ML20056H075
| ML20056H075 | |
| Person / Time | |
|---|---|
| Site: | 05200002 |
| Issue date: | 08/31/1993 |
| From: | Brinkman C ABB ATOM, INC. (FORMERLY ASEA ATOM, INC.), ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LD-93-131, NUDOCS 9309080190 | |
| Download: ML20056H075 (13) | |
Text
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?.
ABB ASEA BROWN BOVERI August 31, 1993 LD-93-131 Docket No.52-002 Document Control Desk U.S. Nuclear Regulatory Commission r
Washington, DC 20555
{
Subject:
Combustion Engineering Standard Safety Analysis j
Report - Design Certification, Amendment R l
Dear Sirs:
[
t This letter transmits thirty-seven (37)- formally printed copies i
of Amendment R to the Combustion Engineering Standard Safety Analysis Report - Design Certification (CESSAR-DC). and the
{
affidavit, as required by 10CFR50. 4 (b) and 10CFR50. 3 0 (b).
l Amendment R includes revisions previously transmitted as draft i
marked-up pages of CESSAR-DC as summarized in Attachment 1.
If you have any questions, please call me or Mr. Stanley-Ritterbusch of my staff at (203) 285-5206.
Very truly yours, r
COMBUSTION ENGINEERING, INC.
2 I....__..
C.
B. Brinkman l
Acting Director l
Nuclear Systems Licensing j
ser/lw
Attachment:
As Stated
Enclosure:
As Stated l
cc:
w/o enclosures:
P. Lang (DOE)
J. Trotter,(EPRI) n t@ g 070080 g
i ABB Combustion Engineering Nuclear Power-g L
j comtiusion Engmenna. trc..
1000 nospeci em naaa Tencone goams 1911 Post Ofice Bos 500
. Far (203 ?S5 9512 9
190933 wineso. C.onnecicet 06095 0500 Temu 99297 COMBEN WSDR-A ADOCK 05200002 TN PDR J L
Docket No.52-002 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of:
)
)
Combustion Engineering, Inc.
)
)
Standard Plant Design
)
APPLICATION FOR REVIEW OF
" COMBUSTION ENGINEERING STANDARD SAFETY ANALYSIS REPORT-DESIGN CERTIFICATION" Robert E. Newman, being duly sworn, states that he is the Pre:Jdent, ABB Combustion Engineering Nuclear Systems, of Combustion Engineering, Inc.; that he is authorized on the part of said corporation to sign and file with the Nuclear Regulatory Commission this document; and that all statements made and matters set forth therein are true and correct to the best of his knowledge, information, and belief.
COMBUSTION ENGINEERING, INC.
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f i
n By:
=
Robert E. Newman President ABB Combustion Engineering Nuclear Systems Subscribed and sworn to before me this SI dday ofb6(cd
,1993.
V N
I!M1
/
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Notary Public 4
My Commission Expires: 3-31-7M
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ATTACIIMENT 1 CESSAR-DC Amendment R Over iew t
Chapter I -Introduction and General Description of Plant 1.
Sections 1.2.4.2 and 1.2.4.5 were revised to refer to the Shutdown Cooling System (SCS) and indicate that the SCS can be used as a back-up to the CS pumps and heat exchangers.
2.
Sections 1.2.9 and 1.6 were revised to incorporate editorial changes.
3.
Table 1.8-3 was revised to incorporate editorial changes.
4 Table 1.8-1 was revised to incorporate Reg. Guide 1.160 5.
Table 1.10-1 was revised to include new COL applicant items referenced in the text of CESSAR.
Chanter 2 - Site Envelone Characteristics 1.
Sec' ions 2.3.5 and 2.5 and Tables 2.0-1,2.3-2,2.5-1, and 2.5-2 were revised for editorial changes and to include revised digitized spectral ordinate data.
Chapter 3 - Design of Structures. Components. Equipment and Systems 1.
Chapter 3 was revised to incorporate editorial changes, Integrated Consistency Review comments, and the final resolutions to the following DSER items:
Confirmatory Item:
3.9.6.1-1 Open Items:
3.9.6-1 3.9.6.2-2 3.9.6.2-5 3.9.6-2 3.9.6.2-3 3.9.6.2-6 3.9.6.2-1 3.9.6.2-4 3.9.6.2-7 These DSER responses incorporate technical agreements made at the Inservice Testing meeting held June 23-25,1993 at ABB-CE's Windsor offices.
2.
Table 3.9-15 (IST Plan) and Figure 3.9-16 were revised to incorporate comments on inservice testing of safety related valve.; & pumps per IST meeting with NRC and Brookhaven National Labs on June 23-25,1993 and makt editorial changes as follows (numbers in [ brackets] refer to meeting note item numbers):
[2.1]
Table 3.9-15 was revised to add relief and safety valves.
[2.2]
Added reverse flow test for each category A/C valve.
[2.3]
Reduced number of quarterly tested valves by recategorizing and design changes.
AMEND _R. sum 1
August 31,1993 (11:00am) i
i
[2.4]
Resolved Open Items 3.9.6.2-4 & 3.9.6.2-5 by discussing MOV and POV continuing design basis capability.
{2.5]
Resolved Open Item 3.9.6.2-1 by clarifying the method of verifying full j
stroke of affected check valves referencing configuration 15.
l
[2.6]
Addressed basis for placing CVCS and spent fuel pool valves in Table 3.2-2.
l 1
[2.7]
Defined " safety related" with respect to IST Plan contained in Sect. 3.2.1.
[2.8)
Resolved Open Item 3.9.6.2-7 by listing reactor pressure isolation valves, their testing requirements, describe reactor pressure isolation function, and revise P& ids.
[2.9]
Resolved Confirmatory Item 3.9.6.1-1 to clarify method of suction pressure calculation for sump pumps for service water pumps.
L.10]
Clarified OM-10 treatment of category A valves.
i 2
[2.11]
Clarified refueling outage valve testing schedule requirements.
l
[2.12]
Clarified OM-10 requirements for cold shutdown testing.
[2.13]
Table 3.9-15 was revised to deleted discharge pressure requirements for positive displacement pumps.
[2.14]
Table 93.1-1 was revised to include air operated valves in IST Plan.
l
[2.15]
Table 3.9-15 note (i) was revised to clarify usage of typical test j
configuration by plant system designers.
[3.1.1] Added missing safety components related to CESSAR to IST Plan.
[3.1.2] Clarified requirements for 10CFR50 Appendix J Type C testing of valves.
l
[3.13] Table 3.9-15 was revised according to required position (s) of valves performing safety functions.
i
[3.1.4]
Provided justification in notes of Table 3.9-15 for using Technical l
l Specification LCOs to perform quarterly testing.
[3.1.5] Table 3.9-15 was revised to require "RR" fer certain valves.
[3.1.6] No change - not practical to design SIT outlet check valves to full stroke under partial flow conditions.
[3.1.7] Table 3.9-15 was revised to reflect testing philosophy for SI pump valves.
[3.1.8] Table 3.9-15 note (i) was revised to define pump and valve test configuration.
[3.1.9] Table 3.9-15 was revised to recategorize valves.
[3.2.1] Added minimum flow check, CVCS cooling header, surge tank vacuum breaker, and CCW drain valves to IST Plan.
[3.2.2]
Same response as [3.1.8].
[3.23]
Same response as [3.1.8] and revised Figure 3.9-16. Resolved Confirmatory Item 3.9.6.1-1 by revising Section 3.9.6 to clarify the sizing of miniflow lines.
[3.2.4]
Section 3.9.6.1 was revised to use NRC staff guidance in using pump curve evaluations instead of single repeatable parameter test point method described in OM-6.
[3.2.5]
No change - stroke testing frequency for affected valves will remain as originally proposed in the IST Plan - cold shutdown.
j
[33.1]
Same response as [3.2.4].
[33.2] Same response as [3.1.8].
[3.4.1] Table 3.9-15 was revised to add CVCS components to IST Plan.
[3.4.2] Table 6.2.4-1 was revised to reflect current CVCS letdown line inservice tested valves.
[3.5.1] Table 93.1-1 was revised to add unnumbered AOVs at the discharge of the AHUs to the IST Plan.
AMEND _R. sum 2
August 31,1993 (11:00am)
i
[3.5.2]
Same response as [3.1.8].
[3.5.3]
Same response as [3.1.8].
{3.5.4]
Same response as [3.1.8].
[3.5.5] Tables 3.9-15 and 6.2.4-1 were revised to reflect the containment penetration configuration specified in Figures 6.2.4-1 and 9.2.9-1.
[3.5.6] Revised notes 32 and 39 to clarify that the NCW CIVs and non-essential CCW isolation valves will be quarterly stroke tested except during summer months.
[3.6.1] Table 3.9-15 was revised to include EFW turbine governor and trip valves and pump discharge crossover manual valves.
[3.6.2] Clarified the reverse flow testing of EFW pump valves.
[3.7.1]
Figure 10.4.8-1 was revised in Amendment N to oe consistent with the IST
~
Plan.
t
[3.7.2] Added reverse flow testing to the IST Plan for containment isolation and relief valves.
[3.8.1] Added MSSVs, FW check valves, and ADV block valves to the Table 3.9-15.
[3.8.2]
Section 10.4.7.2.7 was revised to delete the leakage requirements for MFIVs and selected SG valves.
[3.8.3] Table 9.3.1-1 was revised to relabel the MSIV bypass valves correctly.
[3.9.1]
No change - the spent fuel cooling pumps and associated valves should not be included in the IST Plan.
[3.10.1] Table 3.9-15 was revised to reflect the containment floor drain and reactor cavity sump pumps' combined discharge line penetration configuration.
[3.10.2] Table 3.9-15 was revised to use test configuration 14 instead of 15 and deleted note 33.
[3.10.3] Same response as [3.10.2].
[3.10.4] Table 3.9-15 was revised to require quarterly testing of the reactor and diesel building sump pumps and deleted note 34.
[3.11.1] Table 3.9-15 was revised to add pressurizer spray, reactor vessel closure t
head leakoff, RCP controlled bleedoff, pressurizer relief valves.
[3.11.2] Table 3.9-15 was revised to recategorize the rapid depressurization and i
vent valves.
[3.12.1] Table 3.9-15 was revised to add multiple check valves associated with the fuel oil storage tanks and fuel oil pump and booster pump associated valves.
[3.12.2] Table 3.9-15 was revised to add note 35 for the diesel air start system i
[3.12.3] Table 3.9-15 was revised to delete stroke test requirements for the diesel generator starting air valves.
[3.12.4] Table 3.9-15, note 35, was revised to clarify the testing of the starting air l
l tanks.
[3.12.5] No change - the diesel support systems will not be included in the IST Plan because the design and preventative measures are discussed in other sections.
[3.12.6] Revised test configuration 9 in Figure 3.9-16 to delete the use of pressure inarumentation to determine reverse flow and leakage testing of check valves.
[3.13.1) Table 3.9-15 was revised to add recombiner outlet check valves.
AMEND _R. sum 3
August 31,1993 (11:00am) t
i
. 3.
Chapter 3 was revised to provide reference to and descriptions for computer codes used in the Nuclear Island structures soil structure interaction analysis, editorial
~
changes, and provide reference to options available for seismic analysis by response spectrum method.
l 4.
Table 3.2-1 revised to incorporate comments from Fred Allenback of the NRC based on coi..ersations on 5/11-93 and 5/12-93.
5.
Section 3.3 was revised to delete COL applicant items for verification of bounding tornado loadings and wind velocity and clarify basis of design wind velocity.
)
i 6.
Figures 3.7-3, -4, -5, -6, -7, -8, and -9 were revised to incorporate editorial changes.
l 7.
Figures 3.7B-46 through -88 were revised to correct figure titles consistent with the List of Figures.
8.
Table 3.2-2 was revised to incorporate integrated consistency review comments and l
make appropriate changes to incorporate ISLOCA design improvements.
9.
Added Appendix 3.7D and Figures 3.7D-1 through 41 to include sample in-structure t
response spectra.
10 Appendix 3.9A was revised to incorporate miscellaneous editorial changes and to provide additional technical detail for the analysis methods and acceptance criteria for piping, supports, and HVAC ductwork.
t
- 12. Section 3.10 was revised to provide additional detail to describe methods and procedures for qualification of mechanical and electrical equipment, and delineate COL administrative items to support the equipment.
- 13. Figures 3.11A-4B,-5B were revised to relabel the curves for Gamma and Beta which were inadvertently mis-labeled in Amendment Q.
Chanter 4 - Reactor No changes Chapter 5 - Reactor Coolant System and Connected Systems i
1.
Figure 5.1.3-1 was revised to incorporate comments from the Imegrated Consistency Review and modify the drawing to agree with the System 80+ design. The revision deleted the Cold Leg SI nozzles, added DVI nozzles and added an additional DVI nozzle.
2.
Section 5.2.L2 and Table 5.2-3 were revised to reflect response to DSER Open i
Item 5.2.1.2-1.
l AMEND _R. sum 4
August 31,1993 (11:00am) f
.3.
Sections 5.3.1.2,.4,.6,.7, 5.3.2, Figure 5.3-1 and Figure 5.3.7 were revised to include changes resulting from the Integrated Consistency Review and add of COL Applicant item to verify plant specific materials to those delineated in Section 5.2.3.1.
4.
Section 5.3.1.4 was revised to provide CESSAR text incorporating resolution of DSER Open Items 5.2.3-10 and 5.3.1-5.
5.
Section 5.4.7.4 was revised to incorporate test and inspections resulting from Tier 1 commitments.
l 6.
Appendix 5A was revised to incorporate Integrated Consistency Review comments and editorial changes.
l 7.
Appendix 5D was revised to reflect the responses to follow-up questions on DSER Open Item 5.4.3.1-1 and RAI 440.209.
l Chapter 6 - Engineered Safety Features 1.
Chapter 6 was revised to incorporate integrated consistency review comments and i
l editorial changes.
l l
2.
Section 6.3.3.5 was revised with editorial changes in response to the Integrated Consistency Review. Most of this section was deleted and moved to Appendix 15A.
3.
Figure 6.2.1-1 was revised to correct editorial changes.
3.
Table 6.2.4-1 was revised to incorporate integrated consistency review comments.
l 4.
Table 6.4-1 was revised to incorporate the control room dose from an additional feedwater line break scenario and include the new dose for other DBAs associated with a revised inputs / safety analysis.
5.
Figure 6.2.4-1 was revised to incorporate changes in the containment isolation valve configurations, resolve integrated consistency review comments, and incorporate changes resulting from the NRC IST Review Meetings.
6.
Section 6.5.1 was revised to specify trisodium phosphate dodecahydrate for post accident pH control.
7.
Figures 6.3.3.2-3B,-8F,-9F,-12 were revised to incorporate editorial changes.
i 8.
Figures 6.5-4 and 6.5-5 were revised for results for the DBA LOCA containment mixing rate and DBA LOCA spray LAMBDA, respectively.
Chapter 7 - Instrumentation and Controls 1.
Table of Contents was revised to reference IEEE Std. 323-74 for Section 7.1.2.5.
AMEND _R. sum 5
August 31,1993 (11:00am)
2.
Section 7.2.1.1.2.5 and the references to Section 7.2 were revised to provide re3olution to DSER Open Item 4.4.4-1 regarding the software design and change procedures for the CPCs and CEACs.
3.
Table 7.2-5 was revised to reflect comments resulting from the Integrated Consistency review.
4.
Figure 73-17 was revised to incorporate editorial changes.
5.
Section 7.7.1.6.3 was revised to provide descriptions to several loose parts monitoring system instrument tests.
6.
Appendix 7A was modified to reflect recent staff comments on the thermal-hydraulic analysis related to the I&C diversity issue.
4 Chanter 8 - Electric Power 1.
Section 8.1 was revised to correct typographical errors.
2.
Section 8.3.1.1.4 was revised to incorporate resolution to DSER Open Item 20.2-20.
Chapter 9 - Auxiliary Systems 1.
Sections 9.2.1.2.1.3 and 9.2.1.4 were revised to incorporate in-service inspection l
requirements for station service water piping.
r 2.
Seetions 9.2.1.2.1.2,9.2.1.2.2.3,9.2.2.2.1.1,9.2.2.2.1.2,9.2.2.2.2.4, and Table 9.2.2-4 were revised to specify the safety grade shutdown requirements for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> cooldown and the CCW heat exchanger outlet temperature for the final shutdown cooling at 100 F.
3.
Table 9.2.2-3 was revised to incorporate changes in the typical CCW heat loads specified for the shutdown cooling heat exchangers, spent fuel pool cooling heat exchanger, gas stripper, and containment spray heat exchanger for the various CCW system operating modes.
4.
Table 9.3.1-1 was revised to add additional descriptions to air operated valve service, safety related active functions, and add additional valves to the listing.
l These additions incorporate comments provided by the NRC IST consultant.
Additionally, the MSIV were deleted from the table to be consistent with the current type of MSIV which is a process flow medium operated valve not requiring
)
air as a motive force.
5.
Section 9.5.4 was revised to incorporate comments resulting from the Tier 1 review meetings and integrated consistency review meetings by deleting the feel oil recirculation system interlocks with LOCA.
6.
Sections 9.5.4.3 and 9.5.4.4 were revised to incorporate inservice inspection re.quirements for the diesel generator fuel oil piping.
AMEND _R. sum 6
August 31,1993 (11:00am)
Chanter 10 - Steam and Power Con ersion System i
-1.
Chapter 10 Table of Contents was revised to delete a note which referenced future Chapter 10 updates to include baseline data from Chapters 6,15, and 19 analyses.
(Note: The design certification effort in these areas has progressed to the extent that this note is no longer needed.)
j l
2.
CESSAR Figure 10.1-2 was revised to change type of MSIV and symbol to be consistent with process flow medium operated valve, revise penetration numbers to agree with Figure 6.2.4-1, and correct valve fail positions.
2.
Sections 10.3 and 10.3.2.3.3.1 were revised to incorporate technical details and changes for a process flow medium operated MSIV and a solenoid operated ADV.
3.
Section 10.4.1.3 was revised to clarify the Turbine Building flooding issues resulting from Tier 1 review.
4.
Section 10.4.8 was revised to incorporate resolution / comments from the NRC IST review (Open Item 3.9.6-1) by adding the A! ternate Feedwater Actuation Signal (AFAS) to the steam generator blowdown containment isolation valves.
5.
Table 10.4.9-5 was revised for division references and power channels for EFWST l
instrumentation.
j l
l Chanter 11 - Radioactive Waste Managemelg 1.
Section 11.1 was revised to incorporate the tritium production rate for core power increase and incorporates Integrated Consistency Review comments, general revisions to reflect YGN (issued supporting documentation), and added analysis description to verify Reg. Guide 1.143 commitments.
2.
Sections 11.2 and 11.4 were revised to add an analyses description to verify compliance to Regulatory Position C.5 of Reg. Guide 1.143.
3.
Section 11.3 was revised for editorial changes io the text of Amendment O which provided closure of DSER Open Item 11.1-1.
I 4.
Section 11.5 was revised for editorial changes to text added in Amendment Q which provided closure of DSER Confirmatory Items 11.5-1 and 11.5-2.
Chapter 12 - Radiation Protectim I
No changes l
Chapter 13 - Conduct of Operations l
No changes AMEND _R. sum 7
August 31,1993 (11:00am)
Chanter 14 - Initial Test Program 1.
Sections 14.2.1.12.1.39 and 14.2.12.4.23 were revised to provide DSER Open Item resolution for the Safety Depressurization System and Natural Circulation Test.
Chapter 15 - Accident Analyses L
Chapter 15 was revised to incorporate editorial changes throughout in response to the Integrated Consistency Review.
2.
Section 15.1.4 was revised to incorporate integrated consistency review comments and the reunalysis of the IOSGADV event.
3.
Section 15.1.5 was revised to describe changes in the assumptior.s for LOOP as turbine valve closure, provided additional discussion of CEA worth, and revise Table 15.1.5-12 to delineate changes to Mass Releases based on analysis changes.
4.
Sections 15.2.1-4,6, & 7 were revised to incorporate integrated consistency review comments.
6.
Section 15.3, figures, and, tables were revised to describe changes in the analysis for RCS pressure, LOOP time assumptions, delays, and other initial conditions, and revise doses resulting from these changes.
7.
Sections 15.4.1,2,3, & 6 were revised to incorporate integrated consistency review comments to correct the descriptions of Fa on the initial conditions table and make minor editorial changes.
8.
Section 15.4.8 was revised to update to radiological consequences (table 15.4.8-5).
9.
Section 15.5.2 was revised to describe the charging pump control system more accurately.
- 10. Section 15.6.5 was revised to describe changes in the analysis assumptions for LOOP, control ventilation and provide changes in the analysis results. Existing tables and figures were revised and Table 15.6.5-2 was added.
- 11. Section 15.7A.2 was revised to clarify restrictions on heavy loads in the containment and fuel building.
- 12. Appendix 15A was revised to incorporate integrated consistency review comments l
and editorial changes and revised computer code references.
l Chanter 16 - Technical Soecifications i
1.
Technical Specification 3.5.2 was revised to incorporate the resolution to comment j
3.1.7 from the June 23 through 25,1993 IST mecting with the NRC.
AMEND R. sum 8
August 31,1993 (11:00am) i
i i
Chapter 17 - Ouality Assurance Procram 1.
Section 17.1 was revised to incorporate comments from Fred Allenback of the NRC based on conversations on 5/11-93 and 5/12-93.
2.
General revision to DRAP Program text to incorporate comments from internal i
review and M. POLICH of the NRC on 5/7/ & 5/10/93.
3.
Sections 17.3, Fig.17.3-1, & Table 17.3-1 were revised to incorporated integrated review changes.
Chapter 18 - Human Factors Engineerine 1.
Figure 18.7.3-2 was revised to incorporate editorial changes.
Chapter 19 - Probabilistic Risk Assessment 1.
Sections 19.-2.11 and 19.11.1 and Table 19.33-1 and 19.3.3-2 were revised to incorporate editorial changes, correct typographical errors for mean occurrence value.
2.
Figure 19.4.13-1 was added because it was inadvertently deleted by Amendment P.
3.
Section 19.4.3.3.1 was revised for the typographical errors.
4.
Tables 19.5-2 and 19.5-3 were revised to list additional components in the steam and power conversion system and to revise descriptions of components for clarity.
These changes incorporate resolution to DSER Open Item 19.1.2.1.1.5-2.
5.
Table 19.5-5 was revised to include operator action probability for blowdown system valves and turbine bypass valves. These changes incorporate resolution to DSER Open Item 19.1.2.1.1.5-2.
6.
Appendix 19.5A was revised to include changes to Basis Event Probability calculation worksheets, make editorial changes, provide technical backup for failure probability assumptiens, and include new worksheets for several blowdown system components. These changes incorporate resolution to DSER Open Item 19.1.2.1.1.5-2.
7.
Table 19.63.1-1 was revised to list new assignments for the Blowdown System valves. These changes incorporate resolution to DSER Open Item 19.1.2.1.1.5.2.
8.
Sections 19.6.3.7.2.1 and 19.6.4.5.2.1 were revised to justify assumptions for LSSB and SCTR events and failure of operator to maintain steam generator level.
j Additionally Section 19.6.4.5.2.1 was revised to justify isolation of ruptured steam generator. These changes incorporate resolution to DSER Open Item 19.1.2.1.1.5.2.
I AMEND _R. sum 9
August 31,1993 (11:00am)
. 9.
Table 19.6.-
i was revised to include new results for dominant cutsets for failure to isolate a ruptured steam generator. These changes incorporate resolution to DSER Open Item 19.1.2.1.1.5.2.
- 10. Figure 19.6.4.5-2 was revised to include new fault trees for failure to isolate a i
ruptured steam generator. These changes incorporate resolution to DSER Open Item 19.1.2.1.1.5.2.
- 11. Section 19.7.3.2 was revised to incorporate editorial changes and revise the fire j
event initiating frequency calculation. These revisions incorporate comments for N.
Saltos of the NRC faxed to ABB on 5/27/93.
1
- 12. Table 19.7.3.1-6 was revised to include reference to CESSAR-DC figures used in the fire analysis. These revisions incorporate comments for N. Saltos of the NRC faxed to ABB on 5/27/93.
- 13. Table 19.7.3.2-1 was revised to delete reference to the Control Room. These revisions incorporate comments for N. Saltos of the NRC faxed to ABB on l
5/27/93.
l l
- 14. Appendix 19.8A, Table 2.4-2 was revised to incorporate editorial changes to abbreviations, items, and indicator / alarm descriptions.
l
- 15. Appendix 19.8A, Section 2.4.3.1.2 was revised to clarify the justification for the dedication for the SCS to the DHR function.
- 16. Appendix 19.8A, Table 2.4-3 termination point 2 was deleted.
i l
- 17. Sections 19.9.2.8, 19.9.3.2, 19.9.2.13, and Tables 19.9.1-2,19.9.1-4,19.9.2.13-1, and l
19.9.2.8-6 were revised to include new LOOP, ATWS, and fire related scenarios.
These changes incorporate resolution to DSER Confirmatory Items 19.1.2.1.1.3-3 and 19.1.2.1.1.2-2 and Open Item 19.1.2.1.1.3-5.
- 18. Figures 19.10-3 and 19.10-4 were added to address change in core damage frequency for RCP Failure Rates.
- 19. Section 19.11 was revised to incorporate NRC review comments and Integrated Consistency Review comments.
- 20. Section 19.15.2.1.2 was revised to correct typographical errors and minor changes in the listing of dominant accident sequences and accident sequence frequency and add new LOOP accident scenario description and frequency.
- 21. Tables 19.15.2-1,19.15.3-2, and 19.15.4-2 were revised to include new data for core damage frequency contributors. This incorporates resolutions to DSER Confirmatory Items 19.1.2.1.1.3-3 and 19.1.2.1.1.2-2. These revisions resolve comments from N. Saltos of the NRC faxed to ABB on 5/27/93.
1 AMEND _R. sum 10 August 31,1993 (11:00am) l I
, Appendix A - Closure of Unresolved and Generie Safety Issur.s 1.
. Appendix A Issue B-56 and References to Appendix A were revised to incorporate the resolution to DSER Open Item 20.2-20.
2.
Appendix A, Issue 24 was revised to reference IEEE Std. 323-74.
3.
Appendix A Issue II.K3, sub-issue 2 was revised to incorporate the resolution of I
DSER Open Item 20.3-1.
t I
i AMEND R. sum 11 August 31,1993 (11:00am) l l
l
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