ML20034F885
| ML20034F885 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 01/26/1993 |
| From: | Kenyon T Office of Nuclear Reactor Regulation |
| To: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| NUDOCS 9303050146 | |
| Download: ML20034F885 (16) | |
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January 26, 1993 Docket No.52-003 Mr. Nicholas J. Liparulo Nuclear Safety and Regulatory Activities Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, Pennsylvania 15230
Dear Mr. Liparulo:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON THE AP600 As a result of its review of the June 1992 application for design certifica-tion of the AP600, the staff has determined that it needs additional informa-tion in order to complete its review. The additional information is needed in the areas of generic safety issues (Q100.8),* valve reliability (Q210.27-Q210.28), plant systems (Q410.93-Q410.105), emergency response guideline:,
(Q440.32, Q620.50), and technical specifications (Q630.6-Q630.9).
Enclosed are the staff's questions.
Please respond to this request within 120 days of the date of receipt of this letter.
You have requested that portions of the information submitted in the June 1992 application for design certification be exempt from mandatory public disclo-sure. While the staff has not completed its review of your request in accordance with the requirements of 10 CFR 2.790, that portion of the submitted information is being withheld from public disclosure pending the staff's final determination. The staff concludes that this request for additional information does not cortain those portions of the information for which exemption is sought.
However, the staff will withhold this letter from public disclosure for 30 calendar days from the date of this letter to allow Westinghouse the opportunity to verify the staff's conclusions.
If, after that time, you do not request that all or portions of the information in the enclosures be withheld from public disclosure in accordance with 10 CFR 2.790, this letter will be placed in the NRC's Public Document Room.
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- The numbers in parentheses designate the tracking numbers assigned tor the questions.
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Mr. Nicholas J. Liparulo January 26, 1993.
This requirement affects nine or fewer respondents; and, therefore, is not
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subject to Office of Management and Budget review under P.L.96-511.
i If you have any questions regarding this matter, you can contact me at-(301) 504-1120.
i Sincerely, l
(Original signed by)
Thomas J. Kenyon, Project Manager Standardization Project Directorate Associate Director for Advanced Reactors i
and License Renewal i
Office of Nuclear Reactor Regulation
Enclosure:
i As stated i
cc w/ enclosure:
l See next page i
DISTRIBUTION-t
- Central File PDST R/F TMurley/FMiraglia DCrutchfield
- PDR WTravers RBorchardt TKenyon RHasselberg GGrant, EDO JMoore, 15B18 ACRS (11) i MMalloy MSiemien, 15B18 CLi, 8D1 JLyons, 8D1 PShea MRubin, 8E23 GHsii, 8E23 GWeidenhamer, RES MVagins, RES DFischer, 7E23 DTerao, 7H15 RLi, 7E23 i
TSullivan, 7E23 REckenrode, 10D24 JBongarra, 10D24 REmch, 11E22 CSchulten, 11E22 GSuh, 12E4 (2) i SC:P$:ADAR 0FC:
LA:PDST:ADAR PM: psf':ADAR PM:PDST:ADAR NAME: PSQ3 deh[)in:sg RHaMrg RBohrdt 0%d3 01/j/93 01/r4/93 01/8(//93 DATE:
0FFICIAL RECORD COPY:
DOCUMENT NAME: LETTER.VII
- To be held for 30 days i
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b Mr. Nicholas -J. Liparulo Westinghouse Electric Corporation Docket No.52-003 AP600 cc:
Mr. B. A. McIntyre Advanced Plant Safety & Licensing Westinghouse Electric Corporation Energy Systems Business Unit Box 355 Pittsburgh, Pennsylvania 15230 Mr. John C. Butler Advanced Plant Safety & Licensing Westinghouse Electric Corporation Energy Systems Business Unit Box 355 Pittsburgh, Pennsylvania l
Mr. M. D. Beaumont Nuclear and Advanced Technology Division Westinghouse Electric Corporation One Montrose Metro 11921 Rockville Pike i
Suite 450 Rockville, Maryland 20852 Mr. Daniel F. Giessing U. S. Department of Energy NE-42 Washington, D.C.
20585 Mr. S. M. Modro EG&G Idaho Inc.
i Post Office Box 1625 Idaho Falls, Idaho 83415 i
Mr. Steve Goldberg i
Budget Examiner 725 17th Street, N.W.
Room 8002 i
Washington, D.C.
20503 Mr. Frank Ross U.S. Department of Energy i
NE-42 Washington, D.C.
20585 l
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i ENCLOSURE i
REQUEST FOR ADDITIONAL INFORMATION ON THE WESTINGHOUSE AP600 DESIGN f
GENERIC SAFETY ISSUES 100.8 Section 1.9.4 of the AP600 Standard Safety Analysis Report (SSAR)
I addresses generic safety issues.
10 CFR 52.47(a)(1)(iv) requires the applicant to propose technical resolutions to those Unresolved Safety Issues (USIs) and medium-and high-priority Generic Safety Issues (GSIs) that are identified in the version of NUREG-0933 current on the date six months prior to application and which are technically relevant to the design. The version of NUREG-0933 that is applicable to AP600 is dated July 1991, as correctly stated in the SSAR.
However, Section 1.9.4 of the SSAR provides proposed resolutions only to those issues categorized in NUREG-0410, "NRC Program for the Resolution of Generic Issues Related to Nuclear Power Plants," dated January 1978. As a result, it does not appear that all applicable generic issues have been addressed. For example, Generic Issue 15,
" Radiation Effects on Reactor Vessel Supports," which is high-priority as stated in NUREG-0933, is not addressed in the SSAR.
Provide the proposed resolutions of all USIs and GSIs in the SSAR in accordance with 10 CFR 52.47(a)(1)(iv).
VALVES 210.27 Provide a written response to the pre-application request for additional information on component capability and reliability that was transmitted in a May 7, 1992 letter, or provide a cross-reference j
to any response (s) that may have already been formally submitted.
1 210.28 The staff, with the assistance of the Oak Ridge National Laboratory (ORNL), has been assessing critical valves for the AP600 design. The staff has identified critical valves and their critical failure modes, and is attempting to develop estimates of the initial reliability of these types of valves. Table A is a list of the critical valves that the staff has identified.
However, in order for the staff to complete its assessment, detailed technical information on many of these valves is required. The staff recognizes that some of this detailed information may not be available at the design certification stage of the review. However, pertinent assumptions that were used in determining valve design and reliability may be beneficial to the staff in helping it assess component operability and reliability. These assumptions should be provided where technical information is unavailable. Accordingly, provide the following information for the valves listed in Table, as appror a:
Information Requested on All Valves a.
What is the process fluid composition (water, steam, raw water, borated water, etc.) assumed for these valves for normal and accident conditions?
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What is the maximum temperature of the process fluid assumed for these valves?
c.
Provide the range of flow, pressure, and differential pressure assumed for these valves for both normal and accident conditions.
d.
Provide any available design information for these valves, e.g.,
the manufacturer and model number of the valve and actuator.
e.
Are there any design changes in the design of these valves as they are used in conventional nuclear generating stations?
f.
List the scope and 1 equency of planned periodic testing and preventive maintenanca.
i g.
Describe the planned qualification testing and its potential l
effect on replacement intervals.
l h.
Is a method of bonnet over-pressurization protection provided for l
normally closed gate valves?
j Information Requested on Air-Operated Valves The following information requests pertain to Valve Nos. PXS V108A/B, V014A&B, V015A&B, PXS V002A&B, V003A&B, and RC V004A/B/C/D.
- i. What elastomeric compounds will be used for the various 0-rings, seats, diaphragms, etc.?
i
- j. What lubricants will be used in the valve and solenoids? Provide the manufacturer and trade name, if available.
k.
Will the plant meet ISA Standard S7.3, " Quality Standard for Instrument Air," if instrument air is used with these valves?
l Information Requested on Motor-Operated Valves l
1.
What is the anticipated duty cycle of the valve actuator of the I
following valves: Valve Nos. PXS V117A/8, VllBA/B, V101, RC j
V001A/B/C/D, V002A/B/C/D, and V003A/B/C/D?
i Information Requested on Check Valves e
i The following information requests pertain to Valve Nos. PXS V016A/B, V017A/B, V006A/B, V007A/B, V119A/B, V120A/B, V122A/B, V123A/B, V124A/B, and V125A/B.
m.
What is the minimum opening pressure differential?
n.
What kind of position indication system is used?
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i Information Requested on Explosive Valves The following information requests pertain to Valve No. PXS V301A/B.
j o.
What is the manufacturer and model number of the valve and actuator?
p.
What is the predicted reliability based on operating experience and testing to date?
j PLANT SYSTEMS i
Air-Conditionino. Heatina, and Ventilation System I
410.93 Table 3.2-3 of the SSAR, " Classification of Components and Systems,"
does not list Classification of Structures.
Provide the classification of structures housing all corresponding specific subsystem (s) and component (s) identified in Sections 9.4.1-9.4.3 and 9.4.6-9.4.11 of the SSAR.
Also, Table 3.2-3 does not address the containment recirculation cooling system (VCS) and the turbine building ventilation system.
i Provide corresponding information in Table 3.2-3 for these subsystems.
Verify that all systems and components listed in Table 3.2-3 are complete for Sections 9.4.1-9.4.3 and 9.4.6-9.4.11 of the SSAR, l
including system ducting data.
In addition, the titles for the HVAC system in Sections 9.4.8 and 9.4.11 differ from those in Table 3.2-3 of the SSAR for VRS-and VHS-designated systems, respectively.
Clarify the discrepancies.
410.94 Provide up-to-date, half-size drawings for all HVAC systems identified in Section 9.4 of the SSAR, " Air Conditioning, Heating, 4
Cooling, and Ventilation System," (see Sections 9.4.1-9.4.3 and 9.4.6-9.4.11 of the SSAR), including the turbine building ventilation system that was not provided previously.
These drawings should include piping and instrumentation diagrams (P& ids), orthographic HVAC systems drawings, general arrangement drawings, and system flow diagrams showing pressure, temperature and flow data for all modes of operations, including normal, abnormal and emergency modes, as applicable.
For Q410.95-Q410.104, demonstrate how the AP600 design meets applicable GDCs by providing failure modes and effects analyses and other requested details, as identified in applicable SRP section(s) review methodology.
410.95 Provide a detailed specific conformance analysis for each of the HVAC subsystems in Sections 9.4.1-9.4.3 and 9.4.6-9.4.11 of the SSAR against the following guidelines of the Standard Review Plan i
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. i (NUREG-0800): Sections 3.4.1 for flood protection, 3.5.1.1 for protection against internally-generated missiles, 3.5.2 for protection against externally-generated missiles, and 3.6.1 for i
protection against high-and moderate-energy pipe breaks.
This analysis should be in greater detail than the information provided in Section 3.0 of the SSAR.
Q410.96-Q410.98 are followup questions to Q450.1 and Q450.2 relating to the adequacy of the habitability of the control room.
410.96 WCAP-13063 states that the nuclear island nonradioactive ventilation system (VBS) for the control room area ventilation system has been designed to be nonsafety-related (see Section 9.4.1).
An exception to Position C.1 of Regulatory Guide 1.29 has been taken. The staff concludes that it may be necessary to maintain the filtration fcaction of the CRAVS in order to meet GDC 19.
Therefore, justify the non-safety designation of this syst9m by demonstrating that GDC-19 can be met using a non-safety CRAVS 7 provide a safety-related CRAVS.
Demonstrate that the system is capable of withstanding the effects of earthquakes through conformance with the guidelines of Position C.1 of Regulatory Guide 1.29 in order to meet GDC 2.
Also, demonstrate how the VBS conforms with the guidance of Position C.2 of R.G. 1.29 for the nonsafety-related portions of the system.
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410.97 Demonstrate how the requirements of GDC 4, " Environmental and Missile Design Basis," are met by the VBS to maintain environmental conditions in the control room within the design limits of the i
essential equipment located therein for normal, transient, or i
accident conditions (see Section 9.4.1).
l 410.98 Section 9.4.2 of the SSAR, " Annex / Auxiliary Buildings Non-Radioactive HVAC System (VXS)," predominantly falls under the review guidelines i
of Section 9.4.3 of the SRP, " Auxiliary and Radwaste Area Ventilation i
System." WCAP-13053 states that the VXS conforms to Position C.2 of R.G. 1.29 and Positions C.1 and C.2 of R.G. 1.140.
Demonstrate how the VXS conforms with the guidelines of (1) Position C.2 of R.G.1.29 for the nonsafety-related portions of the system (to show how it meets GDC 2), and (2) Positions C.1 and C.2 of R.G. 1.140 (to show how it meets GDC 60).
Provide justification for taking an exception to Position C.1 of R.G.1.29 for the VXS since it also serves main steam components, electrical penetration and switch gear rooms, reactor trip switchgear rooms, M/G set room battery rooms, and battery charger rooms.
Provide justification for the provisions in the VXS design of only one 100-percer.' mcity air handling unit for the general area HVAC 6
subsystem and two 50-percent-capacity air handling units for the equipment room HVAC subsystem and main steam compartment versus redundant capacity units to satisfy the single failure criteria.
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s l Identify what pressurization level is maintained in the Annex I t
building with respect to adjacent buildings, and provide corresponding fresh-air make-up flow rates to provide this pressurization level.
i Provide an equipment operability evaluation for all of the MSIV compartment equipment to demonstrate that this equipment can i
withstand a 104*F temperature environment. Address the habitability concerns inside the MSIV ccmpartment for this elevated temperature.
i 410.99 Section 9.4.3 of the SSAR, " Radiologically Controlled Area Ventilation System (VAS)," partially falls under review guidelines of Section 9.4.2 of the SRP for the fuel handling area HVAC subsystem and Section 9.4.3 of the SRP for the Annex II and auxiliary building portion HVAC subsystems.
WCAP-13053 indicates that Westinghouse is taking an exception to Position C.1 of R.G.1.29 for the safety-related portions of the spent fuel pool area ventilation system, but other acceptance criteria are identified as " acceptable" to indicate conformance with GDCs 2, 60 and 61. Demonstrate that this system conforms with the guidelines of R.G.1.29 (to show it meets GDC 2), Position C.2 of R_G. 1.52 and Positions C.1 and C.2 of R.G. 1.140 (to show it meets GDC 60 with respect to the capability of the subsystem to suitably contrt.1 release of gaseous radioactive effluents to the environment),
and Position C.4 of R.G. 1.13 [to show it meets GDC 61 with respect to the subsystem's capability to provide appropriate containment, confinement, and filtering to limit releases of airborne radioactivity to the environment from the fuel storage facility urAer normal and postulated accident conditions (see Section 9.4.2 of the SRP for the fuel handling area HVAC subsystem)].
The P& ids, flow diagrams, component data, and system description should reflect corresponding conformance information as identified in Section 9.4.2 of the SRP, i.e., Table 3.2-3 should reflect equipment information for HEPA filter (s), adsorbers, single failure criteria design for equipment, isolation dampers, radiation detectors, etc.
WCAP-13053 indicates that the auxiliary and radwaste area ventilation systems conform with Position C.2 of R.G. 1,29 and Positions C.1 and C.2 of R.L. 1.140. Demonstrate that the Annex II and auxiliary building portion HVAC subsystems conform with the guidelines of R.G.
1.29 (to show it meets GDC 2) and Positions C.1 and C.2 of R.G. 1.140
[to show it meets GDC 60 with respect to the capability of the subsystem to suitably control release of gaseous radioactive effluents to the environment (see Section 9.4.3 of the SRP)).
Similar applicable details identified above for the fuel handling area should be provided for these HVAC subsystems.
410.100 WCAP-13053 indicates that information on the ESF ventilation system will be provided later.
Section 9.4.5 of the SSAR, "ESF Ventilation System," indicates timt this section is not applicable to the AP600 1
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design.
Sectior.s 9.4.6, " Containment Recirculation Cooling System (VCS)," and 9.4.7, " Containment Air Filtration System (VFS)," do not mention conformance with any particular SRP sections.
i The staff concludes that these two HVAC systems should be evaluated as ESF ventilation systems as part of the design-in-depth concept.
l Therefore, these systems should conform with the guidance of Section 9.4.5 of the SRP.
Demonstrate that these systems conform with the guidelines of (1) R.G. 1.29 (to show they meet GDC 2), (2) Position C.2 of R.G. 1.52 and Positions C.1 and C.2 of R.G. 1.140 (to show 1
l they meet GDC 60), and (3) NUREG/CR-0660 (to show they meet GDC 17).
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Also, demonstrate that these systems conform with GDC 4.
The system i
P& ids, flow diagrams, component data and system description should reflect corresponding details as identified in Section 9.4.5 of the SRP, i.e., Table 3.2-3 of the SSAR sWid reflect equipment information for HEPA filters, adsorbers, single failure criteria design for equipment, isolation dampers, radiation detectors, etc.
r 410.101 Section 9.4.8 of the SSAR, "Radwaste Building HVAC System (VRS),"
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q falls under the review guidelines of Section 9.4.3 nf the SRP. WCAP-13053 indicates that the auxiliary and radeaste area ventilation system conforms to Position C.2 of R.G. 1.29 and Positions C.1 and C.2 of R.G. 1.140.
Demonstrate that this system conforms with the guidelines of (1)
Position C.2 of R.G.1.29 for the nonsafety-related portions of the i
system (to show that they meet GDC 2) and (2) Positions C.1 and C.2 l
of R.G. 1.140 (to show that it meets GDC 60). Also, provide 2
justification for taking an exception to Position C.1 of R.G.1.29 for the VRS since it collects the vented discharges from potentially contaminated equipment and tanks, including the waste container processing chamber, compactor, glove boxes, dryers, and hoods, and l
d since it provides for radioactive par +':ulate removal and radiation monitoring of exhaust air prior to relt ase to the environment.
Identify what negative pressurization level is maintained in the radwaste building with respect to adjacent areas, and provide corresponding flow rates of fresh air make-up and exhaust to provide the above pressurization level.
Provide an equipment operability evaluation for those radwaste areas to demonstrate the system can withstand 104*F and 130*F temperature i
environments. Address the habitability concerns inside these areas j
for the elevated temperatures.
J Provide justification for the provisions in the VRS design of only two 50-percent-capacity air handling units for the supply air subsystem and two 50-percent-capacity exhaust filtration units for.
the exhaust subsystem versus redundant capacity units to satisfy the single failure criteria.
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~i f 410.102 Section 9.4.9 of the SSAR addresses the turbine building ventilation l
system.
WCAP-13053 indicates that the turbine area ventilation j
system conforms to Positions C.1 and C.2 of R.G. 1.29, Positions C.1
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and C.2 of R.G. 1.140, and GDC 5.
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Demonstrate that this system conforms with (1) the guidelines of Position C.1 of R.G.1.29 for the safety-related portions of the system and Position C.2 for the nonsafety-related portions of the system (to show that it meets GDC 2 with respect to the system being capable of withstanding the effects of earthquakes), (2) the guidelines of Positions C.1 and C.2 of R.G.1.140 (to show that it meets GDC 60 with respect to the capability of the system to suitably control the release of gaseous radioactive effluents to the environment), and (3) the requirements of GDC 5.
Also, provide (1) i design temperatures inside the room (s) and areas of the turbine l
building, (2) a detailed system description, and (3) system component data.
i 410.103 Section 9.4.10 of the SSAR, " Diesel Generator Building Heating and Ventilation System (VGS)," falls under the review guidelines of i
Section 9.4.5 of the SRP, "ESF Ventilation System." WCAP-13053 l
indicates that information will be provided on the ESF ventilation 1
system later. Section 9.4.10 of the SSAR does not address the system's conformance with the guidelines of Section 9.4.5 of the SRP.
I The staff concludes that this HVAC system should be evaluated as an l
ESF ventilation system as part of the design-in-depth concept.
l Therefore, this system should conform with the guidance of Section 9.4.5 of the SRP.
Demonstrate that this system conforms with the i
guidelines of (1) R.G. 1.29 (to show it meets GDC 2), (2) Position C.2 of R.G. 1.52 and Positions C.1 and C.2 of R.G. 1.140 (to show it j
meets GDC 60), and (3) NUREG/CR-0660 (to show it meets GDC 17).
t Also, demonstrate that this system conforms with GDC 4.
The system j
P&lDs, flow diagrams, component data, and system description should reflect corresponding details as identified in Section 9.4.5 of the SRP, as applicable.
Table 3.2-3 of the SSAR should reflect appropriate equipment information.
Provide an equipment operability evaluation for the diesel generator building areas served by VGS to demonstrate that they can withstand '
l 150*F temperature environment (as identified in Section 9.4.10 of the SSAR). Address the habitability concerns inside these areas for the i
elevated temperatures.
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Provide justification for the provisions in the VGS design of only l
two 50-percent-capacity roof-mounted exhaust fans for each diesel generator room and the normal ventilation system having only one 100-percent-capacity primary air handling unit versus fully redandant l
capacity units to satisfy the single failure criteria.
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410.104 Section 9.4.11 of the SSAR, " Health Physics and Hot Machine Shop HVAC System (VHS)," falls under the review guidelines of Section 9.4.3 of j
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' the SRP. WCAP-13053 identifies that the auxiliary and radwaste area ventilation system conforms to Position C.2 of R.G. 1.29 and Positions C.1 and C.2 of R.G. 1.140.
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Section 9.4.11 of the SSAR states that the VHS collects the vented i
discharge from potentially contaminated sumps and equipment in the area, maintains the control access area and hot machine shops at a negative pressure with respect to the adjacent Annex I building clean areas to prevent the unmonitored release of radioactive contaminants to the outside environment, and provides for radhattive particulate removal and radiation monitoring of exhaust air prior to release to the outside environment. Demonstrate that this system conforms with the guidelines of (1) Position C.2 of R.G.1.29 for nonsafety-related portions of the system (to show it meets GDC 2) and (2) Positions C.1 and C.2 of R.G. 1.140 (to show it meets GDC 60).
Identify what negative pressurization level is maintained in the control access area and hot machine shops with respect to adjacent clean areas of Annex I building.
Provide corresponding flows of fresh-air make-up and exhaust to provide this pressurization level.
Provide justification for the provisions in the VHS design of only two 50-percent-capacity air handling units for the supply air subsystem and two 50-percent-capacity exhaust filtration units for the exhaust air subsystem versus redundant capacity units to satisfy the single failure criteria.
Water Systems 410.105 Section 9.2.8 of the SSAR states that the turbine building closed i
cooling water system provides a cor tinuous supply of cooling water to turbine plant equipment at a tempercture of 95"F or less. The heat sink for the system is the SWS.
Section 9.2.1.2.2 of the SSAR states that upon loss of control air or electric power, the SWS valves to the CCWS heat exch::ngers fail to an open position while the turbine building closed cooling water system heat exchangers valves fail to a closed position.
Discuss the emergency preparedness considerations for maintaining the turbine building closed loop cooling capability if the SWS is degraded because of a weather change or SWS valve malfunction.
i EMERGENCY RESPONSE GUIDELINES i
440.32 TMI Action Item I.C.1 of NUREG-0737 requires that licensees prepare emergency operating procedures (EOPs).
The information in tne E0Ps should provide assurance that operator and staff actions are technically correct and the procedures are easily understood for normal, transient, and accident conditions.
In order to assist the plant owner-operator in preparing the E0Ps, emergency response guidelines (ERGS) should be provided as a part of the design certification application. The overall content, wording, and format l
i
, of procedures that affect plant operation, administration, maintenance, testing and surveillance must be in compliance with the guidance provided in NUREG-0737 and its Supplement 1.
The E0Ps should be function-oriented procedures to mitigate the consequences i
of the broad range of mitigating events and subsequent multiple failure or operator errors without the need to diagnose specific events.
i Provide a complete version of the AP600 Emergency Response Guidelines (ERGS).
The staff understands that the AP600 ERGS are based on the current Westinghouse Low Pressure ERGS (LP-ERGS), which the staff previously reviewed (see Generic Letter 83-22).
If Westinghouse proposes to submit a revised version of the LP-ERGS that reflect design-specific differences associated with the AP600, then describe these differences, including the technical bases for these 4
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differences (see Q620.50 for a related question regarding the ERGS).
1 620.50 The emergency response guidelines (ERGS), in conjunction with additional safety-significant operator actions derived from the AP600 probabilistic risk assessment (PRA), should be used as the basis for
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developing a minimum inventory of fixed and continuous displays, i
controls, and alarms relied on by the operator for transient and accident mitigation.
In addition to the ERGS requested in Q440.32,
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l develop the minimum inventory of displays, controls, and alarms j
described above based on the AP600 ERGS and appropriate PRA operator action insights, and provide this information using the following matrix:
COLUMN ITEM j
1 State whether the step is an ERG or PRA reference 2
State each high level ERG or PRA step (include each entry I
condition, caution, and note as a separate step).
3 Describe each primary operator action associated with the high level step separately (NOTE:
Primary operator actions are substeps of ERGS and should include any pertinent l
operator actions referenced from ERGS to System Operating Procedures, Integrated Operating Procedures, or other procedures).
1 4
List all operator information ar.d alarm requirements necessary to determine if each primary operator action is to be performed (e.g., RCS temperature, pressurizer pressure, containment pressure, and SG low level alarm).
5 List all operator control requirements necessary to perform i
each primary operator action (e.g., operator must select a pressurizer spray isolation valve and depress "open" switch).
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a j NOTE:
For items 6-13, place an asterisk (*) next to each display, control, alarm, or operator aid which is not expected to be 4
in the control room, and describe its intended location.
6 List all displays required by the operator to perform each primary operator action (e.g., narrow range SG level indication, wide range RCS temperature indication, narrow range prassurizer pressure indication, etc.).
7 List all controls required by the operator to perform each primary operator action (e.g., RCP start switch).
8 List all alarms required by the operator to perform each primary operator action (e.g., SG low level alarm, pressurizer high nressure alarm).
9 List all operator sids required by the operator to perform each primary operator action (e.g., nomgraphs, steam tables, computer-based aids, etc.).
10-13 List all displays, controls, alarms, and operator aids used for feedback to operators to ensure that each primary operator action has been accomplished or initiated appropriately.
14 Determine if each display, control, or alarm required to perform operator actions or to be used for feedback purposes l
is Class lE instrumentation and/or RG 1.97 instrumentation.
l TECHNICAL SPECIFICATIONS 630.6 In order to address the unique design features of the AP600, Westinghouse states that it i. considering including new limiting conditions for operation (LCOs) for the following passive, safety-related systems:
the automatic depressurization valves, the core makeup tanks, the passive residual heat removal systems (operating and shutdown), and the passive containment cooling system. Submit the LCOs for this equipment and these systems, or provide a schedule for doing so.
630.7 Section 16.1.1 of the SSAR states that the technical specification (TS) LCOs are provided in accordance with the criteria of the Commission's Policy Statement on Technical Specification Improvements, and are consistent with draft NUREG-1431, " Standard Technical Specifications (STS) - Westinghouse Plants," to the maximum possible extent, except where differences are justified because of design differences.
The staff has recently completed the resolution of comments on the improved STS that were issued to the Westinghouse Owners Group for proof and review on June 30, 1992. As a result, the draft NUREG-1431
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r i that Westinghouse used as the foundation for the AP600 application has changed substantially with the issuance of the Revision 0 STS.
Therefore, identify. specific differences in the proposed technical-specification requirements for the AP600 from those contained in the June 30, 1992 version of NUREG-1431.
630.8 For each of the topical reports referenced in the Westinghouse STS Bases (Revision 0) that are similarly used in the Chapter 16 TS submittal for the AP600, provide specific justification for applying the topical reports to the AP600 design consistent with the staff's requirements for adopting the individual topical reports.
630.9 Section 16.1.1 states that, in addition to excluding LCOs for systems classified as "non-safety systems" (as this classification is used for the AP600 design), other technical specification changes are included as a result of (1) redefining completion times and surveillance frequencies using a combination of deterministic criteria and PRA evaluation; (2) specifying shutdown completion times and mode definitions based on the availability of passive systems; and (3) specifying "TBD" for information required to be specified in the TS but where detailed design, equipment selection, or other efforts are incomplete.
Provide specific justification for the changes to the completion times and surveillance intervals in accordance with the basis for the staff's evaluation of related topical reports.
In addition, submit the "TBD" information on the technical specifications presented in Chapter 16 of the SSAR, or provide a schedule for doing so.
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I Table A Critical Valves For the AP600 -
(See Q210.28)
Valve No. and Description P&ID No.
PXS V013A/B (CMT outlet) LO gate valve, manual PXS M6 001 PXS V014A/B (CMT outlet) NC globe A0V PXS M6 001
[
PXS V015A/B (CMT outlet) NC globe A0V PXS M6 001 PXS V016A/B (CMT outlet) N0 tilt disc check valve PXS M6 001 PXS V017A/B (CMT outlet) N0 tilt disc check valve PXS M6 001 PXS V002A/B (CMT pressure line) NC globe A0V PXS M6 001 PXS V003A/B (CMT pressure line) NC globe A0V PXS M6 001 PXS V006A/B (CMT pressure line) N0 check valve PXS M6 001 PXS V005A/B (CMT pressure line) N0 gate MOV PXS M6 001 PXS V030A/B (condensate drain) NC globe SOV PXS M6 001 PXS V031A/B (condensate drain) NC globe 50V PXS M6 001 j
PXS V027A/B (accumulator outlet) NO gate MOV PXS M6 001
~
PXS V028A/B (accumulator outlet) check valve PXS M6 001 PXS V029A/B (accumulator outlet) check valve PXS M6 001 PXS V021A/B (accumulator N line) NO S0V PXS M6 001 2
PXS V042 (accumulator N line) NO A0V PXS M6 001 g
PXS V043 (accumulator N, line) N0 check valve PXS M6 001 PXS V045A/B (accumulator N line) NO S0V PXS M6 001 2
PXS Vll7A/B (IRWST to sump screen) NC gate MOV PXS M6 002 PXS V118A/B (IRWST to sump screen) NC gate MOV PXS M6 002 PXS V119A/B (IRWST to sump screen) NC check valve PXS M6 002 PXS V120A/B (IRWST to sump screen) NC check valve PXS M6 002 PXS V121A/B (IRWST injection) N0 gate MOV PXS M6 002
i Table A (continued)
Critical Valves For the AP600 (See Q210.28)
Valve No. and Description P&ID No.
PXS V122A/B (IRWST injection) check valve PXS M6 002 PXS V123A/B (IRWST injection) check valve PXS M6 002 PXS V124A/B (IRWST injection) check valve PXS M6 002 PXS V125A/B (IRWST injection) check valve PXS M6 002 PXS V102A/B (passive RHR HX) L0 gate valve PXS M6 002 PXS V103A/B (passive RHR HX) LO gate valve PXS M6 002 PXS V108A/B (passive RHR HX) NC globe A0V PXS M6 002 PXS V109A/B (passive RHR HX) L0 gate valve PXS M6 002 PXS V101A/B (passive RHR HX) NO gate MOV PXS M6 002 PXS V111A/B (hot leg H drain) NC globe valve PXS M6 002 2
PXS V130A/B (gutter loop seal) NO A0V PXS M6 002 PXS V231A/B (CMT isolation) check valve PXS M6.003 PXS V230A/B (CMT isolation) NC globe A0V PXS M6 003 PXS V232A/B (accumulator isolation) NC globe A0V PXS M6 003 PXS V301A/B (pH adj. tank injection line) NC squib valve PXS M6 004 PXS V315A/B (pH adj. tank, N system) NC vacuum breaker PXS M6 004 2
RC V004A/B/C/D (ADPs) NC 12" gate A0V RCS M6 001 RC V001A/B/C/D (ADPs) globe DC MOVs RCS M6 002 RC V002A/B/C/D (ADPs) gate DC MOVs RCS M6 002 RC V003A/B/C/D (ADPs) gate DC MOVs RCS M6 002 PC V002A/B (containment cooling line) N0 gate MOV PCS M6 001 PC V001A/B (containment cooling line) NC butterfly A0V PCS M6 001 SG V040A/B (main steam line) NO gate A0V SGS M6 001 J
.