters operating.                           movement SR    3.9.6.2        Verify the VAS fuel handling area            24 months subsystem aligns to the VFS filtered exhaust on an actual or simulated actuation signal.
BR   3.9.6.3         Verify one VFS exhaust subsystem trede       24 months on a can maintain a negative pressure in the     STAGGERED TEST fuel handling area with respect to          BASIS atmospheric pressure during the post-accident mode of operation.
AP600 AP019eespee1N r06442798 3.9-10             04/98 Draft Amendment P

e
                                                                                     'J A" _ 4 VFS 3 3.9.6 i
B 3.9   REFUELING OPERATIONS B 3.9.6   0;di;1e,1;;11y Ce_trelied Aree V;;tiletic; Cy t        (VA ; 24 Containment Air Filtration System (VFs)                                               I I
Basus BACKGROUND          The radiologically controlled area ventilation system (VAs) serves the fuel handlia:g area of the auxiliary building, and the radiologically controlled portions of the auxiliary and annex buildings, except for the health physics and hot machine shop areas which are provided with a separate l
     -                       ventilation system (VHS). If high airborr.e radioactivity is detected in the exhaust air from the auxiliary or annex buildings, the VAs supply and exhaust duct isolation dampers               '
automatically close to isolate the affected area from the outside environment and starts the containment air l      I                     filtration exhaust ete subsystem. The VFS prevents
!                            exfiltration of unfiltered airborne radioactivity by i
maintaining the isolated zone at a slightly negative pressure with respect to the outside environment and adjacent unaffected plant areas. Ce airfie ;;;; ti.;_gi the - *--;.;; f     is   i ;;iz: 2 et ; ce ;;;;. vel ; iy u f 1;;i;.; the f      islet - ee. ". ;_teide ei; - '-__,
                             '-- ;. _.;4.1;;;; te . ;;e1 ti;          ..;; eirfie; ;;;; t' .e_gi ti;    : . :_z f s' ;;.21 filtese te ;istsi; tie i;elet.O etee;;) et e eligitly ;;;_tive ,.;;e a. relative te the j                            si:n ;;;ee.
i l                            For a fuel handling accident, the AP600 dose analysis does i
not rely on the OPERABILITY of the VAs or VFS to meet the
!                            offsite radiation exposure limits. This LCO is provided as l                            an additional level of defense against the possibility of a
;                            fission product release from a fuel handling accident in the fuel building. If the VFS exhaust air filtration units are operational and ac power is available, they may be used to support post-event recovery operations. The plant vent bewh range radiation detectors monitor effluents discharged from the plant vent to the environment.
The containment air filtration system consists of two 100 percent capacity supply air handling units, a ducted supply and exhaust air system with containneint igelation
!                            valves and piping, registers, exhaust fans, filtration l                            units, automatic controls, and accessories.
i (continued) l            AP600                                3 3.9-19             04/98 Draft AmenAmant P
_ - _m

e VM e '. VFS D 3.9.6 i
BASES BACKGROUND                     The filtration units are connected to a ducted system with (continued)       isolation dampers to provide EEPA filtration and chercoal adsorption of exhaust air from the containment, fuel handling area, radiologically controlled areas of the auxiliary and annex buildings. A gaseous radiation monitor is located downstream of the exhaust air filtration units in the common ductwork to provide an alarm if abnormal gaseous releases are detected. The plant vent exhaust flow is monitored for gaseous, particulate and iodine releases to the environment. During conditions of abnormal airborne radioactivity in the fuel handling area, auxiliary and/or annex buildings, the VFS exhaust air filtration units provide filtered exhaust to minimize unfiltered offsite releases.
The VAS is described in SSAR section 9.4.3 and the VFS is described in SSAR section 9.4.7. (References 1 and 2).
APPLICABLE                     The VAG-end-VFS ere is not required to mitigate the SAFETY ANALYSES                consequences of the limiting Design Basis Accident (DBA),
which is a fuel handling accident. The analysis of the fuel handling accident, given in Reference 3, assumes that all fuel rods in an assembly are damaged. The DBA analysis of l                                            the fual bandling accident does not assume that the VAs-ee
,                                              l                                            VFS prc, rides a filtered exhaust, and tineer its operation
!                                                                                           would ruduce the consequences of the fuel handling accident.
This specification is included in accordance with NRC direction per Reference 6.
LCO                            r; t;ei et the V : i; ;;, i;;' te h. ;;;;;tieg te p;mi";
l                                            fe; -:-iterieg ef pete tiel reles;;; 0; . ti; _el e;e ,
1                                            One train of the VFS exhaust is required to be OPERABLE to reduce the consequences of a fuel handling accident by filtering the fuel building atmosphere.
A VFS exhaust subsystem is considered OPERABLE when its associated:
l l
I (continued)
AP600                                   3 3.9-20     04/90 Draft Amendment P t

VM ;'. VFS D 3.9.6 BASES LCO                                                                                                  a.                                Exhaust fan is OPERATIONAL;
: b.                                 HEPA filter and charcoal adsorber are not excessively restricting flow, and are capable of performing their filtration functions
: c.                                The associated heater and ductwork ,velv.; ;.4 '           _eie are OPBl& der 5 OPERATIONAL, and air circulation can be maintained.
l APPLICABILITY                                                                                         During movement of irradiated fuel in the fuel handling area,-the V;.                                  ie spe. ting te se iter ;; die;;ti .-ity i;. the f el esee ef ti.e ; ilieiy Leildisg,                                     -4 the VFS is OPERABLE to alleviata the potential consequences of a fuel handling accident.
ACTIONS                                                                                              M                                                                                                     )
J With Leth t; is.; ef VI.: ir. :;;;;_L1. , _;tica ; .;; i; t_te te                                     d eteit ese treia ef 7".C '-- - fietely.                                  If the eyet      i; ;;;
pi;;ed is ep;;eties, t:.ie actie res irse .;;ep; eier. ef f ;l
                                                                                                                       ..                                 -t,     which p .elud_,.; e f el ' - 'lir.g ;;;ide t .
1.ie 0;;e set preclude tt; ;.                                      .;; ef f el es.;- ' lice te e eef.
peeities.
When t e treir.e ef tt; '.T; ere the required VFS subsystesa is inoperable during movement of irradiated fuel assemblies in the fuel building, action must be taken to place the unit in a condition in which the LCO does not apply. Action must be taken insnediately to suspend movement of irradiated fuel assemblies in the fuel building. This does not preclude the movement of fuel to a safe position.
(continued) 1 1
AP600                                                                                                                                             3 3.9-21               04/98 Draft Amendment P L_____.-______-_________    _ _ .                                 _.

VAS-end-VFS D 3.9.6 l
RASES SURVEILLANCE               SR   3.9.6.1 REQUIREMENTS i
'   l                            The VFS 0;;;ity eyet--- should be checked periodically to l                            ensure that it they-functions properly. As the
                                 ;_. ire-__ ;tel ;;4 se; eel operating conditions on this system are not severe, testing each train within one month prior to fuel movement provides an adequate check on this system.
Operation of ths heater dries out any moisture accumulated in the charcoal from humidity in the ambient air.
SR   3.9.6.2 This SR verifies that the VAS fuel handling area subsystem aligns to the VFS and that the VF8 train starts and operates l                                on an actual or simulated actuation signal. During the post-accident mode of operation, the VAS fuel handling area subsystem aligns to the VFS filtered exhaust subsystem. The 24 month Frequency is consistent with Referencs 4.
SR   3.9.6.3 This SR verifies the integrity of the fuel handling area of the auxiliary building enclosure. The ability of the VAS and VFS to maintain negative pressure in the fuel handling area of the auxiliary building with respect to potentially uncontaminated adjacent areas is periodically tested to-verify proper function of the VAS and VFS. During the post-accident mode of operation, the VAs fuel handling area             ,
l                                subsystem aligns to the VF8 filtered exhaust subsystem.r-end       l bbe-YP6 i; f;;is;;O te seietsie ; ;11 it ;;;;ti.; p;;;;;;e         i is the f;;l '--flisi ;;;; :: ti; ;__iliary L.ildiag, te p.e..;; ;; filtered ;;0        sitered leui;ge. In this l                                configuration, the VFS is designed to maintain a slight negative pressure in the fuel handling area of the auxiliary building with respect to atmospheric pressure, to prevent          ;
unfiltered and unmonitored leakage. Doors may be opened for        !
l                                short periods of time to allow ingress and egress. The             '
Frequency of 24 months is consistent with the guidance provided in NUREG-0800, Section 6.5.1 (Ref. 5).                    l l
l (continued)
      @ AP600                                         3 3.9-22            04/98 Draft Amendment P won. chap.cusoxmos ,os<mse

l D 3.9.6 i
i RASES REFERENCES
: 1. AP600 SSAR, Section 9.4.3.
: 2. AP600 SSAR, Section 9.4.7.
: 3. SSAR, Section 15.7.4.
l                                               4. Regulatory Guide 1.52 (Rev. 2).
i I                                               5. NUREG-0800, Section 6.5.1, Rev. 2, July 1981.
: 6. NRC Request for Additional Information (RAI) 480.1159F.
i t
l l
l l
i l
                          @ AP600                                                    3 3.9-23 04/98 Draft Amendment P apoiwimmana rosos 7se l

6 1
M Westinghouse                                 FAX COVER SHEET e
RECIPIENT INFORMATION                             SENDER INFORMATION DATE:               AAb '{            /4 9{           NAME:             gmg          ptfLiM TO:                                                   LOCATION:         E      GY CENTER -
fggp          g,        ,g PHONE:              FACSIMILE: fd-30/ '/tf-lug        PHONE:            Omce. (V/2) 379.gg COMPANY:                   ,                          Facsimile:
* 284 4887 d                                             cutside: (412)374-4887 LOCATION:             () ( i 7 e:     %,a 7-Cm + Pages          1+      b The following pages are being sent from the Westinghouse Energy Center, East Tower, Monroeville, PA. If any problems occur during this transmission, please call:
WIN: 234.642% Bev )or Outside:(412pT4-6529 COMMENTS:                              g
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                ._                                                                                   l

RESPONSES TO NRC REQUEST FOR ADDITIONAL INFORMATION l
OITS 6742 - ITAAC Open Item I&C ITAAC (Sections 2.5.1. 2.5.2)
: 1. Table 2.5.1-5 identified that the DAS Process Cabinets are located in Arulex Building which is not a seismically qualified structure. DAS performs reactor trip and the ESFAS function. A Seismic event may disable DAS's intended function and may even interfere with the protection systems. This is not acceptable. A conference call was held on 4/14/98 between Westinghouse. Tom Kenyon and Hulbert Li. Westinghouse promised that they will discuss this concem with us again.

===Response===
The portion of the Annex Building which contains the DAS processor cabinets is a Seismic Category 11 building. As stated in SSAR 3.2.1.1.2. Seismic Category 11 buildings are designed to prevent their-collapse under the safe shutdown eanhquake.
The DAS is a nonsafety-related system and is not required to function after a seismic event. Itis therefore acceptable for the DAS to be located in a Seismic Category 11 building. The functions pertonned by DAS serve as a backup to the functions of the safety-related PMS. The DAS is not assumed in any safety analysis and is not required to mitigate a seismic event.
The statement that the DAS "may even interfere with the protection system" is not correct. As stated m SSAR 7.7.1.11. the DAS actuation devices are isolated from the PMS actuation devices, so as to avoid adverse interactions between the two systems.
Per telecon agreement on 4/22. Westmghouse will revise SSAR section 7.7.1.11 to identify that the DAS pnicessor cabinets are hwated in the portion of the Annex Building that is a Seismic Category 11 st ruct ure.
SSAR Revision:
The last sub-section of SSAR 7.7.1.11 will be revised as shown:
Equipment Qualification and Quality Standards The diserse actuation system is located m a controlled envinmment. but is capable of functioning dunog and alter nonnal and abnonnal events and conditions that include:
OITS 67421 W
      ~
Westinghouse
(
L_

e RESPONSES TO NRC REQUEST FOR ADDITIONAL INT ORMATION
                 .p..
5      *
* Wide temperature range of 40 to 120*F Noncondensing relative humidity up to 95 percent
* Radio frequency and electromagnetic interference l       1he diverse actuation system processor cabinets are located in the portion of the Annex Huilding that is a Seismic Category IIstructure. The diverse actuation system equipment, including actuated devices is designed and qualified in accordance with the industry standards listed in subsection 7.1.4.1.8. The adequacy of the hardware and software is demonstrated through the verification and validation program discussed in subsection 7.1.2.15. This program provides for the use of commercial off-the-shelf hardware and software. As the diverse actuation sptem performs many of the protection functions associated within the ATWS systems used in existing plants, the diverse actuation system is designed to meet the quality guidelines established by Generic Letter 85-06. " Quality Assurance Guidelines for ATWS Equipment that is not Safety-Related."
ITAAC Revision:
None 1
l l
l O n 6 N 2-2 W
Westinghouse l                                                                                                                                    l b____________.__    _            _     _     __           _                                _       _ _ _ _ . . _             _  ____

e RESPONSES TO NRC REQUEST FOR ADDITIONAL INFORMATION
: g. _.                       .
E                               .
OITS 6743 ITAAC Open item INC ITAAC (Sections 2.5.1. 2.5.2)
: 2. Component location listed in ITAAC Tables 2.5.1-5. 2.5.2-9 were not mentioned in the SSAR before. SSAR needs to be updated.

===Response===
Per telecon agreement on 4/22, we will revise SSAR section 7.7.1.11 to identify that the DAS pntessor cabinets are located in the portion of the Annex Building that is a Seismic Category 11 structure.
SSAR Revision:
The last sub-section of SSAR 7.7.1.11 will be revised as shown in response to OITS 6742.
ITAAC Revision:
None W westinghouse

i ITAAC OPEN ITEM
                                                                                                                                  ==
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l I
i l
l OITS 6744       ITAAC Meeting Open Item                                                                                                                        j l     I&C ITAAC (Sections 2.5.1, 2.5.2)
: 3. Tables 2.5.1-5 and 2.5.2-9 need title to be consistent with other tables.                                                                                 I 1

===Response===
   *                                                                                                                                                                 )
From the response to OITS 6711:
                                                                                                                                                                     )
l l          In the AP600 Tier 1 material, titles have been omitted from most tables. Table formats which are used in more than one Tier 1 section and contain a multiplicity of information do not have titles.                                                         '
Specific tables which are only used in a single section for a specific purpose have a table title.
The approach used for the AP600 Tier i material is to describe the specific design commitment listed in the referenced table and to reference the table by number, not by a description or a table title. This                                                  j
(.
method of referencing the tables by table number and avoiding the use of a table title is more direct, succinct and less likely to create confusion when interpretation of the design commitment is required.
Since Tables 2.5.15 and 2.5.2-9 are table formats used in other sections, a table title is not included for the reasons described above.
l l
l l    SSAR Revision-                                                                                                                                                  I None l
Tier 1 Revision:
None t
OITS 6744-1 l

I o
RESPONSES TO NRC REOUEST FOR ADDITIONAL INFORMATION OITS 6745 - ITAAC Open Item I AC ITAAC (Sections 2.5.1. 2.5.2)
: 4. Table 2.5.2-3 generaD u consistent with SSAR Table 7.3-1. However. two ESFAS functions should be added on ITAAC Table 2.5.2-3:
(a) Safeguard Actuation Signal tb) Pressurizer Heater Bloci: Signal

===Response===
Per telecon agreement on 4/22. we will revise CDM Table 2.5.2-3 to add safeguards actuation and pressurizer heater block.
SSAR Revision:
None ITAAC Revision:
CDM Table 2.5.2-3 will be revised as shown:
Table 2.5.2 3 PMS Automatically Actuated Erigineered Safety Features Safeguards Arttation Containment isolation Automatic Depressurization System (ADS) Actuation Main Feedwater Isolation Reactor Coolant Pump Trip CMT Injection Turbine Trip Steam Line Isolation Steam Generator Blowdown isolation Panive Containment Cooling Actuation Startup Feedwater Isolation
                                                                                             '" S"~ '
w westingnous.

t RESPONSES TO NRC REQUEST FOR ADDITIONAL INFORMATION C _. .
Passive Residual Heat Removal (PRHR) Heat Exchanger Alignment Block of Boron Dilution Chemical and Volume Control System (CVS) Makeup Line isolation Steam Dump Block MCR isolation and Air Supply Initiation A xiliary Spray and Letdown Purification Line isolation Containment Air Filtration System isolation Nomtal Residual Heat Removal isolation Spent Fuel Pool isolation In-Containment Refueling Water Storage Tank (IRWST) Injection IRWST Containment Recirculation CVS Letdown isolation l    Pressurizer Heater Block I
l OITS 6745-2 3 Westinghouse 1
1

I
        ,i
                                          @ Westinghouse                                                            FAX COVER SHEET Recipient Information                    Sender Information Date:                         5/7/98                    Name:       D. Lindgren To:                          Joe Sebrosky               location:   WEC E 330 Phone:                                                  Phone:      (412) 374 4856 (301) 415-1132 Facsimile:                                              Facsimile: Bell: (412) 374 4887 (310) 415-2002 Company:                     U.S.NRC                                WIN 284 4887 Location:                    Rockville, MD Cover + Pages                                  1+9 The following pages are being sent from the Westinghouse Energy Center, Monroeville, PA.
If there are any problems during this transmission, please call the sender or WIN 284-6529 or Bell (412) 374-6529.
Comments:                            Joe, l                                        Attached are DRAFT SSAR Rev. 23 change pages to address FSER confirmatory items. These l                                        changes have been provided previously as markups. When these changes are incorporated into the SSAR the Confirmatory items can be closed.
: 1.        On Pages l A 25 and I A-26 changes to the conformance with Reg. Guide 1.54 in Appendix 1 A are shown to address comments related to coating inside containment.
: 2.         On Page 6.1-11 a change to 6.1.3.2 is shown to address a comment on containment coatings.
l                                        3. On Page 3.7-6 changes are made to the third and fourth bullet of 3.7.1.4 to clarify ground water assumptions.
: 4.          On Page 3.8 29 a bullet is shown in 3.8.3.4.2.1 that adds a reference to the calculation for hydrodynamic loads.
: 5.         On Page 3.8-74 Reference 51 is added as for the calculation of hydrodynamic loads.
There is an additional change requested by Tom Chcng that is not a confirmatory item. On page 3.8-57 reference to inspection in addition to testing is added to the last paragraph in 3.8.4.7. This will be j                                        included in Rev. 23.
There is are additional changes from our review to verify that design changes and commitments are included in the SSAR. On page 3.2-73 the construction code for the fire dampers in the VBS is changed to UL-555S. On page 3.2-84 UL-555S is added to fire dampers in the VXS and the exhaust fan for the ancillary diesel room is added. The staff should be aware of these. These were commitments omitted from previous SSAR revisions.
I

e
: 1. litroduction end G: nerd Description tf Plant Criteria      Referenced                    AP600 Section       Criteria                      Position         Clarification /Sununary Description of Exceptions Reg. Guide 1.53, Rev. O,6/73 Application of the Single-Failure Criterion to Nuclear Power Plant Protection Systems General       IEEE Std. 379-1972            Exception        Regulatory Guide 1.53 endorses IEEE Std. 379-            l 72 (Reference 10), which has been superseded by IEEE Std. 379-88 (Reference 11). De AP600 uses the latest version of the industry standards       )
(as of I/90). This version is not endorsed by a regulatory guide but its use should not result in deviation from the design philosophy otherwise stated in Regulatory Guide 1.53.
The guidelines are applicable to safety-related dc      ;
power systems. There are no safety-related ac power sources in the AP600.
Reg. Guide 1.54, Rev. O, 6/73 - Quality Assurance Requirements for Protective Coatings Applied to Water-Cooled Nuclear Power Plants General       ANSI N101.4-1972               Exception       Some coatings inside containment are nonsafety-related and satisfy appropriate ASTM Standards.
See subsection 6.1.2 for additional information.
Application is controlled by procedures using qualified personnel to provide a high quality            I product. The paint materials for nonsafety-related      l coatings inside the containment are subject to 10CFR Part 50 Appendix B Quality Assurance l                                                              requirements. The standards endorsed in the              l Regulatory Guide are not current. The Combined l                                                              License applicant is responsible for preparing the l                                                              programs for safety related coatings and for procurement of nonsafety-related coatings inside l                                                              containment.      See subsection 6.1.3 for the           ;
1                                                              Combined License information item.                       l l C.I           ANSI N101.4-1972               Exception       The standards endorsed are not ANSI current.
N45.2-1971                                     Appropriate current standards including ASME             l NQA 1 are followed to develop the quality                l l                                                                                                                        assurance program for safety related coatings and        ;
;                                                                                                                         for procurement of nonsafety-related coatings           ;
I                                                                                                                         inside containment.      De quality assurance program for safety-related coatings conforms to the requirements of ASME NQA-1-1983 as I                                                              endorsed in Regulatory Guide 1.28. Appropriate I                                                              current standards for coating quality assurance are I                                                               used in conjunction with Regulatory Guide 1.28.
Revision: 23 W Westinghouse                                  IA 25                                         DRAFT,1998

::  y 8
: 1. Introduction cad GInertl Description of PI:nt
                    'l' Criteria      Referenced                   AP600 Section . Criteria                     Position                          Clarification / Summary Description of Exceptions I C.2           ANSI N101.4-1972             Exception                        The standard endorsed is not current.
1                                                                             Appropriate current standards are followed by the                                                                                                    ,
I                                                                             Combined License applicant for safety-related coatings.                                                                                                                                           ]
                                                                                                                                                                                                                                           )
l C.3           ANSI N101.4 1972             Exception                        The standard endorsed is not current.
I                                                                              Appropriate current standards are followed by the                                                                                                 i l                                                                              Combined License applicant for safety-related                                                                                                       I coatings.                                                                                                                                           I I
l C.4           ANSI N101.4-1972             Conforms                          Guidance for the control of cleaning and other material used on stainless steel material is provided in Regulatory Guides 1.37 and 1.44.                                                                                                      >
Subsections 5.2.3.4 and 6.1.1.2 address the                                                                                                         i control of processes used on stainless material for safety-related piping and components.
Reg. Guide 1.55 - Withdrawn l
l l         Reg. Guide 1.56, Rev.1,7/78 Maintenance of Water Purity in Boiling Water Reactors General                                    N/A                               Applies to boiling water reactors only.
Reg. Guide 1.57, Rev. O, 6/73 - Design Limits and Loading Combinations for Metal Primary Reactor                                                                                                                                 I Containment System Components General       ASME Code, Section III       Exception                         The regulatory guide was issued in 1973. It refers to the ASME Code through the Summer 1973 Addenda. The acceptance criteria have been defined in greater detail in SRP 3.8.2. The AP600 complies with the SRP acceptance criteria with the exception that the operating basis earth-quake is excluded.
Reg. Guide 1.58 Withdrawn Reg. Guide 1.59. Rev. 2,8/77 Design Basis Floods for Nuclear Power Plants l
l         C.1-4         Regulatory Guide 1.29        N/A                               The maximum water level due to the probable maximum flood is established as a site interface in Chapter 2 and is used in the design of the AP600. This is the Combined License appli-cant's responsibility.
l l
l Revision: 23 DRAIT,1998                                       1 A 26                                                                                                                                                     3 W8Stingh00$8 L   .__                                                _      _ _ _ _ _ . _ _ _ _             .__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _                  J

e
                                                                                                                                     =- m:
: 6. E:gineered Saf:ty Fc:tures by the Combined License applicant. This program is not subject to 10 CFR 50, Appendix B, quality assurance requirements.
Due to the use of modularized construction, a significant portion of the containment coatings are shop applied to the containment vessel and to piping, structural and equipment modules.
This application of coatings under controlled shop conditions provides additional confidence that the coatings will perform as designed and as expected.
The coatings used in radiologically controlled areas outside containment are tested for radiation resistance and evaluated for decontaminability; they are not specified to be design basis accident tested. Where practical, the same coating materials are used in radiologically controlled areas outside containment as are used inside containment. This provides a high level of quality and optimizes maintenance painting over the life of the plant.
6.1.2.2    Other Organic Materials A listing of other organic materials in the containment is developed based on the specific type of equipment and the supplier selected to provide it. Materials are evaluated for potential interaction with engineered safety features to provide confidence that the performance of the engineered safety features is not unacceptably affected.
6.I.3       Combined License Information Items 6.1.3.1     Procedure Review The Combined License applicants referencing the AP600 will address review of vendor fabrication and welding procedures or other quality assurance methods to judge conformance of austenitic stainless steels with Regulatory Guides 1.31 and 1.44.
6.1.3.2     Coating Program l                   The Combined License applicants referencing the AP600 will provide a program to control procurement, application, and monitoring of safety-related coatings. The program for the control of the use of safety-related coatings will be consistent with subsection 6.1.2.1.6.
6.1.4       References
: 1. NUREG-0797, " Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2."
: 2. Bolt, R. O. and J. G. Carroll, " Radiation Effects on Organic Materials". Academic Press, New York,1963, Chapter 12.
: 3. Parkinson, W. W. and O. Sisman, "The Use of Plastics and Elastomers in Nuclear Radiation", Nuclear Engineering and Desigr 17 (1971), pp 247-280, North-Holland Publishing Co., Amsterdam.
Revision: 23 Y W85tingh00$8                                    6.1-11                                    DRAFT,1998

e
: 3. Design of Structures, Ccmponents, Equipmext, cad Systems soil profiles include a hard rock site, a soft rock site, an upper bound soft-to-medium soil site and a soft-to-medium soil site. The shear wave velocity profiles and related governing parameters of the four sites considered are the following:
For the hard rock site, an upper bound case for firm sites using fixed base seismic analysis.
For the soft rock site, a shear wave velocity of 2400 feet per second at the ground surface, increasing linearly to 3200 feet per second at a depth of 240 feet, and base rock at the depth of 120 feet.
For the soft-to-medium soil site, a shear wave velocity of 1000 feet per second at ground surface, increasing parabolically to 2400 feet per second at 240 feet, base rock I                    at the depth of 120 feet, and ground water is assumed at g.ade level.
For the upper bound soft-to-medium soil site, a shear wave velocity of 1414 feet per second at ground surface, increasing parabolically to 3394 feet per second at 240 feet, I                    base rock at the depth of 120 feet, and ground water is assumed at grade level. The initial soil shear modulus profile is twice that of the soft-to-medium soil site.
He strain-dependent shear modulus curves for the foundation materials, together with the corresponding damping curves, are shown in Figures 3.7.1-14 and 3.7.1-15 for rock material and soil material, respectively. The shear wave velocity profile for the design soil profiles, with variation of depth to base rock, is shown in Figure 3.7.1-17.
Free field analyses are performed for each design soil profile and acceleration response spectra are calculated at the foundation level of the nuclear island as described in subsection 2A-6.
De envelopes of the horizontal and vertical spectra for the four design soil cases are shown in Figures 3.7.1-18 and 3.7.1-19 respectively. These envelopes represent the seismic input at foundation level for which the AP600 is designed. These spectra are used for comparison with the results of site specific soil amplification studies as described in subsection 2.5.2.1.
He AP600 design for the site parameters given in Table 2-1 is implemented using analyses for the four soil conditions described above. These four soil conditions consist of competent material. They do not include profiles consisting of one or more thin layers overlying competent material (Standard Review Plan 3.7.2). The shear wave velocity parameter in Table 21 excludes these shallow soil sites from consideration as a part of design certification. J ne AP600 may also be suitable at sites outside the bounds of the site parameters. These sites may be demonstrated to be acceptable using the methodology in subsection 2.5.2.2.
Rese site specific analyses demonstrating acceptability of the site would be submitted as part
;                         of the Combined License application. De evaluation of the suitability of these sites is not j                         included in design certification.
The AP600 nuclear isf and consists of three seismic Category I structures founded on a common basemat. He three structures that make up the nuclear island are the coupled Revision: 23 DRAFT,1998                                          3.7-6                              3 W8Stingh00S8 L____ _ _________-______    _      _                                                  _
_j

e
  ,    3. Desiga of Structures, Components, Equipment, rnd Systems Two pressure time histories, characterized by different shapes and frequency content, can be selected as representative of the sparger discharge pressures; they are assumed as acting on a spherical bubble centered on the sparger centerline and enveloping the ends of the sparger arms.
The application of such time histories as forcing functions to an analytical model, simulating the fluid structure interaction effects in the test tank, has been found to predict the measured tank wall pressures, for the two selected reference time intervals.
The two defined sparger source term pressure time histories can be used as forcing functions for global hydrodynamic analyses of the in-containment refueling water storage tank by developing a comprehensive Guid-structure finite element model and reproducing the test tank mesh pattern in the sparger region.
l              .
The hydrodynamic loads on the vessel head support columns and ADS sparger piping I                     located in the IRWST are developed from the forcing functions using the methodology I                     documented in Reference 51.
3.8.3.4.2.2 In Containment Refueling Water Storage Tank Analyses The in-containment refueling wat" storage tank is constructed as an integral part of the containment internal structures as described in subsection 3.8.3.1.3. It contains two depressurization spargers that are submerFed approximately 9 feet below the normal water level. Transmission of the hydrodynamic pressures from the sparger discharge to the wetted in-containment refueling water storage tank is evaluated using the coupled fluid-stmeture interaction method similar tn that described for the test tank analysis in the previous subsection.
The 3D ANSYS finite element modelincludes the in-containment refueling water storage tank boundary, the water within the in-containment refueling water storage tank, the adjacent structural walls of the containment intemal structures, and the operating floor. The model of the in-containment refueling water storage tank, shown in Figures 3.8.3-10 (sheet 2),3.8.3-11, and 3.8.3-12, represents the outer steel structures, the inner concrete walls, and the water. The model of the adjacent structural walls and floors is shown in Figure 3 8.3-10 (sheet 1). The flexible steel outer wall is represented using beam and shell elements; isotropic plate elements are used to represent the inner structural module walls. The water is modelled as a compressible fluid to provide an acoustic medium to transmit the source pressure. The model has two bubble boundaries representing the spargers. Pressure loads are applied to the solid element faces adjacent to the air bubbles. The forcing functions at the sparger locations are conservatively assumed to be in phase. Rayleigh damping of 5 percent is used for the concrete-filled structural modules and fluid damping is neglected. All degrees of freedom were retained in the step-by-step direct integration solution procedure for the in-containment refueling water storage tank boundary and the water. Degrees of freedom in the adjacent walls and floor were condensed by Guyon reduction.
Revision: 23 l        [ Westiflgh00Se                                     3.8-29                                    DRAFT,1998
: 3. Design of Structures, Components, Equipment, cnd Systems
: 50. ACI 349.3R-96, " Evaluation of Existing Nuclear Safety-Related Concrete Structures."
l            51. Letter DCP/NRC 1340, April 7,1998 from Brian A. McIntyre, Westinghouse Electric I                Company, to T. R. Quay, Nuclear Regulatory Commission Enclosure 1.
J l
l l
Revision: 23 DRAFT,1998                                    3.8-74                                 Westinghouse

i E .:
: 3. Design of Structures, Components, Equipment, tnd Systems 1
De vertical elevation of the passive containment cooling water storage tank relative to the top of the shield building cylindrical wall at the tension ring will be measured before and after first filling. The change in relative elevation will be compared against the predicted deflection.
A report will be prepared summarizing the test and evaluating the results.
l             There are no other in-service testing or inspection requirements for the seismic Category I shield building and auxiliary building. However, during the operation of the plant the condition of these structures should be monitored by the Combined License applicant to provide reasonable confidence that the stmetures are capable of fulfilling their intended functions.
3.8.4.8     Construction Inspection Construction inspection is conducted to verify the concrete wall thickness and quantity of concrete reinforcement. The construction inspection includes concrete wall thickness and 2
reinforcement expressed in units of in /ft (linear length) equivalent when compared to standard reinforcement bar sections. Inspections will be measured at applicable sections excluding designed openings or penetrations. Inspections will confirm that each applicable section provides the minimum required reinforcement and concrete thickness as shown . in Table 3.8.4-7. He minimum required reinforcement and concrete thickness represents the minimum values to meet the design basis loads. Table 3.8.4-7 also indicates the reinforcement provided which may exceed the minirnum required reinforcement for the following reasons:
* Structural margin
* Ease of constmction a      Use of standardized reinforcement sizes and spacing 3.8.5       Foundations 3.8.5.1     Description of the Foundations The nuclear island structures, consisting of the containment building, shield building, and auxiliary building are founded on a common 6-foot-thick, cast-in-place, reinforced concrete basemat foundation. The top of the foundation is at elevation 66'-6" l
Adjoining buildings, such as the radwaste building, turbine building, and annex building are                                                      ;
structurally separated from the nuclear island structures by a 2-inch gap at and below the grade. A 4 inch minimum gap is provided above grade. This provides space to prevent interaction between the nuclear island structures and the adjacent structures during a seismic event. Figure 3.8.5-1 shows the foundations for the nuclear island structures and the adjoining                                                   i structures.
i Revision: 23 W Westinghouse                                      3.8-57                                                                   DRAFT,1998 m____.___   _._ . _ _ _ _ _ _ . _                                                                       _ . _ _ _ _ _ _ _ __  _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _

J 4 @ Westinghouse                                                 FAX COVER SHEET Recipient Information                         Sender Information Date:           5/f f /9p                      Name:      D. Lindgren To:           Joe Sebrosky                     Location:  WEC E 330 Phone:                                         Phone:     (412) 374 4856 (301) 415-1132 Facimile:                                      Facimne:   BeQ: (412) 374 4887 (310) 415 2002 Company:      U.S.NRC                                     WIN 284 4887 Location:     Rockville, MD 3
Cover + Pages        1+
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                                                                                                     \
The following pages are being sent from the Westinghouse Energy Center, Monroeville, PA.         ;
If there are any problems during this transmission, please call the sender or WIN 284-6529 or    l Bell (412) 374-6529.
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l Unavailability of Criterion 1                                                                       the associated Are nonsafety mieted SSCs considered in                                                           nonsafety related the calculation of the initiating event                                                             SSCs is not frequency?                                                                        Important to the focused PRA l
l                                       Yes l                                   Crtterion 2                                                                      UnavdaW of Does the unavailability of the nonsafety-                                                                 "
l nonse reisted SSCs significantly affect the          No---e coloulation of the initiating event                                                               SSCs is t important to the focused PRA
!                                       Yes l
Unavaitetsitty of CHterton 3                                                                          the associated            j Does the initiating event significantly                                                         nonsafety related
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i Figure 31 Evaluation of Nonsafety related SSCs Impact on Initiating Event Frequency WCAP 13856                                                                                                                        Revision: 1 mm n a.m m           _ n -

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16 Technical Specifications Table 16.3-1 LIST OF INVESTMENT PROTECTION SHORT TERM AVAILABILITY CONTROLS Systems, Structures, Components                                    Number                                                    MODES Trains (a)                                               Operation (b) 1.0 Instrumentauon Systems 1.1 DAS ATWS Mitigation                                     2                                                               1 1.2 DAS ESF Actuation                                       2                                                               1.2.3.4.5.6 (3) 2.0 Plant Systems 2.1 RNS                                                      1                                                              1.2.3 2.2 RNS - RCS Open                                           2                                                              5.6 (2.3) 2.3 CCS - RCS Open                                           2                                                              5.6 (2.3) 2.4 SWS - RCS Open                                           2                                                              5.6 (2,3) 23 PCS Water Makeup Long Term Shutdown                        1 1.2.3.4.5.6 (4) 2.6 MCR Cooling - Long Term Shutdown                          i                                                               1.2.3.4.5.6 2.7 I&C Room Cooling - Long Term Shutdown                     1                                                               1.2.3.4.5.6 2.8 Hydrogen lgnitors                                         1 1.2.5.6 (2.3) 3.0 Electrical Power Systems 3.1 AC Power Supplies                                         1                                                               1.2.3.4.5 3 2 AC Power Supplies RCS Open                              2 (1)                                                            5.6 (2.3) 3 3 AC Power Supplies - Long Term Shutdown                     i                                                              1.2.3.4.5.6 34 DC Power Supplies - DAS                                    2                                                               1.2.3.4.5.6 (3 i i
Alpha Notes:
ian Refers to the number of trains covered by the availability controls.
ib) Refers to the MODES of plant operauon where the availability controls apply.
Notes:
il) 2 of 3 AC power supplies (2 standby diesel generators and I offsite power supply).
      <2) MODE 5 with RCS open.
I i3) MODE 6 with upper internals in place or casicy level less than full.
(4) MODES 5 and 6 with the' calculated core decay heat greater than 6 MWt.
i i
                                                                                                                                                              )
Revision: 22 April 6,1998                                         16 1-4                                                                          W W8Stingh0US8 I
o
: 16. Technical Specifications Table 16.3-2 (Cont.)
i INVESTMENT PROTECTION SHORT TERM AVAILABILITY CONTROLS 2.0 C: ant Systems 2.1 Normal Residual Heat Removal System (RNS) l OPERABILITY:             One train of RNS injection should be operable APPLICABILITY:           MODE 1,2. 3 ACTIONS CONDITION                        REQUIRED ACTION                COMPLETION 'ITME A. One required train not          A.1 Notify [ chief nuclear officer] or   72 hours operable.                            [on call alternate).
AND A.2 Restore one train to operable status 14 days B. Required Action and             B.1 Submit report to [ chief nuclear     i day associated Completion                officer) or [on-call alternate)
Time not met.                        detailing interim compensatory measures. cause for inoperability, and schedule for restoration to OPERABLE.
AND B.2 Document in plant records the         1 month justification for the actions taken to restore the function to OPERABLE.
Revision: 22
[ WeStingh0038                                     16.3 11                                                              April 6,1998 l
l
  - - - - _ - - - _ - - _ - - - - - _ . - - - -           .- _                                                                                                                                l

+
: 16. Technical Specincatioins Table 16.3 2 (Cont.)
INVESTMENT PROTECTION SHORT TERM AVAILABILITY CONTROLS SURVEILLANCE REQUIREMENTS SURVEILLANCE                                   FREQUENCY SR I.1.1.1                                                                Verify that one RNS pump develops a differential head of     92 days (330] feet on recirculation flow SR 1.1.1.2                                                                 Verify that the following valves stroke open                 92 days RNS V011         RNS Discharge Cont. Isolation RNS V022         RNS Suction Header Cont. Isolation RNS V023         RNS Suction from IRWST Isolation l
l Revision: 22 April 6,1998                                                                                                      16.3 12                          3 W8stinduse
: 16. Technical Specifications Table 16 M iCo ita INVESTMENT PROTECTION SHOW i.TEitM AVAILABILITY CONTROLS 2.0 Plant Systems 2.1 RNS BASES:
The RNS injection function provides a nonsafety-related means of injecting IRWST water into the RCS following ADS actuations. The RNS injection function is imponant because it provides margin in the PRA sensitivity performed assuming no credit for nonsafety-related SSCs to mingate at-power and shutdown events. The margin provided in the PRA study assumes a minimum availability of 90% for this function during the hiODES of applicability, considenng both maintenance unavailability and failures to operate.
One train of RNS injection includes one RNS pump and the line from the IRWST to the RCS. Three of the valves in the line between the IRWST and the RCS are normally closed and need to be opened to allow injection. This equipment does not normally operate during NIODES 1,2. 3. Refer to SSAR section 5.4.7 for additional information on the RNS.
The RNS injection function should be available during MODES 1,2. 3 because decay heat is higher and the need for ADS is greater.
Planned maintenance on redundant RNS SSCs should be performed dunng MODES 1. 2. 3. Such maintenance should be performed on an RNS SSC not required to be available. The bases for this recommendauon is that the RNS is more risk important dunng shutdown MODES when it is normally operaung than dunng other MODES when it only provides a backup to PXS injection.
Planned maintenance on non-redundant RNS valves (such as V0ll, V022. V023) should be performed to minimize the impact on their RNS injecuon and their containment isolation capability. Non-pressure boundary maintenance should be performed dunng MODE 5 with a visible pressunzer level or MODE 6 with the refueling cavity full. In these MODES, these valves need to be open but they do not need to be able to close. Containment closure which is required in these MODES can be satisfied by one normally open operable valve. Pressure boundary maintenance can not be performed dunng MODES when the RNS is used to cool the core, therefore such maintenance should be performed dunng MODES 1,2,3. Since these valves are also containment isolation valves, maintenance that                                                                            l renders the valves inoperable requires that the containment isolanon valve located in senes with the inoperable valve has to closed and de-acuvated. The bases for this recommendauon is that the RNS is                                                                      n more nsk important dunng shutdown MODES when it is normally operating than dunng other MODES when it only provides a backup to PXS injection. In addition, it is not possible to perform pressure boundary maintenance of these valves dunng RNS operanon.
1 Revision: 22 3 Westingt10Use                                                                           16.3 13                             April 6,1998

e y_
: 16. Technical Speedicctions Table 16.3 2 (Cont.)
I INVESTMENT PROTECTION SHORT TERM AVAILABILITY CONTROLS                                    '
2.0 Plant Systems 2.2 Normal Residual Heat Removal System (RNS) RCS Open OPERABILITY:             Both RNS pumps should be operable for RCS cooling APPLICABILITY:           MODE 5 with RCS pressure boundary open.
1                          MODE 6 with upper internals in place or cavity level less than full ACTIONS I
CONDITION                         REQUIRED ACTION                    COMPLETION TIME l   A. One pump not operable.      A.1 Initiate actions to increase the         12 hours I                                           water inventory above the core.
l l                                      AND I
l                                      A.2 Remove plant from applicable             72 hours 1                                           MODES B. Required Action and         B.1 Submit report to (chief nuclear          i day associated Completion            officer] or [on-call altemate]
Time not met.                    detailing interim compensatory                                  ,
measures, cause for inoperability.
and schedule for restoration to                                 l
{
OPERABLE.                                                       I AST)
B.2 Document in plant records the             1 month justification for the actions taken                              l to restore the function to                                      I OPERABLE.                                                        l l
Revision: 22 April 6,1998                                      16.3 14                                   Westingh0USS l
w _________ __      _.
: 16. Technical Specifications Table 16.3-2 (Cont.)
INVESTMENT PROTECTION SHORT TERM AVAILABILITY CONTROLS SURVEILLANCE REQUIREMENTS SURVEILLANCE                               FREQUENCY SR 2.2.1        Verify that one ILNS pump is in operation and that each within 1 day prior to RNS pump operating individually circulates reactor      entenng the MODES coolant at a flow > [900] gpm                           of applicability OR Verify that both RNS pumps are in operation and circulating reactor coolant at a flow > [1800] gpm l
l l
Revision: 22 W   Westinghouse                                   16.3 15                            April 6,1998 1                                                                                                                                                                                             l l                                                                                                                                                                                             l
_ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ . _ _ _ _ _                            _   ._         _                _.       _                                  J
: 16. Technical Specifications Table 16.3-2 (Cont.)
INVESTMENT PROTECTION SHORT TERM AVAILABILITY CONTROLS 2.0 Plant Systems 2.2 RNS - RCS Open 1
BASES:
The RNS cooling function provides a nonsafety related means to normally cool the RCS during shutdown operations (MODES 4,5,6). This RNS cooling function is important during conditions when the RCS pressure boundary is open and the refueling cavity is not flooded because it reduces the probability of an initiating event due to loss of RNS cooling and because it provides margin in the PRA sensitivity performed assuming no credit for nonsafety related SSCs to mitigate at-power and I shutdown events. The RCS is considered open when its pressure boundary is not intact. The RCS is also considered open if there is no visible level in the pressurizer. The margin provided in the PRA study assumes a minimum availability of 90% for this function during the MODES of applicability, considering both maintenance unavailability and failures to operate.
The RNS cooling of the RCS involves the RNS sucuon line from the RCS HL, the two RNS pumps and the RNS discharge line retuming to the RCS through the DVI lines. The valves located in these lines should be open prior to the plant entering reduced inventory conditions. One of the RNS pumps has to be operaung; the other pump may be operaung or may be in standby. Standby includes the capability of being able to be placed into operauon from the main control room. Refer to SSAR section 5.4.7 for additional information on the RNS.
Both RNS pumps should be available dunng the MODES of apphcability when the loss of RNS cochng is nsk important. If both RNS pumps are not available, the plant should not enter these condinons. If the plant has entered reduced inventory conditions, then the plant should take action to restore full system operation or leave the MODES of applicability. If the plant has not restored full system operation or left the MODES of applicability within 12 hours, then actions need to be initiated to merease the RCS water level to either 20% pressurizer level or to a full refueling cavity.
Planned mamtenance affecting this RNS cooling funcuon should be performed in MODES 1,2,3 when the RNS is not normally operaung. The bases for this recommendation is that the RNS is more nsk important during shutdown MODES, especially dunng the MODES of applicability conditions than during other MODES when it only provides a backup to PXS injection.
l l
Revision: 22 April 6,1998                                        16.3 16                                                                   W  W85ti!1ghouS8 l
E_____

M Westinghouse                                             FAX COVER SHEET D
RECIPIENT INFORMATION                SENDER INFORMATION l
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bil b isel            T_s  3. 9. r E 3. 9. 6 S u e_

e Centoina nt P nctration3 3.9.5 3.9    REFUELING OPERATIONS 3.9.5     Containment Penetrations LCO    3.9.5 The containment penetrations shall be in the following status:
: a.         The equipment hatches closed and held in place by (four) bolts or, if open, the containment air filtration system (VFS) shall be OPERABLE and operating ;
: b.         One door in each air lock closed or, if open, the VFS shall be OPERABLE and operating;                                                                                                        ,
: c.         The containment spare penetrations closed or, if open, the VFS shall be OPERABLE and operating;
: d.         Each penetration providing direct access from the containment atmosphere to the outside atmosphere either:
: 1. Closed by a manual or automatic isolation valve, blind flange, or equivalent, or
: 2. Capable of being closed by an OPERABLE Containment Isolation signal.
i APPLICABILITY:            During CORE ALTERATIONS During movement of irradiated fuel assemblies within containment.
ACTIONS l
CONDITION                        REQUIRED ACTION                                                                                   COMPLETION TIME A. LCO not met.                  A.1   Suspend CORE                                                                                         Immediately ALTERATIONS.
Mil 2                                                                                                                        I A.2   Suspend movement of                                                                                  Inuned.intely irradiated fuel assemblies within containment.
l l                  AP600                                        3.9-7                                                                                      05/98    Amendment O Arcivew.cieomos aosim l
I l
L_----------__________.       _ _ _ - _

Centcinment Penstrctions 3.9.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE                            FREQUENCY SR  3.9.5.1 Verify each required containment            7 days penetration is in the required status.                                                      ;
I SR   3.9.5.2 Verify each required containment          In accordance purge and exhaust valve actuates to       with the the isolation position on a manual        Inservice Test actuation signal.                         Program i
SR   3.9.5.3 Verify the VFS can maintain a             24 months negative pressure ($ [-0.125] inches water gauge relative to outside atmospheric pressure) in the area enclosed by the containment and alternate barrier .
SR    3.9.5.4 Operate each VFS train for 1 10           Within 31 days     I continuous hours with the heaters         prior to fuel      i operating.                                movement or core alterations        ;
l l
l l
e AP600                      3.9-8                 05/98    Amendment O

Containment Pcactrctiono B 3.9.5 B 3.9   REFUELING OPERATIONS B 3.9.5   Containment Penetrations BASES BACKGROUND         During CORE ALTERATIONS or movement of irradiated fuel assemblies within containment, pa*.ential releases of        .
fission product radioactivity within containment are monitored and filtered or are restricted from escaping to the environment when the LCO requirements are met.
Monitoring of potential releases of radiation is performed in accordance with Administrative Controls Section 5.5.3, " Radioactive Effluent Control Program."
In MODES 1, 2, 3, and 4, containment operability is addressed in LCO 3.6.1, " Containment." In MODES 5 and 6, closure capability of containment penetrations is addressed in LCO 3.6.8, " Containment Penetrations."
Since there is no potential for containment pressurization due to a fuel handling accident, the Appendix J leakage criteria and tests are not required in Modes 5 and 6.
The containment serves to contain fission product radioactivity that may be released from the reactor core following an accident, such that offsite radiation exposures are maintained within the requirements of 10 CFR 50.34. For a fuel handling accident, the AP600 dose analysis does not rely on containment closure to meet the offsite radiation exposure limits. This LCO is provided as an additional level of defense against the possibility of a fission product release from a fuel handling accident.
The containment equipment hatches, which are part of the containment pressure boundary, provide a means for moving large equipment and components into and out of containment. During CORE ALTERATIONS or movement of irradiated fuel assemblies within containment, an equipment hatch is considered closed if the hatch cover is held in place by at least (fou:r] bolts. Good                                          I engineering practice dictates that the bolts required by this LCO be approximately equally spaced.
l (continued)
AP600                          B 3.9-14                                               05/98 Amendment O

1
* l Centcinment Pcnctrctions D 3.9.5 RASES RACKGROumu       If the equipment hatch is open, an alternative barrier (continued)   between the containment atmosphere and the outside atmosphere shall be in place. Each containment equipment hatch opens into a staging area in the auxiliary building. These staging areas contain doors that open to the radiologically controlled areas of the annex building. The annex building contains a door that opens to the outside atmosphere. The alternate barrier may consist of the staging area in the auxiliary building, or may consist of the staging areas in the auxiliary building and the radiologically controlled areas in the annex building provided the doors from the annex building to the outside atmosphere are closed. The alternate barrier may also consist of a temporary equipment hatch cover that provides equivalent isolation capability. The alternate boundary prevents the airborne fission products from being readily released to the atmosphere if the equipment hatches were open during a fuel handling accident.
If an equipment hatch is open during CORE ALTERATIONS or    j l                    during movement of irradiated fuel assemblies within I                    containment, the containment air filtration system (VFS) i                    shall be OPERABLE, and at least one exhaust fan shall be operating to provide for monitoring of air-borne radioactivity. This system services the containment,
{
and upon detection of high radiation, also services the fuel handling area, the auxiliary building (including the staging areas), and the annex building. If high airborne radioactivity is detected in the area enclosed I
l                    by the alternate barrier, the radiologically controlled area venti 11ation system (VAS) supply and exhaust duct isolation dampers automatically close to isolate the        I affected area from the outside environment, and the VAS exhaust is automatically aligned to the VFS exhaust subsystem. The operation of the VFS exhaust fans provides the system with the ability for monitoring of radioactivity releases from containment following a fuel handling accident and, if operating, will provide l                    filtration of the containment atmosphere.
If a personnel air lock or spare containment penetration is open during CORE ALTERATIONS or during movement of irradiated fuel assemblies within containment, then the containment air filtration system (VFS) shall be OPERABLE and operating to monitor for the release of radioactivity and to provide filtration of the air inside containment. These penetrations open into the auxiliary building. Upon detection of high radiation in the exhaust air from the auxiliary building, VFS will (continued) l l
i AP600                        B 3.9-15                05/98  Amendment O
: n.      .     --

                                                                                                                            \
Containa:nt Penetrctienc   I B 3.9.5 l RASES BACKGROUND      provide filtered exhaust of these areas. Considering (continued)    that these penetrations open into the auxiliary building and not directly to the atmosphere, and that the VFS is in operation, an alternate barrier to the release of radioactivity directly to the environment is provided.
APPLICABLE      For the AP600, there are no safety analyses that SAFETY ANALYSES require containment closure during CORE ALTERATIONS or movement of irradiated fuel assemblies within containment, other than those discussed in LCO 3.6.8.
Fuel handling accidents, analyzed in Reference 1, include dropping a single irradiated fuel assembly and handling tool or a heavy object onto other irradiated fuel assemblies. The requirements of LCO 3.9.4,
                                                              " Refueling Cavity Water Level," ensure that the release of fission product radioactivity, subsequent to a fuel handling accident, results in doses that are well within the guideline values specified in 10 CFR 50.34.
Standard Review Plan, Section 15.7.4, Rev. 1 (Reference 2), defines "well within" to be 25% or less of the limiting dose guideline values.
This specification is included as defense in depth as discussed in Reference 3.
LCO             This LCO provides defense-in-depth against the consequences of a fuel handling accident in containment by limiting the potential escape paths for fission product radioactivity released within containment. This LCO requires that if an equipment hatch, personnel air lock, or spare containment penetration is open during CORE ALTERATIONS or movement of irradiated fuel assemblies within containment, then the containment air filtration system (vrS) shall be OPERABLE and operating to monitor for the release of radioactivity and to provide filtration of the air inside containment.
The VFS is OPERABLE when:                                      ,
: a. One VFS axhaust fan is operating; the    associated HEPA filter and charcoal adsorber are   not excessively restricting flow, and are   capable of         )
performing their filtration function;   and air            l circulation can be maintained;
: b. An alternative barrier between the containment atmosphere and the outside atmosphere is in place.         ,
The alternate barrier may consist of the staging           I area in the auxiliary building, or may consist of the staging areas in the auxiliary building and the radiologically controlled areas in the annex (continued)
()AP600                          B 3.9-16                05/98 Amendment O n._ _

Containment Penetrations 3 3.9.5 BASES LCO                               building provided the doors from the annex building (continued)                     to the outside atmosphere are closed.
Doo.rs in the alternate barrier which are normally closed may be opened for short periods of time for ingress and egress. The alternate barrier may also consist of a temporary equipment hatch cover that provides equivalent isolation capability.
APPLICABILITY                 The containment penetration requirements are applicable during CORE ALTERATIONS or movement of irradiated fuel assemblies within containment because this is when there is a potential for a fuel handling accident. In MODES 1, 2, 3, and 4, containment penetration requirements are addressed by LCO 3.6.1. In MODES 5 and 6, when CORE ALTERATIONS or movement of irradiated fuel assemblies within containment are not being           i conducted, the potential for a fuel handling accident      I does not exist. Containment closure capability in MODES    l 5 and 6 are addressed by LCO 3.6.8.                        !
l ACTIONS                       A.1 and A.2 The required status for the containment equipment hatch, air locks or spare penetration is either closed, or open with the VFS OPERABLE and operating. The required status for the containment penetrations that provide       j direct access from the containment atmosphere to the       '
outside atmoshere is either closed by a manual or          I automatic isolation valve, blind flange or equivalent, or capable of being closed by an OPERABLE Containment Isolation Signal. If the containment equipment hatch or air locks, or any containment penetration that provides direct access from the containment atmosphere to the       !
outside atmosphere is not in the required status, the unit must be placed in a condition where the isolation function is not needed. This is accomplished by immediately suspending CORE ALTERATIONS and movement of    l irradiated fuel assemblies within containment.             j Performance of these actions shall not preclude ccompletion of movement of a component to a safe position.
BURVEYLLANCE                  sR   3.9.5.1 REQUIREMENTS This Surveillance verifies that each of the containment penetrations required to be in its closed position is in that position or the VFS is OPERABLE and operating.
For the VFS to be considered OPERABLE, this surveillance also requires that an alternate barrier is in place .
(continued)
AP600                                   3 3.9-17                05/98  Amendment O AP01uschspecu6030905 f0041396

Centoinment Pcnctrationo D 3.9.5 BASES munVEILLANCE     SR   3.9.5.2 REQUIREMENTS (continued)      This Surveillance demonstrates that each containment purge and exhaust valve actuates to its isolation position on manual initiation. The Surveillance on the open purge and exhaust valves will demonstrate that the valves are not blocked from closing. The Frequency is in accordance with the Inservice Testing Program.
SR   3.9.5.3 This SR verifies the ability of the VFS to maintain a negative pressure ($ [-0.125) inches water gauge relative to outside atmospheric pressure) in the containment and the portions of the auxiliary and / or annex building that comprise the envelope defined as the alternate barrier. This surveillance is performed with the VFS in containment operating. Doors in the alternate barrier which are normally closed may be opened for ingress and egress. The portion of the VAS which services the area enclosed by the alternate barrier is aligned to the VFS exhaust subsystem, and the VAS auxiliary / annex building supply fans and VFS containment purge supply fans not operating. The Frequency of 24 months is consistent with the guidance provided in NUREG-0800, Section 6.5.1 (Ref. 4).
SR   3.9.5.4 The VFS should be checked periodically to ensure that it functions properly. As the operating conditions on this system are not severe, testing each train within 31 days prior to fuel movement provides an adequate check on this system. Operation of the heater dries out any moisture accumulated in the charcoal from humidity in the ambient air.
RXrama-CES       1. AP600 SSAR, Section 15.7.4.
: 2. NUREG-0800, Section 15.7.4, Rev. 1, July 1981.
: 3. MRC Request for Additional Information (RAI) 480.1159F.
: 4. NUREG-0800, Section 6.5.1, Rev. 2, July 1981.
I  II I l
l AP600                         B 3.9-18                           05/98 Amendment o

VFS 3.9.6 3.9        REFUELING OPERATIONS 3.9.6          Containment Air Filtration System (VFS)
LCO        3.9.6                One VFS exhaust subsystem shall be OPERABLE.
APPLICABILITY:                  During movement of irradiated fuel assemblies in the fuel building.
ACTIONS CONDITION                      REQUIRED ACTION                                                                       COMPLETION TIME A.        Required VFS exhaust A.1             Suspend movement of                                                                      Inunediately subsystem                           irradiated fuel inoperable,                         assemblies in the fuel building.
I AP600                                       3.9-9                                        04/98 Draft Amendment P APO1uocampecO6030906 roe 051398 L______.______________.__._.-___.._._._.____._--.-     --                    - - -                                                                                            --    - - - -

VFS 3.9.6 SURVEILLANCE REQUIRE 3MNTS SURVEILLANCE                                                                                                          FREQUENCY SR   3.9.6.1   operate each VFS exhaust subsystem                                                                                       Within 31 days for 2 10 continuous hours with the                                                                                      prior to fuel heaters operating.                                                                                                       movement SR   3.9.6.2   Verify the VAS fuel handling area                                                                                        24 months subsystem aligns to the VFS exhaust subsystem on an actual or simulated actuation signal.
SR  3.9.6.3    Verify one VFS exhaust subsystem can                                                                                     24 months maintain a negative pressure (5, [-
0.125] inches water gauge relative to outside atmospheric pressure) in the fuel handling area.
                                                                                                                                                                   )
l l
AP600                          3.9-10                                             04/98 Draft Amendment P

  ,                                                                                l VFS B 3.9.6 B 3.9    REFUELING OPERATIONS l
B 3.9.6     Containment Air Filtration System (VFS)                            )
RASES BACKGROUND          The radiologically controlled area ventilation system (VAS) serves the fuel handling area of the auxiliary building, and the radiologically controlled portions of the auxiliary and annex buildings, except for the health physics and hot machine shop areas which are provided' with a separate ventilation system (VHS). If high airborne radioactivity is detected in the exhaust air from the fuel handling area, the auxiliary building, or the annex buildings, the VAS supply and exhaust duct isolation dampers automatically close to isolate the affected area from the outside environment and the containment air filtration exhaust subsystem starts.
The VFS exhaust subsystem prevents exfiltration of unfiltered airborne radioactivity by maintaining the isolated zone at 5-[-0.125] inches water gauge pressure relative to the outside atmosphere. Monitoring of potential releases of radiation is. performed in accordance with Administrative Controls Section 5.5.3,
                        " Radioactive Effluent Control Program."
For a fuel handling accident, the AP600 dose analysis does not rely on the OPERABILITY of the VAS or VFS exhaust subsystem to meet the offsite radiation exposure limits. This LCO is provided as an additional level of defense-in-depth against the possibility of a fission product release from a fuel handling accident in the fuel building. The plant vent radiation detectors monitor effluents discharged from the plant vont to the environment.
Each VFS exhaust subsystem includes one 100 percent capacity exhaust air filtration unit, and the associated exhaust fan, heater and ductwork.
l l
l 1
l (continued)
       )AP600                            B 3.9-19         04/98 Draft Amendment P

n                                                                                                                                                                          l VFS S 3.9.6 i
BASES BACKGROUND                                                                         The filtration units are connected to a ducted system (continued)                                                        with isolation dampers to provide HEPA filtration and charcoal adsorption of exhaust air from the containment, fuel handling area, radiologically controlled areas of the auxi'liary and annex buildings. A gaseous radiation monitor is located downstream of the exhaust air filtration units to provide an alarm if abnormal gaseous releases are detected. The plant vent exhaust flow is monitored for gaseous, particulate and iodine releases to the environment. During conditions of abnormal airborne radioactivity in the fuel handling area, auxiliary and/or annex buildings, the VFS exhaust subsystem provides filtered exhaust to minimize unfiltered offsite releases.
The VAS is described in Reference 1 and the VFS is described in Reference 2.
APPLICABLE                                                                         The VFS is not required to mitigate the SAFETY ANALYSES consequences of the limiting Design Basis Accident                               I (DBA), which is a fuel handling accident. The analysis of the fuel handling accident, given in Reference 3,                           i assumes that all fuel rods in an assembly are damaged.
The DBA analysis of the fuel handling accident does not assume that the VFS provides a filtered exhaust, and its operation would reduce the consequences of the fuel handling accident.
J This specification is included for defense-in-depth as discussed in Reference 6.
LCO                                                                                one VFS exhaust subsystem id required to be OPERABLE to reduce the consequences of a fuel handling accident by filtering the fuel building atmosphere.
A VFS exhaust subsystem is considered OPERABLE when its associated:
: a.                      Exhaust fan is capable of operating;
: b.                      MEPA filter and charcoal adsorber are not                I excessively restricting flow, and are capable of performing their filtration functions
: c.                      The associated heater and ductwork are capable of operating.-                                              '
l (continued)
AP600                                                                                      B 3.9-20         04/98  Draft Amendment P

e VFS B 3.9.6 BASES APPLICABILITY During movement of irradiated fuel in the fuel handling area, one VFS exhaust subsystem is OPERABLE to alleviate the potential consequences of a fuel handling accident.
ACTIONS       M When the required VFS exhaust subsystem is inoperable during movement of irradiated fuel assemblies in the fuel building, action must be taken to place the unit in a condition in which the LCO does not apply. Action must be taken immediately to euspend movement of irradiated fuel assemblies in the fuel building. This does not preclude the movement of fuel to a safe                                                                                                             ;
position.                                                                                                                                                    j i
SURVEILLANCE  SR  3.9.6.1                                                                                                                                                ,
REQUIREMENTS Each VFS exhaust subsystem should be checked 31 days prior to fuel movement in the fuel handling area to ensure that it functions properly. As the operating conditions on this subsystem are not severe, testing each subsystem within one month prior to fuel movement provides an adequate check on this system. Operation of the heater dries out any moisture accumulated in the charcoal from humidity in the ambient air.
SR  3.9.6.2 This SR verifies that the VAS fuel handling area subsystem aligns to the VFS and that the VFS exhaust subsystem starts and operates on an actual or simulated actuation signal. During the post-accident mode of operation, the VAS fuel handling area subsystem aligns to the VFS filtered exhaust subsystem. The 24 month Frequency is consistent with Reference 4.
SR  3.9.6.3 This SR verifies the integrity of the fuel handling area of the auxiliary building enclosure. The ability of the VAS and VFS to maintain negative pressure (5, [-0.125]
inches water gauge relative to outside atmospheric pressure) in the fuel handling area of the auxiliary building is periodically tested to verify proper                                                                                                             i function of the VAS and VFS exhaust subsystem. During                                                                                                        l this surveillance, the VAS fuel handling area subsystem is aligned to the operating VFS exhaust subsystem. The fan for the VAS fuel handling area subsystem is off. In this configuration, the VFS exhaust subsystem is Amm4mmmA ta mm4nem4n a nanmelva nramanca in ehm fuel (continued)
  @ AP600                       3 3.9-21                                                                                                         04/98 Draft Amendment P e,__,-

1 l
J VFS 3 3.9.6 BASES l   Surveillance                   SR   3.9.6.3  (continued)
Requirements handling area of the auxiliary building ($ (-0.125]
inches water gauge relative to outside atmospheric pressure), to prevent unfiltered and unmonitored leakage. Doors may be opened for short periods of time to allow ingress and egress. During this surveillance, the VAS may be servicing the remaining portions of the    )
auxiliary and annex buildings. The Frequency of 24 months is consistent with the guidance provided in l
NUREG-0800, Section 6.5.1 (Ref. 5).
REFERENCES
: 1. AP600 SSAR, Section 9.4.3.
: 2. AP600 SSAR, Section 9.4.7.
: 3. SSAR, Section 15.7.4.
: 4. Regulatory Guide 1.52 (Rev. 2).
: 5. NUREG-0800, Section 6.5.1, Rev. 2, July 1981.
: 6. NRC Request for Additional Information (RAI) 480.1159F.
4 l
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i
          'AP600                                   B 3.9-22         04/98  Draft Amendment P AP014eespe616030906 rO6-051398

M Westinghouse                                             FAX COVER SHEET w
RECIPIENT INFORMATION                               SENDER INFORMATION oxrE:                        O5//5/'//                          n^u e-                   Mi,e Pip /ci TO*-                         /                           ''
LOCATION:
c ][ rrJ l\/               )G)/ /S 0i)                             ENERGY CENTER -
EAST PHONE:                      FACSIMILE: h-/-JO/ '//f 2279        PHONE:                      Omce: [tft) {7./ gpo COMPANY:                                                         FacsimHe:                   mn:           284 4887
[/ j A/ N O. -
outside: (412)374-4887 t.OCATION:                    k k,do Nd Cover + Pages                 1+   /7 The following pages are being sent from the Westinghouse Energy Center, East Tower, Monroeville, PA. If any problems occur during this transmiselon, please call:
WIN: 284 6529 (Beverly) or Outside: (412/3744529)
Ur A/                            AWL _                                -/
J;Th&c                 om TW .u-w .'
f Z u /at~    f O                   s         W                            __
O                        O M                                                 .
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    - _ -                             -                                                                                        )

                                                                                                                                              'l f,g  .-
Westinghouse                        Energy Systems                           sci 355 Electric Corporation                                                        Pinsburp Pent:sytvarua 15230 0355 DCP/NRC1366 NSD-NRC-98-5696 Docket No.: 52-003 May 15,1998 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: T. R. QUAY

==SUBJECT:==
RESPONSES TO STAFF REQUESTS REGARDING THE AP600 TIER I MATERIAL, REVISION 4

==Dear Mr. Quay:==

Enclosed are three copies of Westinghouse's responses to ITAAC meeting open items 6800,6801, 6806,6808, and 6810 related to various comments from the staff on Revision 4 of the AP600 Certified Design Material. Rese ITAAC open item responses were requested by the staff in telecons held with the staff during the period from May I through May 11,1998.
This submittal closes, from Westinghouse's perspective, open items 6800,6801,6806,6808, and 6810.
As a result, the Westinghouse status column will be changed to " Confirm W" in the Open Item Tracking System (OITS). De NRC should review these responses and inform Westif.ghouse of the status of the open items to be designated in the "NRC Status" column of the OITS.
Please contact Mr. Eugene J. Piplica at (412) 374-5310 if you have any questions concerning this transmittal.
O Brian A. McIntyre, Manager Advanced Plant Safety and Licensing jml                                                                                                                                                         i Enclosure                                                                                                                                                  i l                                                                 cc:       J. N. Wilson, NRC (w/ Enclosure) l                                                                           N. J. Liparulo, Westinghouse (w/o Enclosure) mw

l                                              ATTACHMENT l'                                    WESTINGHOUSE LETTER DCP/NRCl366 l
1 O

  ,          ITAAC OPliN ITEM g=  =it
:+
OITS 6800 - ITAAC Meeting Open item Per telecon with NRC staff on 5/5/98 (Bongarra)
Section 3.2 fiuman Factors Engineering Change the column title fren " Alarm" to " Alert" in SSAR Table 18.12.2-1 (both sheets) to be consistent with the minimum inventory tables in Tier 1.

===Response===
The requested change will be made in SSAR Revision 23 as indicated.
SSAR Revision:
See attached markup of Table 18.12.2.-l.
Tier 1 Revision:
None 3 Westinghouse                                                                        OITS 6800-1 1
L____________._.________

!                                                              ITAAC OPEN ITEM
                                                                                                                                                                                                              .=;      :
                                                                                                                                                                                                              .=
l                                                                                                                                                                                                              _
l l                                                                                                                                         Table 18.12.2-1 (Sheet I of 2)
MINIMUM INVENTORY OF
!                                                                                                                            FIXED POSITION CONTROLS, DISPLAYS, AND ALERTS
!                                                l                                                                         Description                    Control            Display              Alarm 4Iert*
Neutron flux                                                                                              x                       x Neutron flux doubling x
Startup rate                                                                                              x                      .x RCS pressure                                                                                              x                       x Wide range Thot                                                                                           x Wide range Teold                                                                                           x                       x RCS cooldown rate compared to the limit                                                                    x                       x based on RCS pressure Wide range Tcold compared to the limit                                                                     x                       x based on RCS pressure Change of RCS temperature by more than                                                                                              x 5'F in the last 10 minutes Containment water level                                                                                     x                       x Containment pressure                                                                                        x                       x Pressurizer water level                                                                                    x                       x Pressurizer water level trend                                                                               x Pressurizer reference leg temperature                                                                       x Reactor vessel Hot leg water level                                                                          x                       x Pressurizer pressure                                                                                        x Core exit temperature                                                                                       x                       x RCS subcooling                                                                                              x                       x RCS cold overpressure limit                                                                                 x                       x IRWST water level                                                                                           x                       x PRHR flow                                                                                                   x                       x PRHR outlet temperature                                                                                      x                       x PCS storage tank water level                                                                                x PCS cooling flow                                                                                            x IRWST to RNS suction valve status                                                                            x                       x Remotely operated containment isolation                                                                      x valve status
* Containment area high range radiation level                                                                  x                       x Containment pressure (extended range)                                                                        x OITS 6800-2 M % h00$8 e
L______                        _ _ _ _ _ _ _ _ _                                                         _ . _ _                                 __ _ _ _                _____________._.___.________.__.____________________._________

ITAAC OPEN ITEM a  .3 E!
Table 18.12.2-1 (Sheet 2 of 2)
MINIMUM INVENTORY OF FIXED POSITION CONTROLS, DISPLAYS, AND ALERTS l                       Description                             Control                   Display             Alarm 4Iert'2' Containment hydrogen concentration                                                      x CMT level'"                                                                             x Manual reactor trip (Also initiates turbine                  a trip Figure 7.21, sheet 19.)
Manual safeguards actuation                                  x Manual CMT actuation                                          x Manual main control room emergency                            x habitability system actuation
* Manual ADS actuation (1-3 and 4)                              x Manual PRilR actuation                                        x Manual contamment cooling actuation                           x Manual IRWST injection actuation                              x l
Manual containment recirculation actuation                    x Manual containment isolation                                  x Manual main steamline isolation                               x Manual feedwater isolation                                    x                                                                                            1 Manual containment hydrogen igniter                           x (nonsafety related).
N21tE I. Althougn this parameter does not satisfy any of the selection criteria of subsection 18.12.2, its importance to manual actuation of ADS jostifies its placement on this list.                                                                                         !
: 2. These parameters are used to generate visual alerts that identify challenges to the critical safety functions.
For the main control room, the visual alerts are embedded in the safety-related displays as visual signals.                                           j For the remote shutdown workstation, the visual alerts are embedded in the nonsafety-related displays as visual signals.
: 3. These instruments are not required after 24 hours. (Subsection 7.5.4 includes more information on the class IE valve position indication signals, specified as part of the post-accident monitoring instrumentation.)
: 4. This manual actuation capability is not needed at the remote shutdown workstation.
i olTs 6800 3
[ Westinghouse 6
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _                  _ _ _         _       ___._._            _ _ _   __          ___ _ _ _ _         __ _m.._.__    . _ _ _ _ _ _ _ _ _ _   _____-__________m___w

ITAAC OPEN ITEM s
:=
:m OITS 6801. ITAAC Meeting Open Item Per telecon with NRC staff on 5/5/98 (Bongarra)
Section 3.2 Human Factors Engineering ne staff has questioned the inspection, test, analysis (ITA) cnd the acceptance criteria (AC) for design commitment number 7 (Main Control Room) and number 10 (Remote Shutdown Room). He ITA and the AC need to address the following environmental factors with respect to human factors:
         - illumination (proper lighting, glare, reflections, etc.)
         - noise (acoustics, attenuation)                                                                    1
         - communications (both within the MCR and to the outside)

===Response===
l The design description and commitments for the Lighting System are provided by subsection 2.6.5.
Table 2.6.51 specifies the ITAAC. The design description and commitments for the Communication System are provided by subsection 2.3.19. Table 2.3.19-2 specifies the ITAAC. Reference to these -
two systems and their ITAAC will be added to the ITA and AC for the Human Factors Engineering, subsection 3.2, design commitments 7 (Main Control Room) and 10 (Remote Shutdown Room).
Neither General Electric's ABWR nor Combustion Engineering's System 80* have explicit design commitments and ITAAC for lighting, noise, and communications within their Human Factors Engineering sections. Rey do have separate subsections, as we do, devoted to the Lighting System and to the Communication System. Our ITAAC for these systems is comparable to the respective ones specified by General Electric and Combustion Engineering.
Neither General Electric nor Combustion Engineering have specified a design commitment and ITAAC for noise levels in the main control room (MCR) and the remote shutdown room (RSR). Furthermore,         I to measure the maximum ambient noise levels in the MCR and RSR will require the plant to be              ;
operating and generating electricity. De plant is not allowed to operate at power until all ITAAC have been successfully completed. For this reason, it is impossible to write an acceptance criterion for a specified ambient noise level whose success can be measured. Herefore, noise level is not explicitly specified in the Certified Design Material.
Utility input for the maximum ambient noise level is provided by the utility requirements documents.
As described in SSAR subsection 18.2.1.2, Assumptions and Constraints / Utility Requirements, utility input in the form of utility requirements documents and input from utility representative groups is used as input to the human system interface design.
OITS 6801-1 W

ITAAC OPEN ITEM Su
                                                                                                                                                         =-
as f
1 SSAR Revision:
None Tier 1 Revision:
Table 3.2-1 is modified as shown below to include lighting and communications as part of the ITAAC for design commitments 7 and 10.
Inspections, Tests, Analyses, and Acceptance Criteria Table 3.2-1 specifies the inspections, tests, analyses, and associated acceptance criteria for the HFE program. MCR RSW, and local control stations.
l l
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I OITS 6801-2 g ggg,

ITAAC OPEN ITEM
                                                                                                   =: :=
                                                                                                   =
g Table 3.21 (cont.)
Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment              inspections, Tests, Analyses       Acceptance Criteria
: 7. The MCR provides a            i) See Certified Design         i) See Certified Design suitable workspace               Material, subsection 2.7.1,     Material, subsection 2.7.1, environment for use by the       Nuclear Island Nonradioactive   Nuclear Island Nonradioactive MCR operators.                    Ventilation System.            Ventilation System.
ii) See Certified Design        ii) See Certified Design                                     1 Material, subsection 2.2.5,     Matenal, subsection 2.2.5,                                   j MCR Emergency Habitability      MCR Emergency Habitability System.                         System.
iii) See Certified Design       iii) See Certified Design Material, subsection 2.6.3,     Material, subsection 2.6.3, Class IE de and UPS System. Class IE de and UPS system.
l                                     iv) See Certified Design        iv) See Certified Design l                                    Material, subsection 2.6.5,      Material, subsection 2.6.5, l                                     Lighting System.                Lighting System.
l l                                     v) See Certified Design         v) See Certified Design l                                    Material, subsection 2.3.19,     Material, subsection 2.3.19, 1                                     Communication System.           Communication System.
: 8. He HSI resources              An inspection of the HSI         Re HSI(at the time of plant available to the MCR              resources available in the MCR  startup) includes an alarm operators include the alarm       for the MCR operators will be   system, plant information I   system, plant information        performed.                       system (nonsafety-related system (nonsafety-related                                         displays), wall panel displays), wall patsel                                             information system, and information system, and                                           nonsafety-related controls (soft i   nonsafety-related controls (roft                                  and dedicated).
and dedicated).
[ W85tliigh00S8 I
l

                                                                                                                 ---------------R i
                                                                                                                                 \
ITAAC OPEN ITEM ts
                                                                                                           ~
                                                                                                                 =!
si Table 3.21 (cont.)
Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment               Inspections, Tests, Analyses       Acceptance Criteria
: 9. 7he RSW includes reactor       An inspection of the RSW will   ne RSW includes reactor operator workstation (s) from     be performed.                   operator workstation (s),
which licensed operators perform remote shutdown operations.
I   10. The RSR provides a            i) See Certified Design         i) See Certified Design suitable workspace                Material, subsection 2.7.1,     Material, subsection 2.7.1, environment, separate from the    Nuclear Island Nonradioactive   Nuclear Island Nonradioactive MCR, for use by the RSW           Ventilation System.             Ventilation System.
operators.
l                                     ii) See Certified Design        ii) See Certified Design l                                     Afaterial, subsection 2.6.S,    Afaterial, subsection 2.6.5, l                                     Lighting System.                Lighting System.
I l                                    iii) See Certified Design        lii) See Certified Design l                                    Afaterial, subsection 2.3.19,    Afaterial, subsection 2.3.19, l                                     Communication System.           Communication System, l
l l
in s8014 l       W M
Westinghouse l

1 l
ITAAC OPEN ITEM
[
OITS 6806 - ITAAC Meeting Open Item Per telecon with NRC staff on Sn/98 (nrom)
The following items need to be addressed to close the commitments made in Westinghouse response to FSER Open Item 480.1084, Revision 2, in letter DCP/NRCl225 dated January 22,1998:
a) Add to the SSAR, the description of the baseline testing for the containment water coverage measurements described in paragraph 3 of the FSER Open Item response.
b) Add, if necessary, the appropriate reference to the baseline testing to the passive containment cooling test abstract in the Initial Test Program.
c) Add the Tech Spec revisions to SR 3.6.6.6 and the BASES for B 3.6.6 as committed in the revised response.

===Response===
ne following changes will be incorporated in the AP600 SSAR, revision 23:
a) SSAR subsection 6.2.2.4.2, preoperational testing of the Passive Containment Cooling System, will be revised to incorporate the discussion in paragraph 3 of the Westinghouse response to FSER Open item 480.1084, revision 2, as requested.
I b) SSAR subsection 14.2.9.1.4, General Test Acceptance Criteria and Methods, item d), is revised to include a reference to SSAR subsection 6.2.2.4.2.
I c) Revision 9 of the Technical Specifications, sections SR 3.6.6.6 and B 3.6.6 will be revised as committed in the response to FSER Open Item 480.1084, revision 2.                                                                 1 Tier 1 Revision:
None 1
OITS 6806-1
_ _ _ . _ _ _ _ _ _ _ . _ _ _ . _ _ _ .       - _ _             -- -                            --     ---' -'^- " ' ' ' - ' ' - ~ ~ ~ ~ ~ ~

5 ITAAC OPEN ITEM EI In SSAR Revisions:
SSAR subsection 6.2.2.4.2 is revised as follows:
6.2.2.4.2   Preoperational Testing Preoperational testing of the passive containment cooling system is verified to provide adequate cooling of the containment. He flow rates are confirmed at the minimum initial tank level, an intermediate step with all but one standpipe delivering flow and at a final step with all but two standpipes delivering to the containment shell. De flow rates are measured utilizing the differential pressure across the orifices within each standpipe and will be consistent with the following minimum flow rates:
442 gpm at the minimum operating water level 122 gpm at a level after the first standpipe is uncovered
                  =
71.5 gpm at a level after the second standpipe is uncovered l             The containment coverage will be measured at the base of the upper annulus in addition l
to the coverage at the spring line for thefullpow case using the PCS water storage tank l             delivering to the containment shell and a lowerpow case with both PCS recirculation l            pumps delivering to the contain:nent shell For the lowpow case, a throttle valve is used l
to obtain a lowpow rate less than thefull capacity of the PCS recirculation pumps. This l            pow rate is then re-established for subsequent tests using the throttle valve. These
  -l             benchmark values will be used to' develop acceptance criteria for the Technica!
l             Specipcations. The fullpow condition is selected since it is the most importantpow rate l            from the standpoint ofpeak containment pressure and the lowerflow rate is selected to l             verify wetting characteristics at less thanfullpow conditions.
SSAR subsection 14.2.9.1.4, Passive Containment Cooling System, General Test Acceptance Criteria and Methods, item d) is revised as follows:                                                                      l d) he proper operation of the passive containment cooling water distribution bucket and weirs is verified and proper wetting of the containment is observed and recorded during draindown testing in item c, above. Water delivery and coverage is verified at the initial I                   minimum water level and as each of the first two standpipes is uncovered. Water l                   coverage is measured at the springline and the base of the upper annulus as described l                   in subsection 6.2.2.4.2.
OITS 6806-2 l

l I
ITAAC OPEN ITEM                                                                                                                                  '
!     Tech Spec Revisions:                                                                                                                             l Note: All Tech Spec changes are denoted as bold italic for added text and as a stfikeout for deleted text.                                                                                                                                   '
Note: The following changes are proposed for inclusion in the next revision of the Tech Specs Revise to the Frequency for Surveillance Requirement 3.6.6.6 in Technical Specification Section 3.6.6 as follows:
l l   SR    3.6.6.6 verify passive containment cooling system flow                     10 Years and I                    and water coverage performance in accordance                    after the first I                    with the system Level operability Testing                       fuel cycle Program Revise the third paragraph of the BACKGROUND in the Technical Specification BASES for B 3.6.6 as follows:
Upon actuation of the isolation valves, gravity flow of water from the cooling water tank (contained in the shield building structure onto the upper portion of the containment above     the containment) shell reduces      the conta        inment pressure and temperature following a DBA.
initiallyThe    flow of water established             to the that to assure      containment the requiredshellshortsurface                    term                 is containment cooling requirements followins the postulated worst case LOCA are achieved. As the decay heat from the core becomes less with time, the water flow to the containment shell is reduced in two steps.       The change in flow rate is attained without active components in the system and is dependent only on the decreasing water level in the elevated storage tank. In order to ensure the containment surface is adequately and effectively wetted, the water is introduced at the center of          the containment dome and flows l                      outward,      weirs are placed on        the dome surface to distribute the water and ensure effective wetting of the dome and vertical sides of the containment shell. The monitoring of the containment surface through the Reliability Assurance Program (RAP) and the Inservice Testing Program assures surface containment does not unacceptably I                  degrade containment heat removal performance. During the initial t
l                   test program the containment coverage will be measured at the base i                  of the upper annulus in addition to the coverage at the spring ifne                                                              l 1
for the full flow case and a lower flow case with PCS recirculation                                                             '
l                  pumps delivering to the containment shell. These benchmark values at I                   the base of the upper annulus will be used to develop acceptance                                                                '
I                  criteria for technical specifications. contamination can be removed by PCS actuation or by using coating vendor cleaning procedures.
W . Westinghouse

l a
ITAAC OPEN ITEM
:r.y n OITS 6808. ITAAC Meeting Open Item Per telecon with NRC staff on 5/8/98 (Young)
Flooding issues in ITAAC a) Add text to SSAR subsection 3.4.1.1.1 that Figure 3.41 represents the water barrier as discussed in Tier 1 Section 3 3, Table 3.3-6, item 4.a.
b) Ref. Tier 1, Section 3.3 Table 3.3-2. Add headings to columns 2 and 3 to clarify the information in the columns. For example, " Flooded Room" for column 2 and " Protected Room" for column 3.
c) Verify that the room numbers in Table 3.3-2 and the maximum Good levels for each room are consistent with the SSAR description in SSAR section 3.4.

===Response===
a) The SSAR will be revised as requested.
b) ne Tier I table will be revised as requested.
c) The room numbers in Table 3.3 2 and maximum flood levels are consistent with the SSAR description in SSAR section 3.4. However, to match barrier requirements with expected flood levels the entry for the mechanical equipment room (room 12405) will be revised in the table.
SSAR Revision:
SSAR subsection 3.4.1.1.1, seventh paragraph, revise to state:
    "he seismic Category I stmetures below grade are protected against flooding by a water barrier consisting of waterstops and a waterproofing system. De waterproofing system is provided by . ."
Tier 1 Revision:
AP600 Tier 1 Material Section 3.3, " Buildings," Table 3.3-2, under columns heading "Between Room Number to Room Number", add column heading " Room with Postulated Flooding Source" to column 2 and column heading " Adjacent Room" to column 3.
OITS 6808-1 Y Westinghouse

6 ITAAC OPEN ITEM ire AP600 Tier i Mateial, Section 3.3., " Buildings," Table 3.3-2, line 10, revise to show the Maximum Flood f.evel is 4 inches for Room 12405.
Table 3.3 2 NI Building Room Boundaries Required to Have Flood Barrier Floors and Walls Between Room Number to Room Number i                         Boundary /                        Room with Postulated i               Maximum Flood Level (inches)                   Flooding Source          Adjacent Room Floor /36                                12306                    12211 Floor /3                                12303                 12203/12207 Roor/3                                  12313                 12203/12207 12201/12202/12207 Floor /l                                12300              12203/122N/12205 Floor /3                                12312                    12212 Wall /36                                 12306                    12305 12301/12302/12303 Roor/l                                  12401                 12312/12313 Wall /l                                 12401
                 .-                                                                                      12411/12412 Floor /36                                124M                     123M i                          Roor/G4                                                                                                     I 12405                    12305                                    l Floor /36                                12406                    12306 Wall /36                                 12404                    12401 Wall /l                                 12421                    12452 Floor /3                                 12501              12401/12411/12412                              I Floor /3                                 12555              12421/12423/12422 Wall /36                              12156/12158              12111/12112 l
T Westinghouse                                                                            orrs s808-2

1 o
ITAAC OPEN ITEM rs= ==
OITS 6810       ITAAC Meeting Open Item Per telecon with NRC staff on 5/8/98 (Peralta)
SSAR Chapter I, Appendix I A. Conformance with Regulatory Guides.
He exception to RG 1.68.3, Preoperational Testing of Instrument and Control Air Systems, is no longer applicable as the test of this system in the Initial Test Program meets the requirements of RG 1.68.3. He exception in Appendix 1 A should be deleted and the AP600 Position should be changed to " Conforms."

===Response===
The exception for Regulatory Guide 1.68.3 will be removed from Appendix 1 A of the SSAR, Rev 23.
SSAR Revision:                                                                                               ;
See attached markup of Appendix 1 A.
Tier 1 Revision:
None i
iTs as1S1 T westinghouse l-   --        ---                                          -                       -     _ ---      - _ -        --

I b
ITAAC OPEN ITEM j
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Criteria   Referenced                  AP600 Section    Criteria                  Position        Clarification / Summary Description of Exceptions Reg. Guide 1.68.3 (Task RS 709 4),4/82 - Preoperational Testing of Instrument and Control Air Systems 1
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1 1
OITS 6810-2 W Westinghouse L

May 18,1998 Ted Quay - 301 4 15-2002 Subject - AP600 COL Information Items Ted,-
Attached is the six page table we discussed during our phonecall. Based on the two examples we discussed, I think you can understand the process we went through.
As a result of our phone call, we understand that the NRC did not necessarily include in the FSER all of the COL information items we have in the SSAR. I would therefore question if we need them, because each COL item must be there for some reason.
Confirmatory item 1.81 reads "The staff will ensure that the COL ' action' items identified by the staff are consistent with those identified by Westinghouse."' It would therefore seem that the lists would have to be identical, not that one is a subset of the other.
Take a look and we can discuss this. It is a good place to start.
l 1
1 i
[                                                                                                                               l

Comparisen of COL action items between SSAR and FSER SSAR Table 1.8-2 Item No. SSAR Subsection No.                                                     FSER Appendix F Item No.
1.1 1                     1.1.7                                                                  /
2.1 1                     2.1.1                                                                   2.1-1 2.1-1                     2.1.1                                                                   2.1.1-1 2.1 1                     2.1.1                                                                   2.1.2- 1 2 1-1                     2.1.1                                                                   2.1.3- 1 2.2 1                     2.2.1                                                                   2.2-1 2.2-1                     2.2.1                                                                   2.2.1-1                                                            j 2.2 1                     2.2.I                                                                   2.2.2-I                                                             l 2.2-1                     2.2.1                                                                   2.2.3-1 2.3-l                     2.3.6.I                                                                 2.3.1-1 2.3 2                     2.3.6.2                                                                 2.3.2-1                                                            {
2.3-3                     2.3.6.3                                                                 2.3.31 2.3 4                     2.3.6.4                                                                 /
23-5                      2.3.6.5                                                                 2.3.51 f
2.4-1                     2.4.1.1                                                                 2.4.1-1 2.4-2                     2.4.1.2                                                                 2.4.2-1 2.4 2                     2.4.1.2                                                                 2.4.3-1 2.4-2                     2.4.1.2                                                                 2.4.4-1 2.4-2                     2.4.1.2                                                                 2.4.51 2.4-2                     2.4.1.2                                                                 2.4.6-1
    /                          /                                                                       2.4.71
    /                          /                                                                       2.4.8-1
    /                          /                                                                       2.4.9- 1 24-2                      2.4.1.2                                                                 2.4.10 1 2.4 .1                     2.4.1.3                                                                 2.4. I 1-1 2.4-4                      2.4.1.4                                                                 2.4.12-1 24-5                       2.4.1.5                                                                 2.4.13-1 2 4-6                      2.4.1.6                                                                 2.4.14 1 251                        2.5.1                                                                   2.5.1-1 2.5 2                      2.5.2.I                                                                 2.5.2-1                                                             )
    /                          /                                                                       2.5 2-2                                                             l 2.5-3                      2.5.3                                                                    2.5.3-1                                                            j 25-4                       2.5.4.6.I                                                                2.5 4.1-1                                                          i
    /                          /                                                                        2.5.4.1 2
    /                          /                                                                        2.54.2-1 25-5                       2.5 4.6.2                                                                2.5.4.2-2 2.5-6                      2.5.4.6.3                                                                2.5 4.3-1
;   2 5-6                      2.5.4.6.3                                                                2.5 4.3-2 2.5-7                      2.5.4.6.4                                                                2.5.4.4-1 i   2.5-8                      2.5.4.6.5                                                                2.5 4.5-1 2.5-9                      2.5 4 6.6                                                                2.5.4.6-1
    /                          /                                                                        2.5.4.7-1 2.5-10                     2.5 4.6.7                                                                2.5 4.7-2 2.5-11                     2.5.4.6 10                                                               2.5.4.10-1 2.5 12                     2.5.4.6.1I                                                               2.5.4. I 1-1 2.5-13                     2.5.5                                                                    2.5.5-1 2.5 14                     2.5.6                                                                    2.5.6 1

e SSAR Table 1.8-2 Item No. SSAR Subsection No. FSER Appendix F Item No.
3.3 1                     3.3.3               /
           /                          /                   3.3.2.21 3.4-1                    3.4.3               /
           /                          /                   3.4.2-1
           /                          /                   3.4.2-2 3.5-1      <               3.5.4               /
           /                          /                   3.5.1.31
           /                          /                   3.5.1.3-2
           /                          /                   3.5.1.3-3
           /                          /                   3.5.1.3-4 3.6-1                      3.6.4.1             /
3 6-2                      3.6.4.2             3.6.3.4 1 3.7-1                      3.7.5.1             3.7.2.13-1
          /                           /                   3.7.2.I6-1 3.7-2                      3.7.5.2             3.7.41 3.7-2                      3.7.5.2             3.7.4-2 3.7-3                      3.7.5.3             /
3.7-4                      3.7.5.4             /
3.%i                       3.8.6.I              3.8.21
          /                           /                    3.8.2.4-1 3.S 2                      3.8.6.2              3.8.4.4 1 3 8-3   ,,                 3.8 6.3             /
3.9-1                      3.9.8.!             /
3.9-2                      3.9 8.2              3.9.3.1 1 3.9-3                      3.9.8.3             /
3.9-4                      3.9.8 4             /
3.9-5                      3.9.8.5             /
3.9-6                       3.9.8.6             /
3.10 1                      3.10.6               3.10-1 3.11 1                     3.11.5              /
4.2-1                       4.2.5                4.2.8 1 4.3-1                       4.3.4                4.2.8-1 4.3 2                       4.3.4               /
441                         4.4.7                4.2.8-1 521                         5.2.6.1              5.2.1.1-1 5.21                        5.2.6.1              5.2.1.1-2 52-2                        5.2.6.2              5.2.4 1
          /                           /                    5.2.4 2 5.3 1                       5.3.6 1              5.3.31    ,
5.3-2                       5.3 6.2              5.3.2-1 5.3 3                       5 3.6 3              5.3.32 l         5.3-3                       5.3.6.3              5.3.5-1 5 3-4                       5.3.6.4              /
          /                           /                    5.4.1.1-1 54-1                     ,.
5.4.15               /
6 1-1                       6.1.3.1              6.1.1-1 6.1-2                       6.1.3.2              6.1.21 1
l l
w____. __

s SSAR Table 1.8 2 Item No. SSAR Subsection No.                                                    FSER Appendix F Item No.
6.2-1                       6.2.6                                                                  /
6.31                       6.3.8.I                                                                 6.2.1.8-1
               /                          /                                                                       6.2.5 1 642                        6 4.7                                                                   6.4.I
: 6. 4-3                     6.4.7                                                                   6.4-2 6.6-1                      6.6.9.I                                                                 6.6-1
               /                          /                                                                       6.6-2
               /                          /                                                                       6.6-3 6.6-2                      6.6.9.2                                                                 /
               /                          /                                                                       6.6-4 7.1-l                       7.1.6                                                                  /
               /                          /                                                                       8.2.3.I-1
               /                          /                                                                       8.2.3.2-1
              /                           /                                                                       8.2.3.3-1 8.2 1                      8.2.5                                                                   8.2.3.4 1 8.2 1                      8.2.5                                                                   8.2.3.5 1 8.2-2                      8.2.5                                                                   /
8.3.I                      8.3.3                                                                   8.2.5.2-1                                        I 8.3 2                       8.3.3                                                                   8.3.2.11
              /                           /                                                                       8.3.2.1-2 832                         8.3.3                                                                   8.3.2.1-3 8.3-2                       8.3.3                                                                   8.3.2.1-4 8 3-2
{
8.3.3                                                                   8.4.1-1 8.3 2                       8.3.3                                                                   8.3.1.2- 1 9.1-!                       9.1.6                                                                   /
9.1-2                       9.1.6                                                                   /
9.1-3                       9.1.6                                                                   /
9.1-4                       9.1.6                                                                   /
9 l-5                       9.1.6                                                                   /
9.1-6                       9.1.6                                                                   /
9.3 1                       9.3.7                                                                   /
9.41                        9.4.12                                                                  /
             /                            /                                                                       9.2.61
              /                           /                                                                       9.2.6-2 9.5-1                       9.5.1.8                                                                 9.5.1-1 9.5-2                       9.5.1.8                                                                 9.5.1.2 9.5-3                        9.5.1.8                                                                 /
9 5-4                        9.5.1.8                                                                 9.5 1-11 955                          9.5.l.8                                                                 /
9.5-6                        9.5 2.5.1                                                               /
9.5-7                        9.5 2.5 2                                                               9.5.2-1 958                          9.5.2.5.3                                                               9.5 2-1 9.5-9                        9.5.4.7                                                                 /
9 5-10                       9.5.4.7                                                                 /
             /                            /                                                                       9.5.1-3
             /                            /                                                                       9.5 1-4
             /                            /                                                                        9.5.1 5 l

e 1
1 SSAR Table 1.8-2 Item No. SSAR Subsection No. FSER Appendix F Item No.
     /                           /                    9.5.1-6
     /                           /                    9.5.1-7
     /                           /                    9.5.1 8
     /                           /                    9.5 1-9
     /                           /                    9.5.1 10
     /                           /                    9.5.1-12
     /                           /                    9.5.1-13
     /                           /                    9.5.1-14
     /                           /                    9.5.1-15
     /                           /                    9.5.1-16
     /                           /                    9.5.1-17
     /                           /                    9.5.1-18
     /                           /                    9.5. 3- 1
    /                            /                    9.5.4-1
    /                            /                    9.5.4-2 10.1-1                       10.1.3              /
10.2 1                       10.2.6               10.2.9-1 10 2-1                       10.2.6               10.2.9-2 10.4-1                       10.4.12-1            10.4-1 1042                         10.4.12-2           /
10 4-3                       10.4.12 3           /                                  i
    /                            /                     10.4.5-1                           l 11.2-1                       11.2.5.I             11.2-4 11.2-2                       11.2.5.2            /
    /                            /                     11.1-1 11.2-3                       11.2.5.3             11.2-1 11.2-4                       11.2.5 4             11.2-2
    /                            /                     11.2-3 11.3-1                       11.3.5.1            /
I1.3-2                       11.3.5.2            /
    /                            /                     11.3-1
    /                            /                     11.3 2 11.4-1                       11.4.6               11.4 1
    /                            /                     11.4-2 11.4.I                       i1.4.6               11.4-3 11.5-1                       1a. 7                11.5-1 11.5-2                    -~1 l'.D               /
11.5-3                     ,l1.5.7               /                                  I 12.I 1                       12.1.3               12.2.1-1 12.2-1                       12.2.3               12.3.1-1
    /                            /                     12.2.3-1 12.3-l                       12.3.5               12.4.2-1 l   12.3-1                        12.3.5               12.4.2-2 l   12.3 2                        12.3.5               12.4.4-1 12.5-1                        12.5.5               12.6-1 13.1-1                        13.1.I               13.1-1 13.2-1                        13.2.I               13.2-1 13 3-1                        13.3.1               13.3-1 r
l

l   SSAR Table 1.8-2 Item No. SSAR Subsection No.                                                                        FSER Appendix F ltem No.
13.3 2                     13.3.1                                                                                      13.3 2
   /                          /                                                                                            13.3 3 13.4-1                     13.4.1                                                                                      13.4 1 13.5.I                     I3.5.I                                                                                      13.5-1.1
   /                          /                                                                                            13.5.2 1
   /                          /                                                                                            13.6.1-1 13 6-l                     13.6.I3.I                                                                                   13.6.2-1 13.6-1                     13.6. I 3. I                                                                                13.6.4-1 I3.6-t                     13.6.I3.I                                                                                   13.6.10-1 13.6 1                     13.6.13.I                                                                                   i3.6.12 1 13.6 1                     13.6.13.1                                                                                   13.6.13-1 13.6 3                     13.6.13.3                                                                                   13.6.6-1 13.6-3                     13.6.13.3                                                                                   13.6.I1 1 I3.6 2                     13.6.I3.2                                                                                   13.6.I3.2 1 I3.6-3                     13.6.I3.3                                                                                   13.6.I3.3-1 14.4 1                      14.4.I                                                                                       14.2.2-1
  /                           /                                                                                             14.2.3 1 14.4a2                      14.4.2                                                                                      14.2.3 2 14.4 3                      14.4.3                                                                                      14.2.3.1-1 14.4-4                      14.4.4                                                                                       14.2.3.2-1
  /                           /                                                                                             14.2.5-1
  /                           /                                                                                             15.3.4-1
  /                           /                                                                                            16.2-1 16.3 1                      16.3.2 -                                                                                  /                          1 17.5 1                      17.5                                                                                         17.1 1 17.5-4                      17.5                                                                                         17.2-1
  /                           /                                                                                            17.4.1 1
  /                           /                                                                                            17.4.2-1 l
  /                           /                                                                                             17.4.5 1 17.5-3                      17.5                                                                                        17.4.7.3-1 17.5 7                      17.5                                                                                        17.4.9-1
  /                           /                                                                                             17.4.9 2 17.5 2                     17.5                                                                                       /
17.5 5                      17.5                                                                                      /
17.5-6                       17.5                                                                                      /
17 5-8                     17.5                                                                                       /
18.2-1                     18.2 6                                                                                     /
18.2-2                      18.2.6                                                                                    /
I8.31                      18.3.1                                                                                     /
I8.5-1                     18.5.4                                                                                        I8.5-2 18.5-1                      18.5 4                                                                                        18.5-3                  l 18.5-2                      18.5.4                ,_
18.5-1 1861                        18 6.1                                                                                        18.6 1 18.7-1                      18.7.1                                                                                     /
1881                        18.8.5                                                                                     /
18.9 1                      18.9.I                                                                                        18.9 1 I
V

s 4 '
SSAR Table 1.8 2 Item No. SSAR Subsection No.           FSER Appendix F ltem No.
I8.9.I                      18 9.I                         18.9-2 18.10-1                     18.10.1                        18.10-1 18.11-1                     18.11.1                       /
Item 19: Doesn't have relevant contents in SSAR.
Item 20 Page number in SS AR         Issue name                    FSER Appendix F Item No 1.9-44                      Issue A40                     20.2-1 1.9-73                      issue 142                     20.3 1 1.9-131                     issue I. A. I.4               20.4 1 1.9-13I                     Issue I. A.2.6(1)              20.4-2 1.9-132                     Issue I. A.4. l(2) & I. A.4.2  20.4-3 1.9-134                     Issue I.C.5                    20.4-4 1.9-134                     Issue I.C.9                    20.4-5 1.9-135                     Issue I.D.3                    20.4-6 1.9-136                     issue 1.F.2                    20 4-7                      ,
1.9-140                     Issue II.F 2                   20.4-8 l
1.9 142                     Issue II.J.3.1                 20.4 9 1.9-142                     Issue II.J 4.1                 20.4 10 1 9-144                     Issue II.K.1(26)               20.4-11 1.9-151                     Issue III. A.3.3               20412
                           /                            Bulletin 80-06                 20.7 1
                           /                            Bulletin 80-15                 20.7-2
                           /                            Bulletins 80-16                20.7-3
                           /                            Bulletin 89-03                 20.7-4
                           /                            Genenc Letter 81 38            20.7-5
                           /-                           Genene Letter 81-39            20.7-6
                           /                            Genenc Letter 83-07            20.7-7
                           /                            Genenc Letter 83-11            20.7-8
                           /                            Genenc Letter 89-07            20.7 9
                           /                            Genenc Letters 89-15 & 93-01   20.7 10

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I I
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1 l
l   NRC FSER OPEN ITEM Revision 1 g
WfM Open item 640.97 (OITS #5851) i Your response to question 640.47 is unacceptable. CDM 3.7, ' Design Reliability Assurance Program /
(DRAP) should be revised to include the same commitments provided in the Tier 1 DRAP for the ABWR or System 80+ oasign. In addition, Tables 3.71 and 3.7-2 should be deleted. Future changes by Westinghouse or a combined license applicant to the probabilistic, deterministic, or other methods for determining risk significance could change the list of risk significant structures, systems, or components (SSC) for the AP600 design. Therefore, it is not appropriate to set forth the list of risk significant SSCs in Tier 1. Also, SSAR Section 16.2 should be moved to Section 17.3. This is the appropriate location for a description of the reliability assurance program.

===Response===
Westinghouse has reviewed the CDM commitments provided by System 80+ for D-RAP. The AP600 CDM material for D-RAP as revised in this response provides similar or greater commitments than is provided by System 80+. The main differences in the CDM material are due to the different approach taken to D RAP in the AP600 SSAR.
l The System 80+ SSAR provides an ' example
* list of the D RAP SSCs and as a result the System 80+
CDM material does not include the list of D-RAP SSCs. Instead System 80+ includes the D-RAP selection process, essentially a Design ITAAC, which is required to finalize the D-RAP list. System 80+
CDM Table 3.3-1, items 1.a.1.b,1.c are provided to finalize the list of D-RAP components.
The AP600 D RAP approach is different. SSAR Table 17.4 3 provides the list of structures, systems and components (SSCs) that are included in the AP600 0-RAP program. This comprehensive and conservative list is agl an ' example *, it is the complete list. It is comprehensive because the AP600 SSAR scope includes items that are treated as interfaces in System 80+. The list is conservative because the risk importance cutoff cnteria are lower than they are for System 80+ and as a result more SSCs are captured. The AP600 SSAR D-RAP list has been included in the CDM material in Table 3.7-
: 1. As a result, it is not necessary to provide ITAACs to establish the D-RAP list of SSCs as System 80+ does in its CDM Table 3.3-1 (items 1.a.1.b.1.c).
There is a COL applicant information item in the AP600 SSAR subsection 17.4.7.3 which requires the COL applicant to identify site specific SSCs for the D-RAP program, it is not necessary or appropriate    i to provide ITAACs in the AP600 plant CDM material to cover COL information items; if such an ITAAC l
is necessary it should be covered by the COL applicant in the site specific ITAACs.
System 80+ has another ITAAC item in Table 3.3-1, item 1.d. that requires documentation that concludes failure modes and effects developed for the D-RAP SSCs considered industry experience           {
and that key assumptions and risk insights considered operations, maintenance, and monitoring             I activities. AP600 CDM Table 3.7, item 1, provides a more comprehensive ITAAC which requires that the estimated reliability of the D RAP SSCs be at least equal to the assumed reliability. Such an I
T westinghouse                                                                              ""
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O NRC FSER OPEN ITEM Revision 1                                                                                                                9 (F
activity goes beyond failure modes and effects and key assumptions / risk insights. It is proposed that the AP600 D RAP CDM material be modified to require that inductry experience including operations, maintenance, and monitoring activities be considered in determining the estimated reliability of the D-RAP SSCs.
The AP600 CDM section 3.7 includes statements similar to the System 80+ D-RAP scope and purpose                                                                           I statements. CDM section 3.7 does not include a D-RAP objectives statement; the section will be revised to add a D-RAP objectives statement.
SSAR Change.                                                                                                                                                              j None ITAAC Chary:
CDM section 3.7 and Table 3.7-3 are revised per the attachments.
l 640.97(RI) 2 i
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1 i
NRC FSER OPEN UEM
:   7 Revision 1 i
Revised CDM Section 3.7 1                                              3.7 Design Reliability Assurance Prograin The Design Reliability Assurance Program (D RAP) is a program that will be performed during the detailed design and equipment specification phase prior to initial fuel load. The D-RAP evaluates and sets priorities for the structures, systems, and components (SSCs) in the design, based on their degree of risk significance. De risk-significant components are listed in Table 3.7-1.
The objective of the D RAP program is to provide reasonable assurance that risk significant SSC's (Table 3.71) are designed such that: (1) assumptionsfrom the risk analysis are utill:ed, (2) SSC's (Table 3.71) when challenged, function in accordance with the assumed reliability, (3) SSC's (Table .
3.71) whose failure results in a reactor trip, function in accordance with the assumed reliability, (4) maintenance actions to achieve the assumed reliability are identified.
: 1. De D-RAP provides reasonable assurance that the design of risk-significant SSCs is consistent l      with their risk analysis assumptions.
Inspections, Tests, Analyses, and Acceptance Criteria l
Table 3.7 3 specifies the inspections, tests, analyses, and associated acceptance criteria for the D-RAP.
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l 640.97(RI) 3
)                                                 T Westingtmuse l___m.____ .___.__ _ _ _ _ _ _ _ _ _ _ _ _                              _      __      _   _ _ _ _ _ ___ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _                    _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _

\
NRC FSER OPEN REM Revision 1                                                                                             f" EE.g Revised CD.%f Table 3.7 3 Table 3.7 3 Inspections, Tests, Analyses and Acceptance Criteria Design Commitment                 Inspections, Tests, Analyses             Acceptance Criteria
: 1. The D-RAP provides              Inspection will be performed for  A report exists and concludes that reasonable assurance that the       the existence of a report which   the estimated reliability of each as-design of risk significant SSCs     establishes the estimated         built component identified in is consistent with their risk       reliability of as-built risk-     Table 3.7-1 is at least equal to the analysis assumptions.               significant SSCs.                 assumed reliability and that industry experience including operations, maintenance, and monitoring activities were assessed in estimating the reliability of these SSCs.
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640.97(RI)-4 W-Westinghouse l
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l NRC FSER OPEN ITEM l
Revision 1                                                                                        P^
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Open item 640.186F (OITS #6640)
Your responses to RAI 640.176 and OITS #6590, dated February 27,1998, are unacceptable. You did not provide a Tier 1 design commitment and ITAAC for the safety-related coatings that will be applied to the internal and external surfaces of the passive containment cooling system. Also, the PXS ITAAC must venfy the safety related coatings that will be applied to the areas close to the recirculation screens, e.g. screen plates, and the size of the screen plates. These are important assumptions in your debris transport analysis.

===Response===
The AP600 ITAACs already provide substantial venfication in the areas of concern:
A water distribution test is performed in an ITAAC (CDM 2.2.2, PCS).
An hspection is peribemed to writy that an borganic zinc conting is used on the outside surface of the contehment vessel (CDM 2.2.2, PCS).
The density of the nonsafety-related coatings used inside containment is covered by an ITAAC (CDM 2.2.3, PXS).
The containment recirculation screens are covered by two ITAACs (CDM 2.2.3, PXS); one venfying the screen surface area and the other verifying the size of the protective plates located above the screens.
The insulation used on lines that may be LOCAs is covered by an ITAAC (CDM 2.2.3, PXS).
The AP600 SSAR provides additional details with respect to where safety-related coatings are used, the type of coating used and the applicable quality assurance requirements, including codes and standards.
The evolutionary plants CDMs do not provide any ITAACs on coatings, insulation or containment recirculation screens.
l Two addRionalITAACs are wit be added. One is k hopect the heide surtece of the containment
                                                    ; vessel k writy that R is oceted with inorganic zinc, A second hapection is provided k wrify that
: contengs used h close proxim#y lo the contalrynent rech:uintion screens are quellfled b remah i afteded dLaing post accident condRions.
                                                     ; None that COM Table 2.2.2-3 them 7.k.E, is revised k ciearty stehe where the borganic zhc is required
                                                                                                                                                                         )
{ on the outside ashoe of he coninhment wsoel Also note that h CDM hm 2.2.2.7.c and its acent*ted }lem h Tabie 2.2.2-3, inom 7.c, the words "contahment sheH" wit be revised to " containment      ;
l vessel" b he consistent.                                                                                          l I                                                                                                                                                                        '
f T Westinghouse 640.186(RI)F-1 t

NRC FSER OPEN REM Revision 1                                                                              ==
                                                                                               ~
                                                                                                    =a 3  ,
SSAR Change:
None ITAAC Change:
l Revise CDM secdon 2.2.2 and Table 2.2.2 3, to add an inspecdon (Item 7.b) of the coadng used on the
  ; inside swface of the contahment vessel. Revise COM Tabbe 2.2.3-4, to add an bspecdon of coadngs I
used in close proximity to the containment mcin:uladon screens.
640.186(RI)F-2

d NRC FSER OPEN ITEM Revision 1
                                                                                                                                                                                                    ]
Revloed COM Section 2.2.2,18em 7.b
: 7. The PCS provides the following safety related functions:
a) The PCS provides the delivery of water to the outside of the containment vessel.
I     b) The PCS provides wetting of the inskie andoutside surfaces of the containment vessel.
l     c) The PCS provides air flow over the outside of the containment wsselby a natural circulation air flow path from the air inlets to the discharge structure.
d) The PCS provides drainage of the excess water from the outside of the containment vessel through the two upper annulus drains.
e) The PCS provides a flow path for long-term makeup to the passive containment cooling water storage tank (PCCWST).
f) The PCS provides for long-term makeup from the PCCWST to the spent fuel pool.
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640.186(RI)F-3 l        T Westinghouse

l NRC FSER OPEN ITEM Revision 1 jiE =j" l
t Revised COM Table 2.2.2-3, item 7.b l
Table 2.2.2 3 (cont.)
Inspections. Tests Analyses, and Acceptance Criteria Design Comtaltment                Inspections, Tests, Analyses          Acceptance Criteria 7.b) The PCS provides wetting        i) Testing will be performed to    i) A report exists and concludes of the inside and outside surfaces l
of the containment sessel.
measure the wetted surface of the containment vessel from either of that with water in the PCCWST at the following levels, water
                                                                                                                                                  )
l the two parallel flow paths to the delivery to the containment shell                              i containment sessel.                provides coverage measured at the spring line that is equal to or greater than the corresponding coserage used to calculate peak containment pressure in the safety analysis.
23.75 0.25 ft above the lowest standpipe 20.65 2 0.25 ft above the lowest standpipe 13.55 2 0.25 ft above the lowest standpipe ii) Inspection of the containment  ii) A report exists and concludes                               ;
vessel exterior coating will be    that the containment vessel                                    {
conducted.                         exterior surface is coated with an inorganic zine coating above elevation 13S' 3".
I iii) Inspection of the             li) A report exists and h                                       containment vesselinterior         concludes that the containment l                                       coating will be conducted.          vesselinterior surface is coated with an inorganic zine coating                                 i l       ,
above 7'above the operating
        ;                                                                          deck.
l 640.186(R1)F 4 W Westinghouse
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N9C FSER OPE N ITEM Revision 1                                                                                                                                                                                ?    ~45 i
                                                                                                                                                                                                       . e Table 2.2.2-3 (cont.)
Inspections, Tests Analyses, and Acceptance Criteria 7.c) The PCS provides air flow                       Inspections of the air flow path                                                                         Flow paths exist at each of the over the outside of the                             segments will be performed.                                                                               following locations:
l  containment ressel by a natural circulation air flow path from the                                                                                                                            - Air inlets air inkts to the discharge
                                                                                                                                                                           - Base of the outer annulus sinacture.
                                                                                                                                                                           - Base of the inner annulus
                                                                                                                                                                           - Discharge structure W westinghouse                                                                                                                                                                   m.m p s

4 NRC FSER OPEN REM Revision 1                                                                                                                                                                                                                   Eg i
Revised CDM Table 2.2.3-4, item 8.c
                                                                                                                                                                                                                                                                        =
Table 2.2.3-4 (cont.)
Inspections, Tests Analyses, and Acceptance Criteria Design Commitment            Inspections, Tests, Analyses                                                                                         Acceptance Criteria 8.c) The PXS provides RCS                                  xiii) Inspections willbe                                                                                       xiii) A report exists and makeup, boration, and safety                               conducted of the materials used                                                                                concludes that ti,ese surfaces are injection during design basis                              in the vicinity of the                                                                                         stainless steel or that coatings events.                                                     containment recirculation                                                                                      used on +=se surfaces are screens or analysis, type tests,                                                                               qualified to remain attached to or a combination of analysis                                                                                   these surfaces during design basis and type tests will be performed                                                                               events.
on coatings used on surfaces in the vicinity of the containment recirculation screens. In the vicinity of the containment recirculation screens includes surfaces located above the bottom of the recirculation screens up to and including the bottom surface of the plate discussed in CDM Table 2.2.3 4, item 8.c.vii, out to 10 foot in front and 10 foot to the side of the screen face.
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640,186(RI)F-6 i
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t________________                                                                                   _

NRC FSER OPEN ITEM i "EZ g
Open item OITS #6787 The staff has compared the EO inside containment temperature test envelope, Figure 3D.5-8 of the AP600 SSAR, with the temperature profiles developed in support of Appendix D. " Equipment Survivability," to the AP600 PRA. The staff disagrees with Westinghouse that the EO test envelope bounds the Equipment Survivability environment. Therefore, Westinghouse's contention that the EO ITAAC insufficient to address Equipment Survivability is invalid. The determination of whether or not a particular piece of equipment will survive the severe accident environment defined by Westinghouse in Appendix D to the PRA can only be made at the time of procurement and installation. Therefore, an ITAAC is necessary to make this determination.

===Response===
The AP600 requires very little electrical or mechanical equipment to operate during a severe accident.
More equipment is required in the early time frames of a severe accident (time frames 0 and 1 as defined in PRA Appendix D) than in the later time frames. The envimomental conditions for these eariy time frames (0 and 1) are bounded by DBA harsh envimoments and the associated 1E equipment qualification. In the later time frames (2 and 3) the envimomental conditions can exceed the DBA conditions in some respects. However, in these time frames, the only equipment required that is located inside containment is instrumentation for the RCS pressure, SG wide range level, containment pressure, and containment hydrogen concentration. In addition, physical separation within the containment minimize the chance that all of the sensors of a given function will see temperatures above their DBA qualificaiton limits.
AP600 PRA Appendix D provides an assessment of the ability of equipment utilized to mitigate severe accidents to perform during severe accident envimomental conditions. This equipment is safety-related and qualified for the harsh envimoment applicable to design basis accidents. The assessment performed in Appendix D together with previous testing (EPRI report NP-4354), provides reasonable assurance that this equipment can withstand the envimomental conditions that would exist before, during, and following a severe accident without loss of its severe accident function, for the timo required to perform the severe accident function. The EPRI report showed that showed that equipment qualified for DBAs is expected to function during severe accidents.
In order to provide additional assurance that this equipment can perform its severe accident functions, a commitment will be added to tht, PRA requiring '.he Combined License applicant to perform an assessment of the ability of the as built equipment to perform during severe accident hydrogen bums.
This assessment will be performed utilizing the Environment Enveloping method or the Test Based Thermal Analysis method discussed in EPRI NP 4354.                                                                    .
1 6787-1 m
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l      -
1 NRC FSER OPEN ITEM
                                                                        .d'.=  *i2 2
SSAR Change:
None l
l l        PRA Change:
Revised PRA section 59.10.6 and PRA Appendix D.9 are attached.
ITAAC Change:
None.
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I 6787-2 W    - weineouse

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NRC FSER OPEN REM f    =E
                                                                                                                                                                        ?
_     t Revision to PRA Appendix 0.9 D.9     Conclusions of Equipment Survivability Assesment a 1st paragraph unchanged >>
AP600 provides reasonable assurance that equipment, both electrical and mechanical, used to mitigate the consequences of severe accidents and achieve a controlled, stable state can perform over the time span for which they are needed. In ortier to provido add /lionat assurance that this equpment can perfonn its sente accident functions, the Combined Lloense applicant willperibem an assessment of the as-built equ& ment to pertbem duning severe accident hydnogen bums, The assessment will be peribmnd utillibg the Environment Enveloping method or the Test Based Thermal Analysis method $mmand h EPRI NP-4354 (rekt to PRA section 59.f 0.6). Containment structural integrity is discussed in Chapter 42.
6787' w weenc = .

NRC FSER OPEN ITEM a:-   ==
                                                                                                                                                                                                 =      s Revision to PRA Section 59.t0.6 l
59.10.6     Combined Ucense Information The Combined License applicant tellerencing the AP600 certt6ed design wfIlsssess the as-built equpment used to mitigate sente accidents to provide additionalassurance that this equipment can peribem Ms sewre accident tiunctions durbg sente accident envimomental carninl00s. The Combined License applicant willassess the as-built equpment to perfonn during sewre accident hydrogen barns, utfitting the Environment Enwloping method or the Test Based Thermal Analysis method discussed in EPRI NP-43S4.
6787-4 W westinghouse

l NRC FSER OPEN ITEM a::
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Open item OITS #6794 ( Per Telecon with NRC staff on 5/1/98 (Pella))
CDM Section 2.2.3 page 2.2.3-2, item 9a.
i The design commitment needs to be changed to be consistent with the design commitment in item 9a of Table 2.2.3-4.

===Response===
j l                                                                         The design commitment will be changed to be consistent with the design commitment in item 9a of Table 2.2.3-4.
SSAR Change:
None i
ITAAC Change:
Attached is revised CDM section 2.2.3, item 9.a.                                                    l I
i T Westinghouse

NRC FSER OPEN ITEM Revised CDM Secdon 2.2.4 liem 9.a.
: 9. The PXS has the following features:
l     a) The PXS provides a function to coolthe outside of the reactor wsseldutt'g a sewie accident b) The accumulator discharge check valves (PXS PL-V028A/B and V029A/B) are of a different check valve type than the CMT discharge check valves (PXS-PL-V016A/B and V017A/B).
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l M2 T Westinghouse i
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l NRC FSER OPEN ITEM
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Open item OITS #6797 Per telecon with staff on 5/1/98 (Snodderty)                              .
Section 2.3.9 Containment Hydrogen Control System Table 2.3.9-3, Item 4.b needs to be updated to verify that four PARS (not just two) are provided inside containment and the locations of the two additional PARS are in the IRWST vent and the CVS compartment outlet.

===Response===
CDM Table 2.3.9 3 will be revised to add the other two PARS.
l SSAR Change:
None ITAAC Change:
Attached is revised CDM Table 2.3.9-3, item 4.b.
l l                                                                                                                                                  8
                                                             ,                                                                              6797-1

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NRC FSER OPEN REM Em   =a
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2:
Revisdd COM Table 2.3.9 3, item 4.b Table 2.3.9 3 Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment                 inspections, Tests, Analyses          Acceptance Criteria 4.b) He VLS provides PAR              i) Inspection for the existence  i) Two PAR devices (VLS.MY.
devices for control of the            offour PAR devices inside        E01A/B) are provided inside containment hydrogen                 containment will be performed. containment within the upper concentration during and                                               compartment between elevations following a design basis accident.
150 and 175 ft and with PAR centerline greater than 10 ft from the containment shell. One PAR device (VLS.MY.E02) is located in a IRWST vent. One PAR device (VISMY E03) is located in the CVS room (room number 111209).
ii) Type tests, analyses, or a   ii) A report exists and concludes combination of type tests and    that the hydrogen depletion rate analyses will be performed on    for each installed PAR (VLS MY.
PAR devices VLS MY E01A/B.       E01A/B) is greater than or equal to I scfm of hydrogen at a prevailing concentration of 3 volume percent for a test conducted at atmospheric pressure +2 psi and an ambient temperature of 120.
T westinghouse                                                                                       s.2

NRC FSER OPEN ITEM t.= sn =cg
: r.         s Open item OITS #6798 Per telecon with NRC staff on 5/1/98 (Snodderly)
Section 2.2.1 Containment System Table 2.2.13, item 7.ii. The acceptance criteria for the response tinies is not consistent with Table 2.2.4-4, item 11.b.ii for valves SGS-PL-V040A/B and SGS PL V057A/B.

===Response===
CDM Table 2.2.13, item 7.il requires the response times for containment isolation valves (except for the containment purge isolation valves) to be less than 60 seconds. CDM Table 2.2.4-4, item 11.b.ii, requires the response times for SGS valves SGS PL V040A/B and SGS-PL V057A/B to be less than 5 seconds. These times are not inconsistent; CDM Table 2.2.4-4 contains the more restrictive times and is controlling.
However, in order to prevent confusion, CDM Table 2.2.1-3, item 7.ii, will be revised to say that these SGS valve response times are covered by CDM Table 2.2.4-4. item 11.b.ii.
SSAR Change:
None.
ITAAC Change:
The revised CDM Table 2.2.13, item 7.ii is attached.
W westinghouse                                                                                 "*

NRC FSER OPEN REM
                                                                                                                                                               = ==
                                                                                                                                                                       =
Revised COM Table 2.2.13, Item 7.R Table 2.2.13 (cont.)
Inspections, Tests, Analyses, and Acceptance Criteria Design Commitment                  Inspections, Tests, Analyses          Acceptance Criteria
: 7. The CNS provides the safety-       i) A containment integrated leak   i) The leakage rate from related function of containment       rate test will be performed.       containment for the integrated isolation for containment                                                leak rate test is less than L,.
boundary integrity and provides a barrier against the release of        li) Testing will be performed to   ii) The containment purge fission products to the               demonstrate that remotely          isolation valves close within atmosphere.                           operated containment isolation     20 seconds, SGS valves valves close within the required   SGS-PLV040A/B and response times.                    SGS PbVOS7A/B are covered in CDM Table 2.2.4-4 (item I!.b.il) and all other containment isolation valves close within 60 seconds upon receipt of an actuation signal.
6798 2
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NRC FSER OPEN ITEM y- 5~
Open item OITS #6805 Per telecon with NRC staff on 4/30/98 (Walker, Wilson)
Section 1.1 Definitions a) Add a definition of the environmental conditions to the definition of Qualified for Harsh Environment.
b) Delete the definition for Safety Related as this term is already defined in the industry and is not required to be repeated.
c) is the definition for Cable required? If knowledgeable people in the electrical field have a common understanding of this meaning, then the definition is not required.

===Response===
a) A sentence will be added to the CDM section 1.1 definition of Qualified for Harsh Environment.
b) The defination of Safety-Related will be deleted from CDM section 1.1.
c) Tha definition for Cable is required to differentiate between electrical cables and fiber-optic cables.
This defiriition needs to be retained.
SSAR Change:
None.
ITAAC Change:
In CDM section 1.1, add sentence on enviiunmental conditions to the definition of Qualified for Harsh Environment and delete definition of Safety-Related.
l T Westinghouse

NRC FSER OPEN ITEM pc w y
Revised CDM Section 1.1 1.0 Introduction 1.1 Definitions The following definitions apply to terms used in the design descriptions and associated inspections, tests, analyses, and acceptance criteria (ITAAC).
Acceptance Criteria means the perfoc.ance, physical condition, or analysis result for a structure, system, or component that demonstrates that the design commitment is met.
Analysis means a calculation, mathematical computation, or engineering or technical evaluation.
Engineering or technical evaluations could include, but are not limited to, comparisons with operating experience or design of similar structures, systems, or components.
As built means the physical propenies of a structure, system, or component following the completion of its installation or constmetion activities at its final location at the plant site.
Cable means an electtical conductor with or without insuhtion, or a combination of insulated electrical conductors.
Design Commitment means that portion of the design description that is verified by frAAC.
Design Description means that portion of the design that is certified.
Division (for electrical systems or electrical equipment) is the designation applied to a given safety.
related system or set of components that is physically, electrically, and functionally independent from other redundant sets of components.
Functional Arrangement means the physical arrangement of structures, systems, and components to                                                                                                   i provide the service for which the structure or system is intended, and which is described in the design description.
Functional Capability (of a line) means the line maintains the ability to transfer fluid through the line                                                                                         l while providing a pressure boundary, during and after a design basis event.                                                                                                                       I Heavy Load means a load whose weight is greater than the combined weight of a single spent fuel l   assembly and its handling device.
m2 W westinghouse
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NRC FSER OPEN ITEM l
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l Inspect or Inspection means visual observations, physical examinations, or reviews of records based                               '
on visual observation or physical examination that compare the structure, system, or component condition to one or more design commitments. Examples include walkdowns, configuration checks, measurements of dimensions, or nondestructive examinations.
Inspect for Retrievability of a display means to visually observe that the specified information appears on a monitor when summoned by the operator.
L, is the mr imum allowable containment leakage as defined in 10 CFR 50 Appendix J.
Nominal means a dimension or size used to designate a name whereby such dimension or size may vary from the actual, or as measured, dimension or size, according to industry standards.
Qualified for Harsh Environment means that equipment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of its safety function, for the time required to perform the safety function. These environmental conditions include applicable time-dependent temperature and pressure profiles, humidity, chemical effects, radiation, aging, submergence, and their synergistic effects which have a significant effect on equipment performance. Equipment identified in the Design Description as being Qualified for Harsh Environment includes the:
: a. equipment itself
: b. sensors, switches and lubricants that are an integral part of the equipment
: c. electrical components connected to the equipment (wiring, cabling and termmonons)
Items b and c are Qualified for Harsh Environment only when they are necessary to support operation of the equipment to meet its safety-related function listed in the Design Description table and to the extent such equipment is located in a harsh environment during or following a design basis accident.
Safe Shutdown refers to a plant condition where the reactor is subcritical with adequate coolant inventory and core cooling, with a coolant temperature less than 420*F.
l Edty-rit:d i; : dzi'i= den :pp!!cd :: i::m; =!!:d upcn :: = min fu='! nd dud:g er fc!!c" sing l a &dgn hi :=: :: pretik : :d y =!:::d functica Sd y =!::ed &c app!!= 0 dcamentatten l and serie:: cffe::!:; : :d:y rd::d i::=
l                                              Sensor means a transmitter, resistance temperature detector, thermocouple or other transducer, plus associated cables, connectors, preamplifiers, reference junction boxes, or other signal processing equipment that is located in the immediate proximity of the sensor and subject to the same environmental conditions.
6805-3 W   -
westinghouse 1

o NRC FSER OPEN REM Test means the actuation, operation. or establishment of specified conditions to evaluate the performance or integrity of as-built structures, systems, or components, unless explicitly stated otherwise.
Transfer Open (Closed) means to move from a closed (open) position to an open (closed) position.
                                                                                                         )
Type Test means a test on one or more sample components of the same type and manufacturer to           l qualify other components of the same type and manufacturer. A type test is not necessarily a test of the as-built structures, systems, or components.
UA of a heat exchanger means the product of the heat transfer coefficient and the surface area.
i Ml

NRC FSER OPEN ITEM g::an=a Open item OITS #6807 Per NRC telecon with NRC staff on 5/8/98 (Throm)
Section 2.2.2 Passive Containment Cooling System a) Design commitment 7.c should be containment ' vessel' not "shell" for clarification. Same change is needed in Table 2.2.2-3, item 7.c. The use of
* vessel
* not "shell* for desenbing the containment needs to be consistent throughout Tier 1.
b) Add the word vessel after containment in 7.b.ii in the ITA and AC.
c) Add an ITAAC similar to 7.b.il that inspects the inside of the containment vessel to verify the surface is coated with an inorganic zinc coating.

===Response===
Each of these items has been addressed in the revision 1 response to Open item 640.186 (OITS
  #6640)
SSAR Change:
None.
ITAAC Change:
None.
T W85tingh0088 i
                                                                                                                     - -- - - -- - ----- --- L

a NRC FSER OPEN ITEM E
E m .=
                                                                                                                                                                     =-
Open item OITS #6809 Per Email and telecon with NRC staff on 5/7/98 (Snodderly/ Wilson)
Section 2.1.2 RCS Sparger Table 2.1.2-4 of the CDM adequately verifies the flow area through the holes in each ADS sparger and the elevation of the sparger. But the design commitment that the IRWST has been designed to accommodate the hydrodynamic loads associated with depressurization of the ADS has apparently been omitted. Either the specific location of the spargers relative to the intemal columns and the tank walls or the existence of a report that concludes that the location of the spargers relative to the IRWST intemal columns and tank walls supports that assumed in the design loadings for tiie IRWST is needed as acceptance criteria.

===Response===
!                                                The IRWST is part of the containment structure and as a result is subject to CDM Table 3.3-6, item l
2.a.ii. This item requires a report to reconcile deviations of the as built structures and conclude that the as-built structures will withstand the design basis loads. Deviations in the as-built location of the sparger will be reconciled with consideration for the hydrodynamic loads associated with depressurization via the ADS. No revisions to the CDM are required.
SSAR Change:
None.
ITAAC Change:
None.
l l
l l
T Westinghouse 1

J NRC FSER OPEN ITEM Open item OITS #6828, Per Email from NRC on 5/15/98 (J. Wilson)
SRXB input to AP600 ITAAC SER (4) In item 4 of Design Description in Section 2.2.3, Passive Core Cooling System, labeling of Figures 2.2.3-1 and 2.2.3-2 should be revised to be consistent with the labels for Figures 2.2.3-1 (Sheets 1 and 2).

===Response===
Agreed, item 4.b will be revised to say Figure 2.2.3-1.
                                                                                                                                                                                                                                                            ?
SSAR Change:
None ITAAC Change:
Attached is the revision to CDM section 2.2.3, item 4.b and the corresponding words in CDM Table 2.2.3-4, item 4.b.
W Westinghouse 1

4 NRC FSER OPEN ITEM g   =5 i
Revision to COM Sec60n 2.2.3, Item 4 2.2.3 Passive Core Cooling System Design Description The passive core cooling system (PXS) provides emergency core cooling during design basis events.
l ' The PXS is as shown in Figure 2.2.3-1 and the component locations of the PXS are as shown in Table 2.2.3-5.
: 1.         The functional arrangement of ti,s PXS is as described in the Design Description of this Section 2.2.3.
: 2.          a) The components identified in Table 2.2.3-1 as ASME Code Section lli are designed and constructed in accordance with ASME Code Section lit requirements.
b) The piping identified in Table 2.2.3-2 as ASME Code Section 111 is designed and constructed in accordance with ASME Code Section ill requirements.
: 3.            a) Pressure boundary welds in components identified in Table 2.2.3-1 as ASME Code Section ill meet ASME Code Section ill requirements.
b) Pressure boundary welds in piping identified in Table 2.2.3 2 as ASME Code Section ill meet ASME Code Section lll requirements.
: 4.             a) The components identified in Figure 2.2.3-1 as ASME Code Section til retain their pressure boundary integrity at their design pressure.
1                    b) The piping identified in Figure 2.2.31 as ASME Code Section lit retains its pressure boundary integrity at its design pressure.
: 5.             a) The seismic Category I equipment identified in Table 2.2.3-1 can withstand seismic design                                                                                         4 basis loads without loss of safety function.                                                                                                                                    [
b) Each of the lines identified in Table 2.2.34 for which functional capability is required is I                             designed to withstand combined normal and seismic design basis loads without a loss of its                                                                                      g functional capability.                                                                                                                                                          l l
6828-2 l                                                                                                                                                                                                              ,
\                                                                                                                                                                                                             1

O NRC FSER OPEN ITEM g                =:=
                                                                                                                                        =-                   g Revised CDM TaNe 2.2.3-4, item 4.b Table 2.2.3-4 (cont.)
Inspections, Tests, A:ulyses, and Acceptance Criteria Design CommMment                inspections, Tests, Analyses          Acceptance Criteria 4.b) The piping identified in        A hydrostatic test will be      A report exists and concludes l  Figure 2.2.3-7 as ASME Code          performed on the piping         that the results of the Section Ill retains its pressure     required by the ASME Code       hydrostatic test of the piping boundary integrity at its design     Section ill to be               identified in Table 2.2.3-2 as pressure.                            hydrostatically tested.         ASME Code Section 111 conform with the requirements of the ASME Code Section Ill.
l l
l 8
T Westinghouse
- _ _ _ _ _                    _                                                                                                                                                           a

f i
               ;8 Comparison of COL action items between SSAR and FSER SSAR Table 1.8-2 Item No. SSAR Subsection No.                                                                                 FSER Appendix F Item No.
1.1-1                     1.1.7                                                                                              /
2.1-1                     2.1.1                                                                                               2.1-1 2 1-1                     2.1.1                                                                                               2.1.1-1 2.1-1                     2.1.1                                                                                               2.1.2- 1 2.1-1                     2.1.1                                                                                               2.1.31 2.2-1                     2.2.1                                                                                               2.2-1                i             9    r 8 2.2-1                     2.2.1
* 2.2-1                     2.2.1 2.2.1-1 2.2.21
                                                                                                                                                                                                                                                        *       {d g A E
Q 2.2-l                     2.2.I                                                                                               2.2.3. I                         u   g       $
2.3 1                     2.3.6.1                                                                                             2.3.1 1                              r       &
2.3-2 2.3-3 2.3.6.2 2.3.6.3 2.3.2-1 2.3.31 n-  (       I 2.3-4                     2.3.6.4                                                                                             /                                            y 2.3-5                      2.3.6.5                                                                                              2.3.5-1                                     0
                                                                                                                                                                                                                                                                           ~
2.4-1                      2.4.1.1                                                                                              2.4.1-1 2.4-2                      2.4.1.2                                                                                              2.4.21             p                   ,
p           p 2.4-2                      2.4.1.2                                                                                              2.4.3-1            0    }y                J 2.4-2                      2.4.1.2                                                                                              2.4.4-1               g h glY 2.4-2 2.4 2 2.4.1.2 2.4.1.2 2.4.5-1 2.4.61                7 g
                                                                                                                                                                                                                                                     %,j
                                                                                                                                                                                                                                                                   ,)
hq
                                                                                               /
                                                                                               /
                                                                                                                          /
                                                                                                                          /
2.4.71 2.4.8-1 gf            h F
                                                                                               /                          /
e      3 k
fav 2.4.9-1               M 2.4-2                      2.4.1.2                                                                                              2.4.10-1              4 f
                                                                                                                                                                                                                                                                   "     D i
2.4 3                      2.4.1.3                                                                                              2.4.11-1 2.4-4                      2.4.1.4                                                                                              2.4.12-1                                 ,-
2.4 5                      2.4.1.5                                                                                              2.4.13-1 2.4-6                      2.4.1.6                                                                                              2.4.14-1 2.5-1                      2.5.I                                                                                                2.5.1-1 2.5-2                      2.5.2.I                                                                                              2.5.2-1
                                                                                               /                          /                                                                                                    2.5.2 2 2.5-3                      2.5.3                                                                                                2.5.3-1 2.5-4                      2.5.4.6.I                                                                                            2.5 4.1-1
                                                                                               /                          /                                                                                                    2.5 4.1-2
                                                                                                                          /
l
                                                                                               /                                                                                                                               2.5.4.2 1                                         i' 2.5-5                      2.5.4.6.2                                                                                            2.5.4.2-2 2.5-6                      2.5 4.6.3                                                                                            2.54.3-1 2.5-6                      2.5.4.6.3                                                                                            2.5 4.3 2 2.5 7                      2.5.4.6.4                                                                                            2.5.4.4 1                                         !
2.5-8                      2.5.4.6.5                                                                                             2.5.4.5-1                                        !
2.5 9                      2.5.4.6.6                                                                                             2.5.4.6 1
                                                                                               /                          /                                                                                                    2.5.4.7 1                                      ,
2.5 10                     2.5.4 6.7                                                                                             2.5.4.7-2 2.51l'                     2.5.4.6.10                                                                                            2.5.4.10 1 2.5 12                     2.5.4.6.1I                                                                                            2.5.4. I l-1 2.5. I 3                   2.5.5                                                                                                 2.5.5-1 2.5-14                     2.5.6                                                                                                 2.5.6 1 I

   +
SS AR Table 1.8-2 Item No. SSAk Subsection No.                                                                          FSER Appendix F ltem No.
3.3-1                      3.3.3                                                                                       /
                /                          /                                                                                            3.3.2.2-1 3.4-1                    3.4.3                                                                                       /
                /                          /                                                                                             3.4.2-1
               /                           /                                                                                             3.4.2-2 3.5 1                      3.5.4                                                                                        /                                                                                  <
               /                           /                                                                                            3.5.1.3-1
               /                           /                                                                                             3.5.1.3-2
               /                           /                                                                                             3.5.1.3-3
               /                           /                                                                                             3.5.1.3-4 3.6-1                      3.6.4.1                                                                                      /
3.6-2                      3.6.4.2                                                                                       3.6.3.4-1 3.7 1                      3.7.5.I                                                                                       3.7.2. I 3-1
               /                           /                                                                                             3.7.2.16-1 3.7-2                      3.7.5.2                                                                                       3.7.4-1 3.7-2                       3.7.5.2                                                                                       3.7.4-2 3.7-3                      3.7.5.3                                                                                       /
3.7-4                      3.7.5.4                                                                                       /
3.8-1                       3.8.6.1                                                                                        3.8.2-1
               /                           /                                                                                              3.8.2.4-1 3.8-2                       3.8.6.2                                                                                        3.8.4.4-1 3.8-3                      3.8.6.3                                                                                       /
3.9.I                       3.9.8.I                                                                                       /
3.9-2                      3.9.8.2                                                                                        3.9.3.1-1                                                                        l 3.9-3                       3.9.8.3                                                                                       /                                                                                 l 3.9-4                       3.9.8.4                                                                                       /
3.9-5                       3.9.8.5                                                                                       /
3.9-6                       3.9 8.6                                                                                       /
3.10-1                     3.10.6                                                                                         3.10-1 3 11-1                      3.11.5                                                                                        /
4.2 1                       4.2.5                                                                                         4.2.8-1 4.31                        4.3.4                                                                                         4.2.8 1 4.3-2                       4.3.4                                                                                         /
4.4-1                       4.4.7                                                                                         4.2.8-1 52-1                        5.2.6.I                                                                                        5.2.1.11                                                                         j 5.2 1                       5.2.6.1                                                                                        5.2.1.1-2 522                         5.2.6.2                                                                                        5.2.4-1
               /                           /                                                                                               5.2 4-2 5.3-1                       5.3.6.1                                                                                        5.3.3-1 5.3 2                       5.3.6.2                                                                                        5.3 2-1 5.3 3                       5.3.6.3                                                                                         5.3.3 2 5.3 3                       5.3.6.3                                                                                         5.3.51 l              5.3-4                       5.3.6.4                                                                                        /
               /                           /                                                                                               $ 4.1.1 1 54-1                        5.4.15                                                                                         /
61-1                        6.1.3.1                                                                                        6.1.1 1 6 1-2                       6.1.3.2                                                                                        6.1.2-1 l
b L    - - - _ -                                                   - _ - -                               - _ _ - - - _ _ _ - - -                                 _ - _ - - _ - _ _ - - _ - - - - - _ - - _ _ _ _ - _ - - _ -

(.
e SSAR Table 1.8-2 Item No.      SSAR Subsection No. FSER Appendix F Item No.
i 6.2 1                          6.2.6               /
6.3-1                         6.3.8.1              6.2.1.8-1 l                          /                             /                    6.2.5-1 64-2                          6.4.7                6.4-1 6.4-3                         6.4.7                6.4-2 6.6-1                         6.6.9.I              6.6-1
                           /                             /                    6.6-2
                           /                             /                    6.6-3 66-2                          6.6.9.2              /
                          /                              /                    6.4-4 7.1.I                          7.1.6               /
                           /                             /                    8.2.3.1-1
                          /                              /                    8.2.3.2-1
                          /                              /                    8.2.3.3-1 l                          82-1                          8.2.5                8.2.3.4-1 8.2-1                          8.2.5                8.2.3.5-1 8.2-2                          8.2.5                /
8.3-1                          8.3.3                8.2.5.2-1
!                         8.3-2                          8.3.3                8.3.2.1-1                                        {
                          /                              /                    8.3.2.1 2 8.3-2                          8.3.3                8.3.2.1-3 8.3-2                          8.3.3                8.3.2.1-4 8.3-2                          8.3.3                8.4.1 1 l                         8.3-2                          8.3.3                8.3.1.2- 1 9.l-1                          9.1.6                /
9.1-2                          9.1.6                /
9.1-3                          9.1.6                /
9.1-4                          9.l.6                /
9.1 5                          9.1.6                /
9.1-6                          9.1.6                /                                                l 9.3-!                          9.3.7                /
: 9. 4- 1                        9.4.12               /
                         /                               /                    9.2.6-1
                         /                               /                    9.2.6-2 9.5-1                           9.5.1.8              9.5.1-1 9.5-2                           9.5.1.8              9.5.1.2 9.5-3                           9.5.1.8              /
9.5-4                           9.5.1.8              9.5.1 11 9.5-5                           9.5.1.8              /
l 9.5 6                           9.5.2.5.1            /
95-7                            9.5.2.5 2            9.5.2-1 I                        9.5-8                           9.5.2.5.3            9.5.2-1 9.5-9                           9.5 4.7              /
9.5-10                          9.5.4.7              /
                         /                               /                    9.5.1-3
                         /                               /                    9.5.1-4
                         /                               /                    9.5.1-5 3

e SSAR Table 1.8-2 Item No. SSAR Subsection No. FSER Appendix F Item No.
       /                         /                       9.5.1-6
       /                         /                       9.5.1-7
       /                         /                       9.5.1-8
      /                          /                       9.5.1-9
      /                          /                       9.5.1-10
      /                          /                       9.5.1-12
      /                          /                       9.5.1-13
      /                          /                       9.5.1-14
      /                          /                       9.5.1 15
      /                          /                       9.5.1-16
      /                          /                       9.5.1 17
      /                          /                       9.5.1-18
      /                          /                       9.5.3-1
      /                          /                       9.5 4-1
      /                          /                       9.5.4-2 10.1-1                     10.1.3                 /
10.2.I                     10.2.6                  10.2.9.I 10.2-1                     10.2.6                  10.2.9-2 10.4-1                     10.4.12-1               10.4-1 10.4-2                     10.4.12-2              /
10 4-3                     10.4.12-3              /
     /                           /                        10.4.5-1 1I 2-1                     11.2.5 I                I1.2 4 11.2-2                     11.2.5.2               /
     /                           /                        11.1-1 11.2-3                     11.2.5.3                11.2-1 1I 2-4                     11.2.5.4                11.2-2
     /                           /                        I1.2-3 11.3-1                     11.3.5.1               /
11.3 2                      11.3.5.2               /
     /                           /                        11.3 1
     /                           /                        11.3 2                                                                  ,
i1.41                       11.4.6                  11.4-1
;    /                           /                        11.4-2 11.4-1                      11.4.6                  11.4-3 11.5-1                      11.5.7                  11.5-1 1I52                        11.5.7                 /
11.5-3                      11.5.7                 /
12.1-1                      12.1.3                  12.2.1-1 12 2-1                      12.2 3                  12.3 1-1
     /                           /                        12.2.3-1                                                               l 12.3-1                      12 3.5                  12.4.2-1
;     12.3-1                      12.3.5                  12.4.2-2
: 12. 3< 2                    12.3.5                  12.4.4-1                                                               )
12 5-1                     12.5 5                   12.6-1 13 1-1                      13.1.1                  13.1-1 13 2-1                      13 2.1                  13.2-1 13 3-1                      1331                    13.3 1 l
l l
l L.                                             _     ._.    . . _ . _ _ . . . _ . . _ _ . ._____.____________.__.._____._.______w

e SS AR Table 1.8-2 Item No. SSAR Subsection No FSER Appendix F Item No 13.3 2                 13.3.1            13.3-2
             /                          /                  13.3-3 13.4 1                 13.4.1            13.4-1 13.5 1                 13.5 1            13.5-1.1
             /                          /                  13.5.2-1
             /                          /                  13.6.1 1 1361                     13.6 13.1         13.6 2-1 13 6-1                   13.6.I3 1         13.6.4-1 13.6-1                    13.6.13.I         13.6.10-1 l3.6-1                   13.6. I 3. I      13.6.12.I 13.6-1                    13.6. I 3. I      13.6.13-1 13.6-3                     13.6.I3.3         13.6.6-1 13.6-3                     13.6.I3.3         13.6.I1-1 13.6-2                     13.6.I3.2         13.6.I3.2.I 13.6-3                      13.6.13.3          13 6.I3.3-1 I4.4-1                     14.4.1             I4.2.2-1
            /                           /                   14.2.3-1 l
14.4-2                      14.4.2             14.2.3-2                            I I4.4-3                     14.4.3             14.2.3.1-1 14.4-4                      14.4.4             14.2.3.2-1
            /                           /                   14.2.5-1
            /                           /                   15.3.4-1
            /                           /                   16.2-1 16.3-1                      16.3.2            /
17.5-1                      17.5               17.1-1 17.5-4                      17.5               17.2 1
            /                           /                   17.4.I-1
            /                           /                   17.4.2 1
            /                           /                   17.4.5-1                            l 1
17.5-3                      17.5               17.4.7.3-1                          !
17.5-7                      17.5               17 4.9-1
            /                           /                   17.4.9-2 17.5-2                      17.5              /
17 5-5                      17.5              /
17.5-6                      17.5              /
17.5-8                      17.5              /
18 2-1                      18.2.6            /
I82-2                      18.2.6             /
18 3-I                      18 3.1            /
I85-1                       18 5.4             18.5-2 18 5-1                      18.5.4             18.5-3 18.5-2                      18.5.4             18.5-1 18 6-1                      1861               18.6-1 18.7-1                      18.7.1            /
18.8-1                      18 8.5            /
18.9 1                       18.9.I             18.9-1 l
[

i      )
I SSAR Table 1.8-2 Item No.                                                               SSAR Subsection No.                             FSER Appendix F Item No.
I8.9-1                                                                                 18.9.1                                          I8.9 2 18.10-1                                                                                 18.10.I                                        18.10-1 18.11-1                                                                                 18.11.1                                        /
1
\
;                                                                            Item 19: Doern't have relevant contents in SSAR-Item 20 Page number in SSAR                                                                      issue name                                      FSER Appendix F ltem No.
1.9-44                                                                                  Issue A-40                                      20.2 1 1.9-73                                                                                  Issue 142                                       20.3-1 1.9-131                                                                                 Issue I. A. I.4                                 20.4 1 1.9-131                                                                                 Issue 1. A.2.6(1)                               20.4 2 1.9 132                                                                                 Issue I. A.4. l(2) & l. A.4.2                   20.4 3 1.9 134                                                                                 Issue !.C.5                                     20.4-4 1.9-134                                                                                 issue I.C.9                                     20.4 5 1 9-135                                                                                 Issue I.D.3                                     20.4-6 1.9-136                                                                                 issue I.F.2                                     20.4-7 l                                                                           1.9 140                                                                                 Issue II.F 2                                    20.4-8 l                                                                           1.9-142                                                                                 issue II J.3.1                                  20.4-9 l                                                                           1.9-142                                                                                 Issue II.J.4.1                                  20.4-10 l                                                                           1.9-144                                                                                 Issue li.K.l(26)                                20.4 11 l ~-                                                                        1.9-151                                                                                 issue III. A.3.3                                20.4 12 l
                                                                         /                                                                                          Bulletin 80-06                                  20.7 1
                                                                         /                                                                                          Bulletin 80-15                                  20.7-2 l
i
                                                                         /                                                                                          Bulletins 80-16 .                               20.7-3 I                                                                        /                                                                                          Bulletin 89-03                                  20.7-4                   )
                                                                         /                                                                                          Genenc Letter 81-38                             20.7-5
                                                                         /                                                                                          Generic Letter 81-39                            20.7-6
                                                                         /                                                                                          Genenc Letter 83-07                             20.7-7
                                                                         /                                                                                          Genenc Letter 83 11                             20.7-8
                                                                         /                                                                                          Genenc Letter 89-07                             20.7-9
                                                                         /                                                                                          Genenc Letters 89-15 & 93-01                    20.7 10 I
i I

y 7p.:p ~ c.
l i
FAX TO NRC ON AP600 June 9,1998 To:     Joe Sebrosky Ted Quay l
Attached is a summar" table listing each of the AP600 COL items presented in Chapter 19 of the advanced FSER, and the corresponding SSAR/PRA section where the FSER COL item is addressed.
Note there are 30 COL items listed for Chapter 19 of the advanced FSER whereas there are 5 PRA-                                                    I specific COL items m the AP600 PRA. The conclusion is that many of the FSER CCL items are covered in SSAR sections, and there are some duplicates of COL items within FSER Chapter 19.
Please call me or Jim Winters at your convenience to arrange a telecon between yourselves (Ted and Joe) and us. We would like to use the attached information as a tool for the telecon discussions to resolve the differences between the advanced FSER COL items and the PRA/SSAR COL items.
Regards, i
Ci y Haag Advanced Plant Safety & Licensing Westinghouse cc:     AP600 Informal Correspondence File Jim Winters

I I
(
l CHAfrTER 19 FSER vs. SSAR/PRA COL ITEMS                                           i I
Correspondmg FSER COL               FSER Page         Brief                                              SS AR COL Item #                 (19-0             Desenption                                         Section 19.l.1-1             l 8. 76,102      l Revise PRA for site-specitic info etc.           l PRA 59.10.6 Comment:
This COL item is similar to what is written in PRA section 59.10.6; however, it is too detailed / specific. The PRA COL description does not commit the PRA to be revised, but rather if the as built plant is not consistent with the baseline PRA (which includes the baseline internal and external events), thm the COL is to determine what actions to take.

== Conclusion:==

AP600 PRA COL item in section 59.10.6 remains as is.
19.1.3.1 1             34.102            List ofimportant SSCs to D-RAP                      17.5 Comments:
(1) The FSER COL description on page F 15 should not include the words "and maintenance programs."
FSER pages 19 34 & 19-102 do not specify mamtenance programs.
(2) This FSER stem is covered by a COL item in SS AR <ection 17.5. It is not necessary to duplicate the COL item within Chapter 19. Why isn't this cosered by FSER COL item 17.4.2-1 and 17.4.7.3-1 (which happen to be duplicates as well per FSER page F 14)?

== Conclusion:==

The AP600 PRA will not include a specific COL ttem to cover this RAP item because it is covered by COL actions in SSAR section 17.5.
:y:.=        _ ,                                  n y;;;r? = p ~ --- + y : + - 3_n:~2 qq 19.l.3.1-2           l 34.102         l Lnt of risk-important operator tasks                 18.7.1 Comments:
(1) Remose the words "and fixed dnplay panel" from the description on page F-15. It is not correct to include these words.
: 12) This is cosered by a COL item in SSAR Section 18.7.1. It is not necessary to duphcate the COL item.
Why isn't this cosered by FSER COL item 18.5-27 i3) The COL item in SSAR section 18.7.1 instructs the apphcant to follow the implementation plan that is prouded in WCAP-14651, which is w here the inclusion of risk-important operator tasks is discussed

== Conclusion:==

The AP600 PRA will not include a specilie COL item to cos er thn because it n eosered by a COL action in SS AR section 18.7.1.
        %mwn*
191 31 3
                                                        .. -if5]
l 35             l MCR HEF V&Y nitect PRA HRA
* l 18.11.1 '
Comment-iIi Do not under tand what n meant by thn FSER COL item s2 Does the statt mean it% the COI responsibihty to deselop the HFE V&V plan and to esecute and Jocument it ? iSee SS AR estion is 1I I COL itemi l

4 y                            ?~~. Q g g y                  *;''_T.Y T;~     l             Z.
19.1.5-I                                    76             PRA update for extemal Gooding, hurricanes,                                PRA 59.10.6 other external events on site-speci6c basis Comment:
This COL item is similar to what is written m PRA section 59.10.6; however. It is too detailed /speci0c. The PRA COL description does not commit the PRA to be revned, but rather if the as-built plant is not consistent with the baseline PRA (which includes the baseline internal and external eventsh then the COL is to determme what actions to take,

== Conclusion:==

AP600 PRA COL item in section 59.10.6 remains as is.
       %,7'                             ~ ; +., M f 2f4*6 W . C                .
                                                                                      ~         ~~
19.1.5-2                                    76.81.102. Seismic walkdown & compare as-built SSC                                    PRA $9.10 6 277.279.280. HCLPFs to W values in PRA Chapter 55 281.283.284 Comment:
This COL item is similar to what is written in PRA section 59.10.6.
This FSER COL item is also duplicated by FSER COL items 19A.2.5-1.19A.2.5-2 and 19A.2.5-3.

== Conclusion:==

AP600 PRA COL item in section 59.10.6 remains as is.
19.l.5-3                                  084.102          Update fire PRA                                                            PRA $9.10.6 Comment:
Tlus COL stem is similar to what is written in PRA section 59.10.6: howeser, it is too detailed / specific. He PRA COL description does no' commit the PRA to be updated, but rather if the as-built plant does not conform with the internal fire analpis. then the COL is to determme what actions to take. Note in the PRA.
the 6re and flood COL itera is combined into one COL action.
Conclusion.
AP600 PRA COL item in section 5910 6 remains as is.
                                      - ey n_ y                                                                                                 . . : F =g-1915-4                                     l91.102        l L'pdate flood PRA                                                           PRA 59.10 6 Comment:
This COL item is similar to w hat is w ritten m PR A section 5910 6; howeser. it is too detailed / specific. The                                           l PRA COL Jessription does not commit the PRA to be updated. but rather if the as. built plant does not conform with the internal flood analpes then the COL is to determine what actions to take. Note in the PR A. the nre and flood COL item is combined into one COL action i C. nclusi..n.
        \PN C PR A COL item m section 59 to 6 remams as it I ..                              _ '. U ' '                                  '._ N                                                                        M

9 19.1.8-1                                                                                                           l 103/IN                 l Fire & tlood barrier and maintenance                                                                                      l 9.5.1 A Comment:
(l) Why isn't this an FSER COL item from 9 5' q 2) This FSER item is covered by the third COL stem in SS AR section 9.5.l.8 (refers to Table 9.5.1-1 items identified by the acronym "WA"). Specifically. items 4 and 29 of Table 9.5.1-1 cover this. It is not necessary to duplicate the COL item aithin Chapter 19.

== Conclusion:==

The AP600 PRA will not include a specific COL item to coser this because it is covered by a COL action in SSAR section 9.5.1.8.
                                                                                                                                                                                                                                                                                                                  "_~'~Z Z _
19.1.8 2                                                                                                                  104                  Compensatory measures to minimize fire /Cood                                                                                 9.5.1.8 risk - admin. controls, procedures etc.
Comments:
(1) Text on page F-16 needs to clanfy that it is related to fi .rlood barrier penetrations and fire doors (per page 19-104).
(2) Why isn't this an FSER COL item from 9.5?
(3) This FSER item is covered by the third COL stem in SSAR section 9.5.1.8 (refers to Table 9.5.1-1 items identified by the acronym "WA"). Specifically, items 4 and 29 of Table 9.5.1-1 cover this. It is not necessary to duplicate the COL item withm Chapter 19

== Conclusion:==

The AP600 PRA will not include a specific COL item to coser this because it is covered by a COL action in SSAR section 9.5.1.8.
                                                                                 .z.                              ,
                                                                                                                                                           .. ~. -
                                                                                                                                                                                        .-    .g g_ . _                                                                                                 _-           -
4 19.l.8-3                                                                                                                  104                  Implement maintenance guidelines of                                                                                           13.5.1 Shutdown Eval Report (WCAP-14837)
Comments:
ili A COL item in SSAR 13.5.1 pert.iining to WCAP-14837 cosers the FSER COL item at a higher lesel.
q2: Why isn't this an FSER COL stem in Chapter 13.5 '                                                                                                                                                                                                                                                                        ]

== Conclusion:==

The AP600 PRA will not include a specific COL item to coser this because it is cosered by a COL action m SSAR section 13 51.
                                                                                                                                                                                                               ~
                                                    -4 9                                                                                                                                   e
                                                                                                                                                                                                                                                                                                                       - #-g                                 j 19 I 8-4                                                                                                           l104                      l Control transient combustibles                                                                                              j 9.51 A                                         l l Comments:
ili Why isn't this an FSER COL item trom 9.5 ?
2i This FSER item is coscred by the third COL item in SS AR section 9.5.1.8 (refers to Table 9.5 l-I                                                                                                                                                                                                                       )
items identified by the acrony m "W A"> Specifically. item 4a of Table 9.5. l-l cosers this. It is not nesessary to duplicate the COL stem within Chapter 19 Concluuon The APNio PR A will not include a qwcitie COL item to coser this because it is cosered by a COL action in SSAR settion 9 518
                                                 .~.a...                                                                                                      .
                                                                                                                                                                                                 . , . s . 9.i. g- s , _ - ^' _ ^ ' nci: q

e 191.85               106             i Procedures / training to close entm hatches &     13.5.I & 13 2.1 l penetrations Comment:
(1) Procedures and training are covered by COL items in SS AR sections 13.5.1 and 13.2.1. respectively. It is the COL's responsibility, working with the NRC to develop what procedores and training are necessary.
Thus, the FSER COL item is too specific.
l                 (2) This FSER item should refer back to Chapter 13.

== Conclusion:==

The AP600 PRA will not include a specific COL item to cover this because it is coscred by COL actions in SSAR sections 13.2.1 and 13.5.1.
j! M yM7 -                                   - -
                                                                                                                      ; , ;, 7 19.1.8-6             106                Administrative controls to control foreign        13.5.1 1                    debns in entm Comment:
(1) Admin. controls are covered by a COL item in SSAR section 13.5.1. It is the COL's responsibility, r'>rking with the NRC to develop what admin. control are necessary.
(2) This FSER item should refer back to Chapter 13.

== Conclusion:==

De AP600 PRA will not include a specific COL stem to cover this because it is covered by a COL action m SSAR section 13.5.1.
19.1.8-7             108                 Procedures / policies / training for wide range   13.5.1 & 13.2.1 pressurizer lesel indication Comment:
a 1i Procedures and policies are cosered by a COL item in SSAR section 13.51. and training is cosered by a COL item in SSAR section 13 2.1 (2) Same comments as 19.1.8-5 apply.

== Conclusion:==

The AP600 PR A will not include a specific COL item to coser this because it is covered by COL actions m SS AR sections 13 2.1 and 13.5.1.
                                                                                                                    .fM 191.08                ii!                Cleanliness program on IRWST - control            6.3.8.1 foreign debris Comments:
ili The cleanliness program on the IRWST is cosered by the COL item in SSAR section 6.3 8.1. More det.uls of what is cosered by the COL item are presided in SS AR sections 6 3 2.2.7.2 and 6.3 2.2.7.3.
O Tha COL item is cosered by FSER COL item 6 2.1.8-1. There a no need to duplicate the item.
Con.lusion The \P600 PRA will not include a specihe COL stem to coser tha because it is cosered by a COL action m SS AR section 6 3 x 1
    . _ _ _ _ _ .                                                                                                              J

e 19.l.8-9                                                                                              115      Policies / procedures to maximue availability of 13.5.1 RNS V023 during cold shutdown Comments:
(1) Procedures and policies are covered by a COL item in SSAR section 13.5.1. The ERGS coser the operation of this valve. and the COL is to produce the EOPs per SS AR section 13.5.1.
(2) Same comments as 19.1.8-5 apply.

== Conclusion:==

The AP600 PRA will not include a specific COL item to cover this because it is coscred by a COL action m SSAR section 13.5.1.
                                                                                                                                                                                                            --.my
                                                                                                                                                                                                      , ,. w . +
19.1.8 10                                                                                            115/l16    Admin. controls on inadvertent opening ot        13.5.1 RNS V024 Comment:
Admin. controls are coscred by a COL stem in SSAR section 13.5.1. The FSER COL item is too specific (see comments to 19.1.8-5).

== Conclusion:==

The AP600 PRA will not include a specific COL item to cover this because it is covered by a COL action in SSAR section 13.5.1.
y      a-l a. l .8- 11                                                                                       116         Control room design account for NRC COL           18.7.1 item 19.19-10 Comment:
(1) This esent is identihed as an esample of a risk-important task in Appendix A of WCAP-14651 (pgs A 3/A-4). The COL item in SS AR section 18.71 instructs the applicarit to follow the implementation plan that is provided in WCAP 14651. w hich is w here the inclusion of risk important operator tasks is discussed.
(2) This is cosered by a COL item in SS AR Section 18.7.1. It is not necessary to duplicate the COL item.
Why isn't this cosered by FSER CO! item 18 5 2.'

== Conclusion:==

The AP600 PRA will not include a specitic COL stem to coser this because it is covered by a COL action in SSAR 18 71.
                                    -.; J . .% .~i v -                                                                                                -
191312                                                                                              122          Maintain procedures to respond to low hot leg     13.5.1 les el alarms Commentt i li Praedures are cosered by a COI. item in SS AR section 13 5.1                                                                                The ERGS coser the response to low hot !eg lesel alarms. and the COL is to produce the EOPs per SS AR section 13 5.1.
O same comments as 19155 apply Cons lusion The \PNo PR A will not ini,luJe a specific COL stem to coser this because it is covered by a COL action m SSAR section 13 5 I
                               ......,   M_-. .                                                                                                                          J. "                             G5h

t 19.2.3-1                160             Verify RPV insulation consistent with design                                                     5.3 6.4 bases for IVR Comment:
This COL stem is cosered in SSAR section 5.3 6.4. It is not understood why this isn't an FSER Chapter 5 COL item.

== Conclusion:==

The AP600 PRA w all not include a specific COL ttem to coser this because it is cosered by a COL action in SSAR section 5.3 6.4
                                              ' MSS *.$?Wt?.f**WT?M                                                                                                                 M WW 19.2.3 2                189             Cntm spray design include locations of                                                             12.4.1.8 valves / connections to account for expected                                                      (not as a COL radiation levels and shielding requirements for                                                   item) any required kical operator action Comment:
(1) No COL item is needed because this is part of the design information presented in the SSAR.
(2) The access to these valves / areas is covered by SSAR section 12.4.1.8.

== Conclusion:==

The AP600 PRA will not include a specific COL item to cover this because it is covered by the design information presented in SSAR section 12.4.1.8.
4 Me* . . uce ove : .: --                                                                                                                   -
19 2.5-1                 14.58.125.      Develop accident management plan                                                                   PPA 59.10.6 187.194.196 Comment:
This COL item is similar to what is written in PRA section 59.10 6 Note FSER COL items 19 2.5-1 and                                                          J 19.2.5 2 are represented by one COL action in the PRA.                                                                                                       I l

== Conclusion:==

AP600 PR A COL item in section 59.10 6 remains as is.
g&.           ~7.a, w .                ~ : n.c .- L _ ' ' ^__
                                                                                                                                                                                       ~
                                                                                                                                                                                                      -y &
19.2 5-2               l195            l Follow SAMG (WCAP-13914. Rev. 3)                                                                   PRA 5910.6 Comment:                                                                                                                                                      1 This COL item is similar to what n written in PRA section 59.10 6. howeser. FSER COL items 19.2.5-1 &                                                         l 19.2.5 2 are represented by one COL action in the PRA.
i l

== Conclusion:==
AP600 PR A COL item in section 5910 6 remains as is.
                                            ~
                                                                        =                                                                                                                  :=-
                                                    ,;                     c                           .=-m&~-
                                                                                                                                                                                                  ~.--y..
19253                    195              \ddress considerations (noted by staffiin use                                                       '"
of containment sprays Comment.
What is the statt requestmp here for a COI. item ' h thw something related to procedure * (i.e.. cosered by SSAR estion 13 Si or to SAMG #cosered h3 FSER COL item 19 2.51 L' j         5            . . .
                                                                                                        . .e r n; x ., ._.,g                                                ggg,                      p -

l 9 l
19.3 1                                                                                                         l 238. 239               l Outage planning                                l 13.5.1 l     Comment:
Outage planning is covered by a COL item in SSAR section 13 5.1

== Conclusion:==

!     The AP600 PRA will not include a specific COL stem to coser this because it is covered by a COL action in l     SSAR section 13.5.1.
[        Q. ' , . . n&.                                   '
                                                                                                                                               ~ %1"2                     .
7 . **-
19 A.2.5- 1                                                                                                                286.287        Confirm as-built plant conforms to design used    PRA 5910.6 (twice)         as bases for SMA Comment:
This COL item is similar to what is written in PRA section 59.10.6.
His FSER COL item is also duplicated by FSER COL items 19.1.5-2.19A.2.5 2. and 19A.2.5-3.

== Conclusion:==

AP600 PRA COL item in section 59.10.6 remains as is.
p                                                                 . . ,
J':ff g.';';                           ,
19A.2.5-2                                                                                                                  287            Identify deficiencies in median margin factors    N/A for other supports Comments:                                                                                                                                                                                                                              )
l     (I) The FSER COL text on page F-18 does not relate to the text that " describes" the FSER COL item on                                                                                                                                  I page 19-287.
'     (2) This FSER COL stem is poorly described on page 19-287. It appears to be related to FSER COL item 19 A.2.5 l .
(3) For the words on FSER page 19-287, it appears the NRC is asking how COL item 19A.2.5-1 will identify if there are deficiencies. It is not Westinghouse's action to describe how the COL will identify if the as0 built plant conforms to the SM A. but rather it is the COL's action to do so (4) It is not understood why + tatt added this COL item when Westinghouse and NRC has agreed on SMA COL items earlier in the ;..ar.
t 1

== Conclusion:==

~
Westinghouse does not agree that this COL item is necessary.
mWet.% 4.a ,n                                                                                                                     - --
l      19 A 2.5 3                                                                                                                 287,288.289    Seismic spatial systems interactions (SMA-         PRA 5910.6 related) and deselop details of seismic w alkdow n Comment:
Tb COL item is similar to what is wriiten m PRA section 5910 6.
Ihn FSER COL item n also duphcated by FSER COL items 19A.2.51.19A.2.5 .'. and I')A 2.5-3.
l l
l     Concluuon:
       \PNW) PR A COL item in section 5910 6 remains as n.
                                                                      '' G+ -                                                                                     .. <GQ

6 19A.2.5-4           287.288            Compare as built HCLPFs to those assumed in                                                       PRA 59.10 6 SMA Comment:
This COL item is similar to what is written in PRA section 5910.6.
This FSER COL item is also duplicated by FSER COL items 19A.2.5-l.19A.2.5-2, and 19A.2.5 3.

== Conclusion:==

AP600 PRA COL item in section 59.10.6 remains as is-I 1

FAX COVER SHEET
  ,   W        Westinghouse RECIPIENT INFORMATION                             SENDER INFORMATION DATE:              huvE         /
p / F$            NAME:
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COMPANY:                                             Facsimil.:       win:          284-4887 OE N                                              outside: (412)374 4887 LOCATION:           /d///7E Si# 4-/o 6 J l
Cover + Pages       1+      h n,. r.ii..in, p .. .r. n.ine ..nt er.. in. w tin a.o       En.r,y c.nt.r, e , r...r.
Monroeville, PA. If any poblems occur during tals transmission, please call:                  i WIN: 284 p2% Bev ).r Outside:(412)374-6529 i
COMMENTS:
JrcW / ,            k i i Ap/cm            Any       Sig      Wew tre>es f rf & hE%              rv   y%      kr 7-ric            N)Ay'dl # M 77, v//ry      < a i u a t> r :               .
67D             Lcw bartrus G 7 7 r- Situf 2agn rv OV7%new                           ($sh SaJ Z.uab f1I% -       bc7N or fifYJ< ust N/o& w [70 giLevies)                                l 6 Ciel -       fba /CAbst /AcM 's hanu h=sesuru~
               &T21 -        i 08vi6-non 44wiru<~2, kuo k rc w nen s531        ,
L,     fs um 4 < ><         M 6 /r f

ITAAC OPEN ITEM i
OPEN ITEM 6767 - ITAAC Task Group Meeting Open item 4/16/98 4/17/98
: 22. Leak Detection 3.6 Re-organize Leak Detection ITAAC to include various methods for detection. See GE ABWR 2.4.3, Leak Detection and Isolation System paragraph 4.
Realign equipment to match methods.
RCDT (level detection) level instrumentation is not identified anywhere in ITAAC and needs to be added.
Response (Revision 1):
The AP600 leak detection ITAAC includes the three methods of leak detection of unidentified leakage discussed in SS AR Section 5.2.5.3. These include:
containment sump level containment atmosphere radiation RCS inventory balance (pressurizer level, RCS hot and cold leg temperatures, RCS pressum, CVS makeup and letdown flow).
The ITAAC is organized with the AP600 lef: detection methods. The RCDT level detection is used to identify leakage from the RCS that is routed to the drain tank. This leakage is considered identified leakage, and does not meet the criteria for inclusion in this ITAAC. However, it is added to this ITTAC to expediently close out this open item.
In a subsequent discussions with the NRC staff on 5/15/98, the staff indicated that the design description should be modified to pmvide an overview explanation of the AP600 the leak detection methods. Revision 6 of the ITAACs is modified as shown to address this comment.
SSAR Revision:
None Tier i Revision:
r Secm, L L 1
{
\
!                                                                                                                               l OITS 6767-1 We @ m                                                                            Redslon 1 i
1 l
l I

Certified D3 sign Mitsri:1 REACTOR 5COOLANT PRESSURE BOUNDARY LEAK DETECTION Revision:                                                                                E t Effective: 5/8/98                                                                        Rt . ~
h.j 3.6     Reactor Coolant Pressure Boundary Leak Detection 1
Design Description
(
The reactor coolant pressure boundary leakage detection monitoring provides a means of detec quantifying the reactor coolant leakage. Leakage detection monitoring is accomplished using             ,
i stramentation and other components of several systems,                                                )
t
: 1. The diverse leak detection methods provide the nonsafety-related function of detecting small lea when RCS leakage indicates possible reactor coolant pressure boundary degradation.               !
I Inspection, Tests, Analyses, and Acceptance Criteria Table 3.6-1 specifies the inspections, tests, analyses, and associated acceptance criteria for the leak detection equipment.
t l
i  diverse methods are provided to l
To detect unidentified leakage inside containment, the follo$ ng                               !
f quantify and assist in locating the leakage:                                    ,
i
* Containment Sump Level a
Reactor Coolant System Inventory Balance                                            .
* Contamment Atmosphere Radiation                                                       f l
m 1
I T W use                    -
owAAesv smaos.
orrs 679 L gg V . /

e                                                                                                                                                                                                                                                                                                               i o
RESPONSES TO NRC REQUEST FOR ADDITIONAL INFORMATION lE  "}
l OITS 6795 - ITAAC Open Item                                                                                                                                                                                                           1 Per telecon with b7C staff on 5/1/98 (Pella)
AP600 CDM Rev 4, page 2.5.13, Table 2.5.12, Item 13.
Actuation of the IRWST Drain to Containment is a function manually actuated by DAS. Why isnt this same function included on page 2.5.2-7, Table 2.5.2-4 as a function that is manually actuated by the PMS?

===Response===
The PMS manual actuation of the IRWST Drain to Containment function is included on page 2.5.2-7, Table 2.5.2-4. The PMS manual control for IRWST Containment Recirculation actuates both the IRWST Containment Recirculation function and the IRWST Drain to Containment function.
The PMS manual control for IRWST Containment Recirculation opens all four parallel paths for IRWST recirculation. This includes the two paths without check valves which are used for IRWST Drain to Containment. There is no separate PMS manual control for IRWST Drain to Containment; therefore, no separate ITAAC entry is required.
The DAS manual control for Containment Recirculation opens only the recirculation paths containing check valves. A separate DAS control for IRWST Drain to Containment is therefore required and included in ITAAC 2.5.1, Table 2.5.1-2.
Table 2.5.2 4 will be revised as shown for clarity.
SSAR Revision:
None I
OITS 6795-1 l
_ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _       _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ . .__ __ _ _ . _ . _ . . _ _ _ . . _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _                                               _____J

e RESPONSES TO NRC REQUEST FOR ADDITIONAL INFORMATION
:i~' '%
1 ITAAC Revision:
I Revise Table 2.5.2-4 as shown:
l i
Table 2.5.2-4 PMS Manually Actuated Functions Reactor Trip Safeguards Actuation Containment Isolation Stages 1,2, and 3 ADS Actuation Stage 4 ADS Actuation Main Feedwater Isolation CMT Injection Steam Line Isolation Passive Containment Cooling Actuation PRHR Heat Exchanger Alignment IRWST Injection l                            IRWST Containment Recirculation / IRWST Drain to Containment MCR Isolation and Air Supply Initiation i
l OITS 6795-2 T Westinghouse l
w___-___________      _ _ _ _ . _    _

e iTAAC OPEN ITEM
                                                                                                                                                                                                          ;::: =
                                                                                                                                                                                                          =      s OITS 6813       ITAAC Meeting Open Item ITAAC meeting with NRC staff on 5/12/98 (Wilson)
Section 3.3 Buildings The added ITAAC for the inspection of the buildings needs to refer to the " functional" not " physical" inspection of the buildings or, alternatively, physical anangement, as proposed by Westinghouse for the inspection of the buildings, needs to be defined in Section 1.1 of the Certified Design Material.

===Response===
A definition for Physical Arrangement will be added and the definition for " Functional Arrangement will be modified in the AP600 Certified Design Material, Section 1.1, " Definitions."                                                                                                          ,
SSAR Revision:
None ITAAC Revision:
He definitions for Physical Arrangement and Functional Anangement in Section 1.1, " Definitions," will be as follows:
l l     Physical Arrangement (of a structure) means the arrangement of walls, ceilings, andfloors that l     constitute the structure, and which is described in the design description.
I i
l                          l     Functional Arrangement (of a system) means the physical anangement of s:=::=s, systems, and                                                                                           j l     components to provide the service for which the s:=:un = system is intended, and which is                                                                                              !
described in the design description.                                                                                                                                                  I I
i l
OITS 6813-1 Y Westinghouse r
i

t ITAAC OPEN ITEM
                                                                                                                                                ==
l l
h==
l OITS 6814 - ITAAC Meeting Open Item ITAAC telecon with NRC staff on 5/12/98 (Wilson)
Section 2.1.3 Reactor System - Fuel and CRDM ne added ITAAC that states the initial core meets the principal design requirements that are to be I
specified in SSAR chapter 4 will be met is appropriate as an ITAAC. However, this does not include future cores or reloads. Derefore, a sentence in the narrative of design description needs to be added that states that the fuel, crdms and recas will be designed to meet the pripnciple design requirements. His is sufficient to address future cores and reloads.
Fax from SRXB on 5/15/98 (Wilson)
Item 2) In Section 2.1.3. Reactor System, Item 13 of the design description reiaains an open item.

===Response===
Section 2.1.3, Reactor System, will be revised to include a sentence that the fuel assemblies and RCCAs are designed in accordance with the principal design requirements.
SSAR Revision:
None Tier 1 Revision:
De second paragraph of the narrative in the design description of Section 2.1.3, " Reactor Systems," is modified as follows:
I De reactor core contains a matrix of fuel rods assembled into fuel assemblies using structural elements. Rod cluster control assemblies (RCCAs) are positioned and held within the fuel assemblies by control rod drive mechanisms (CRDMs). He CRDMs unlatch upon termination of electrical l      power to the CRDM thereby releasing the RCCAs. The fuel assemblies and RCCAs are designed                                                \
l     in accordance with the principal design requirements.
l OITS 6814-1

1 RESPONSES TO NRC REQUEST FOR AD0lTIONAL INFORMATION p:.
                                                                                                     =       :p OITS 6829 ITAAC Open Item Per Email from the NRC on 5/15/98 (Hinson)
Section 3.5 Radiation Monitoring The staff recommends the following phrase be added to the end of the first sentence in Section 3.5 (Radiation Monitoring) under Design Description (after the word "possible"):
                                                ~
       "in accessible areas to provide indication of unusual radiological events."

===Response===
We agree to revise Section 3.5 Design Description alternatively, as shown below to address the staff's recommendation..
SSAR Revision:
None ITAAC Revision:
The first paragraph Section 3.5 Design Description will be revised as follows:
R:di::ica =ni:cring is provided for Sc= p!=: == wher: i= i : :igni5:=: pc:en:!:! for airborn: cen:=!=:ica =d for Sc= prceen =d eff!=n: ::::=: ;h= con *=:=:ica i: pczib!c.
l Radiation monitoring is provided in those locations identified in Tables 3.51,3.5-2,3.5-3,3.54, I and 3.5-S. The radiation monitoring component locations are as shown in Table 3.5-7.
OITS 6829-1 W-Westinghouse I
l
(
i

            )
ITAAC OFEN ITEM
                                                                                                                    =-.   =g 5
OITS 6833 - ITAAC Meeting Open Item t
i Fax from SRXB on 5/15/98 Item 3)     Figure 2.1.3, Rod Cluster Control and Drive Rod Arrangement, needs to be modified to include the height of the fuel assemblies.

===Response===
Westinghouse proposes to address this open item by adding the vertical distance between the upper and lower core support plates to Figure 2.1.3. Rod Cluster Control and Drive Rod Arrangement. This dimension addresses the staff's request because the fuel assemblies will be located between these two support plates. This dimension can also be verified prior to delivery of the fuel to the site and prior to insertion of the fuel assembly into the core.                                                              !
SSAR Revision:                                                     ,
None                                                               .
l Tier 1 Revision:
The venical dimension between the upper and lower core support plates is shown in the attached figure.
l I
OITS 6833-1 L-______._______m_

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OITs 6833-2 T Westinghouse

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Westingh0USS                            FAX COVER SHEET l
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l RECIPIENT INFORMATION                                SENDER INFORMATION t
i i       DATE:                 DOM          f, /f96                Name:            hEA/E        /L4 cA TO:                   7cy2/lV /J/ t. J ef)                LOCATION:        ENERGY CENTER - EAST PHONE:                h/ - JJ /- th ~i - J 00 2           PHONE:           Office: 412-374- C$i o                     {
COMPANY:                                                  Facsimile:       win:        284-5535
()J    /d[28._                                      outside: (412)374-5535 LOCATION:             Q r//77 F2 W T             M 7)
Cover + Pages        1+      /
l Th ,oslowing pages are being sent from the Westinghouse Energy Center, East Tower, Monroe ~ville, PA. If any problems occur during this transmission, please call:
WIN: 284-5489 (Wanda)/4031 (Delinal or Outside (412)374-5489/4031.                                                  l l       COMMENTS:
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                  !                      Add the following to the definitions in section 1.1 of the ITAAC Design plant grade means the elevation of the soil to the west side of the nuclear island assumed in the design of the AP600. Adjacent buildings are located on the other three sides of the nuclear island.
Site grade means the as-built elevation of the soil to the west side of the nuclear island.
Nominal floor elevationis the designation applied to name a floor. The actual elevation may vary due to floor slope and layout requirements.
Column line is the designation applied to a plant reference grid used to define the location of building walls and columns. Column lines may not represent the centerline of walls and columns.
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W I Westinghouse aums FAX COVER SHEET RECIPIENT INFORMATION                                 SENDER INFORMATION DATE:             hdAd/O,/7h
                              /                             Name:                         hWE /[L/(A TO:                 MT/)/ N/L $ F                       LOCATION:                     ENERGY CENTER - EAST PHONE:
7.- / -b/- //f c)t)d)               PHONE:                        Office: 412-374- $3 /.,
COMPANY:                                                Facsimile:                    win:                                                                 284-5535 h$     M M C _.                                                 outside: (412)374-5535 LOCATION:             Cs // trF J~l /d T , / dt D Cover + Pages      1+
Tha following pages are being sent from the Westinghouse Energy Center, East Tower, Monroeville, PA. If any problems occur during this transmission, please call:
WIN: 284-5489 (Wanda)/4031 (Delina) or Outside (412)374-5489/4031, i
COMMENTS:
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I. Overall Approach to Tier 1 Material for the AP600
: 1. Features important to plant safety must be identified and included in Tier 1.
: 2. Tier 1 material must be specific, unambiguous and verifiable.
: 3. Design descriptions are a subset of Tier 1 material that serve as binding requirements for the 60 year life of the plant.
: 4. Design descriptions include the descriptive narrative and design commitments.
Tables and figures referenced in the design description are part of the design description.
5, Tables referenced in the design description identify features of structures, systems and components important to plant safety. Tables are also referenced in the ITAAC for verification using explicit acceptance criteria.
6 Figures referenced in the design description are used to illustrate functional arrangement of systems. Each component in a figure is identified by its unique tag number.
: 7. Figures not referenced in the design description are used to provide clarifying information in support of the design description. These figures contain appropriate notes stating the figure is not part of the Tier 1 material and the figure is provided for information only.
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o-_-_----------__-_        -       -_                                                                                     J

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Discussion Points for 2:30PM Telecon with NRC June 10,1998 on 1
AP600 Tier 1 Material Section 3.3, Buildings Approach to Building Figures in Tier 1
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  -e II. Approach to Tier 1, Section 3.3, Buildings
: 1. The physical arrangement of a building is defined as the arrangement of the building features (floors, ceilings, walls, and basemat) and of the structures, systems, and components within, which are described in the building design description.
: 2. The building features most important to safety are those that provide:
a) Ability to support normal and seismic loads (Tables 3.3-1,3.3-5 and 3.3-7) b) Radiation shielding (Table 3.3-1) c) Flood protection (Table 3.3-2) d) Fire protection and electrical separation (Table 3.3-3) f) Protection from pipe breaks (Table 3.3-4)
: 3. Each of tables noted in item 11.2 above provide specific features that can be verified using the acceptance criteria delineated in the building ITAACs (Table 3.3-6.)
: 4. Figures 3.3-1 through 3.3-13 are provided in support of Table 3.3-1 to help identify applicable column lines and elevations used to describe the walls, floors and ceilings delineated in Table 3.3-1.
: 5. Figure 3.3-14 is provided in support of Table 3.3-5 to help identify the overall dimensions of the Nuclear Island.
: 6. Figures 3.3-1 through 3.3-14 are not intended to be part of the Tier 1 material and therefore, the Ggures are not subject to the inspection of the physical arrangement of the buildings as defined in item II.1 above, o Westinghouse' concern is that by including these figures in the Tier i design description, each feature of the figure becomes inspectable and is subject to interpretation. This subjectivity is not present in the functional arrangement Sgures used in the system ITAAC since only the functional connections of components identined by tag numbers are inspectable.
l l        7. The ITAAC of the inspection of the physical arrangement of the buildings (Item I in i            Table 3.3-6) is satisGed when the key features of the buildings described in the                                               .
Tables listed in item JI.2 above have been verified.
l o If there are other key features needed in Tier i to assure safety Westinghouse has offered to consider additions to the design description or the tables to address the specific staff concerns.
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III. Why Figures 3.3-1 through 3.3-14 are not required to be part of Tier 1 material.
: 1. The building features that require inspection have been identified by Westinghouse, and by staff review and concurrence, and have been included as specific, unambiguous and verifiable ITAAC.
2 The tables in Section 3.3 define the key features of the physical arrangement of the buildings that need to be inspected for compliance with the certified design.
: 3. Inclusion of these Revision 6 figures as part of the Tier i design description could be interpreted to mean that reconciliation of the as-built structures with these figures would be required as part of the ITAAC and the figures would constitute a binding requirement for the life of the plant. There is information shown on the Revision 6 figures which is not significant to safety.
: 4. The possibility exists that information on these figures not intended to be part of Tier 1 could be misconstrued to be required for Tier 1, and would lead to confusion, uncertainty and unnecessary delays in the successful completion of the ITAAC and that future plant modifications would not be possible without submitting an exemption to the approved certified design.
: 5. Discussion examples.
o          There is much more information on these figures than the set of information needed to assure plant safety is maintained. On the building layout drawings, this additional information may change as plant owners specify unique requirements. Information supporting plant safety on these drawings will not change since plant owners do not wish to revisit the licensing process, 1
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o IV. Westinghouse Position for Addressing the Staff Concern
: 1. Westinghouse has developed the AP600 Tier 1 Material to maintain the objective that all Tier 1 material be important to safety, and be specific and verifiable. For buildings, Westinghouse believes that:
a) The design descriptions and table include the necessary Tier 1 material to assure that each as-built AP600 plant complies with the design certification.              ]
I b) The Revision 6 figures are only necessary and useful for locating the Tier 1 material described in the design description and tables.                            I c) The Revision 6 figures provide extraneous information not needed to assure           l safety or to comply with certification, and the information may be misinterpreted as necessary for Tier 1.
: 2. Westinghouse asks that the staff consider the following options:
a) Westinghouse has requested the staff identify any building feature imponant to safety included in the Revision 6 figures that have not been included as a specific l                 ITAAC and Westinghouse will, with due consideration and deliberation, add that feature in a Table or as a specific ITAAC. The notes on the figures would remain as is.
b) Alternatively, or in conjunction with item IV.2.a above, Westinghouse proposes to modify the " Interpretation of Figures" in Section 1.1. General Provisions. In addition the notes on the Revision 6 figures would be modified as shown on the next page to state that information on the figures described in the design description and in the tables are considered to be Tier 1 material.
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a V. Proposed revisions to AP600 Tier 1 Material (Item IV.2.b only) l
: 1. Revise Section 1.2, " General Provisions," to clarify that the as-builtfeatures on the buildingfigures may vary provided the variations are in accordance with the tables in the design description.                                                                                            \
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Interpretation of Figures i
l             In many but not all cases, the design descriptions in Section 2 and 3 include one or more figures.
l             The figures may represent a functional diagram, general structural representation, or another j             general illustration. For instrumentation and control (I&C) systems, figures may also represent l             aspects of the relevant logic of the system or part of the system. Unless specified explicitly, the l
figures are not indicative of the scale, location, dimensions, shape, or spatial relationships of as-l             t, silt structures, systems, and components. In particular, the as-built attributes of structures, sysems, and components may vary from the attributes depicted on the figures, provided that those l             wfetA.ne:icas disc =cd b :he de:,ign descrip;ica per:aining-4e the figure are act adve+sely
(       l     effeeted features andfunctions of the structures, systems, and components are in accordance
        !     with the tables in the design description.
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: 2. Modify the notes on each figure as follows:
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!             NOTES FOR FIGURES:
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: 1.         THE FOLLOWING STRUCTURES, SYSTEMS, AND COMPONENTS DEPICTED ON
!                        THESE FIGURES ARE NOT SEISMIC CATEGORY 1:
* VERTICAL ACCESS OPENINGS STAIRS ELEVATORS UNIT VENT I
: 2.         THE BUILD!NO OL"1!NES ^.RE PROVIDED FOR REFERENCE IN TABLE 3.3 i AND TABLE 3.1 $ ONLY AND ARE NOT PART OF EE BER ! MATERIAL OR THE DES!ON DESCR!"!!ON (EE DISCUSSION OF INTERPRETATION OF FIGURES, SECEON !.2, "GE"ERAL PROVIS!ONS," ALSO APPLIES.)
ONLY THOSE BUILDING FEATURES (WALLS, FLOORS, CEILINGS AND BASEMAT) THAT ARE INCLUDED IN TABLES 3.31 AND 3.3 5 ARE INCLUDED IN THE DESIGN DESCRIPTION.
: 3.          THE BUllDING ELEVATIONS ARE PROVIDED FOR REFERENCE ONLY AND ARE NOT PART OF THE DESIGN DESCRIPTION.
l            34.         NORTH IS PROVIDED AS A REFERENCE DIRECTION ONLY AND IS NOT PART OF THE EER ! MAHR!AL OR THE DESIGN DESCRIPTION.
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C:rtified De BUILDINGS Revision: 6 Effective: 5/29/98
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Figure 3.3 8 Nuclear Island Plan View at Elevation 135'3" 3.3-41 o:\ap60(NTAACSVev62303 twp6.lb-06049R 7                                                                                              l
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