ML20149G962

Forwards Description of 880215 Amend 68 to Fsar,Consisting of Revised Effective Page List for Affected Portions,Revs, Additions,Updates & Editorial Changes.Summary of Significant Changes of Amend Listed

ML20149G962
Person / Time
Site:	Comanche Peak
Issue date:	02/15/1988
From:	Counsil W TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
TXX-88229, NUDOCS 8802190034
Download: ML20149G962 (90)

Text

{{#Wiki_filter:l 6 LM = '___ d Log # TXX-88229 _-r r File # 10010 Ref # 10CFR50.34(b) $$5Si8dm February 15, 1988 U. S. Nuclear Regulatory Commission ATTN: Document Control Deck Washington, D. C. 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) DOCKET NOS. 50-445 AND 50-446 FSAR AMENDMENT 68 DESCRIPTION Gentlemen: Amendment 68 to the CPSES FSAR was transmitted to you under a separate cover letter, TXX-88228, dated February 15, 1988. Amendment 68 provides updates, revisions, additions and editorial changes (including the continuation of the process of reprinting the FSAR in the computerized format) as well as a revised Effective Page List for the affected portions of the FSAR. A s'ummary of the more significant changes contained in this amendment (listed by FSAR chapter) is provided below.

1.0 INTRODUCTION

AND GENERAL DESCRIPTION OF PLANT The 1A(N)/1A(B) sections have been revised to provide updates to'the TV Electric position for the following Regulatory Guides: 1 1) Regulatory Guide 1.25 2) Regulatory Guide 1.38 3) Regulatory Guide 1.75 2.0 SITE CHARACTERISTICS l Sections 2.4 and 2.5, specifically relating to hydrology, geology and seismology, have been clarified or updated to include the information developed from the validation of civil / structural design criteria parameters (i.e. bearing capacity, lateral loads, settlement of Category I structures and all dynamic soil and rock properties). 8802190034 880215 PDR ADOCK 05000445 A DCD k O f monk ouve surro a st oenu, rum mot

E TXX-88229 February 15, 1988 Page 2 of 6 3.0 DESIGN OF STRUCTURES. COMPONENTS. E0VIPMENT. AND SYSTEMS l Section 3.6B has been revised to: 1) describe the new methodology used i to determine jet impingement loads for high energy and moderate energy line breaks, 2) delete reference to arbitrary intermediate breaks, 3) redefine inside containment break exclusion area (BEA) piping to eliminate the break exclusion area, and 4) revise the "stress node and break location" figures to update the redefined containment break exclusion area piping and incorporate the revised break locations. Section 3.7N has been revised to reflect the results of Westinghouse seismic qualification reports on the reactor internals. Section 3.7B has been corrected to reflect the new seismic t qualification for the Service Water Intake Structure (SWIS) and Category I Tanks based on reanalysis performed as part of the design l validation for CPSES. For the SWIS and Category I Tanks a revised i Amplified Response Spectra is required. Also included are various ) changes to the text, tables, and figures which reflect the reanalysis performed as part of the design validation for CPSES. Section 3.8.1 has been revised to include several clarifications, corrections, and revisions. The applicable codes, standards, and specifications were changed to provide the,orrect applicability dates and sections for: 1) concrete materials, 2f punching shear for reinforced concrete, 3) thermal stresses, 4) structural steel, and 5) containment liner and penetrations. Changes for the liner seam welds allow the use of alternate non-destructive examination methods and acceptance criteria. The description of the design procedures was corrected to reflect the reanalysTs._and analysis performed as part of the design validation for CPSES. The requirement for ultrasonic testir.; of the liner plate in the vicinity of attachments was deleted. Section 3.8.2 has been revised to correct ASME Code applicability dates and sections used for the construction of the containment liner and penetrations and to revise the load equations and acceptance criteria to be consistent with Regulatory Guide 1.57. Section 3.8.3 has been revised to include se al changes. The ~ discussion of the polar crane derailment in regard to load combinations has been clarified. The description of the design and analysis procedures was corrected to reflect the reanalysis performed as part of the design validation for CPSES. The anchorage requirement for reinforcing steel (900 hook) was changed to allow the required length to be based on testing. Section 3.8.4 has been revised to include several changes. The description of the design and analysis procedures was corrected to reflect the reanalysis performed as part of the design validation for CPSES. The anchorage requirement for reinforcing steel (900 hook) was changed to allow the required length to be based on testing. Alternative design criteria were added for brackets and corbels when considering shear stress.

TXX-88229 ~ February 15, 1988 ^ Page 3 of 6 Section 3.8.5 has been revised to clarify the seismic gap requirements between the foundation mats of seismic Category I structures. Section 3.9N has been revised to correct the acceleration levels for Westinghouse supplied active valves, and to conservatively revise the damping used in the seismic analysis of the reactor coolant pump. Table 3.98-10 has been revised to expand the list of active valves. Section 3.llN has been revised to describe the environmental design of mechanical and electrical NSSS equipment. Changes reflect: 1) the effects of the revised plant service conditions (i.e. the effects of temperature, pressure, radiation etc.) on existing equipment, 2) the incorporation of the new definition of mild environment into the qualification program, 3) updates to the section to include the latest revisions of applicable references and 4) the present status of the CPSES qualification effort (i.e. work completed). 5.0 REACTOR COOLANT SYSTEM Section 5.4 has been revised to reflect the revised RHR cooldown analysis performed as part of the CPSES design validation program, j 6.0 ENGINEERED SAFETY FEATURES Section 6.2 has been revised to: 1)updatetheNPSHcurvesforlthe-containment spray pumps and provide associated text changes, 2) provide additional descriptions of the functioning of several, containment isolation valves and 3) update the Tables associated with containment isolation valves to reflect as built conditions. Section 6.3 has been revised to correct the method by which the accumulator motor operated isolation valves are locked closed during plant shutdown. Also revised the list of ECCS motor operated valves. Section 6.4 has been revised to add a statement that a concurrent release of toxic gas due to a seismic event and a radiological release due to a LOCA is not considered in the design basis. Also a description of the analysis for the release of refrigerant in the control room has been added. Table 6.4-6 has been revised based on Westinghouse "Radiation Analysis Design Manual, Standard Plant Model 412. " Revision 3. Section 6.5 has been revised to provide a new opening time for the containment spray pump isolation valve. 7.0 INSTRUMENTATION AND CONTROLS Chapter 7 has been revised to reflect the current plant design as a result of the design validation program. Changes also include updates, corrections and clarifications. ._,1

TXX-88229 ~ 3 February 15, 1988 Page 4 of 6 8.0 ELECTRIC POWER Section has been issued with various updates, clarifications, typographical and editorial corrections. A major portion of the clarifications concern the separation of non-Class 1E and Class 1E circuits at CPSES based on the design validation program. A new table identifying non-Class IE equipment connected to Class IE power buses has been provided. The containment electric 11 penetration protection description and 125 VDC battery load tables have been updated. Two additional splice applications have been added to Appendix 8A. 9.0 AUXILIARY SYSTEMS Chapter 9 has been revised to include:

1) corrections to the design criteria applicable to spent fuel pool cooling and purification,

2) revisions to the SSW and CCW temperatures and time to cooldown on RHR, 3) revisions to the dercription of the CCW control circuitry,

4) the deletion.of the plant vent stack radiation monitor from the primary vent stack exhaust, and 5 ) revisions to the figures for the new fire water supply system.

10.0 STEAM AND POWER CONVERSION SYSTEM Section 10.4 has been revised to: 1) provide new guidelines for chlorination, 2) correct the usable volume of the condensate storage tank, and 3) clarify and update the Auxiliary Feedwater Pump operation description. 11.0 RADI0 ACTIVE WASTE MANAGEMENT Table 11.5-1 has.been revised to correct the principle isotopes monitored in several process radiation monitoring detectors and to correct the bases for alarm set points in several other detectors. 13.0 CONDUCT OF OPERATIONS and, 14.0 INITIAL TEST PROGRAM Chapters 13 and 14 have been revised to reflect the reorganization of the Startup organization to form the Test Department which is responsible for testing and initial startup activities. 17.0 OVALITY ASSURANCE The changes to Table 17A-1 are technical or editorial in nature and do not affect the programmatic aspects for the establishment and implementation of the QA/QC programs.

TXX-88229

• February 15, 1988

~ Page 5 of 6 NRC OVESTIONS AND RESPONSES ) Changes to the following questions and responses (Section) have been made for clarification, correction, update, and addition:

1) 032.0 Instrumentation and Control Systems

2) 040.0 Power Systems i

3) 130.0 Structural Engineering 4) 212.0 Mechanical Engineering

5) 421.0 Quality. Assurance 6) 423.0 Quality Assurance EDITORIAL Several editorial changes have been made which include the reissuance of Sections, Appendices, Tables and Figures utilizing the format allowing computerization of the amendment change bars and numbers.

~ This computerization ensures consistency and accuracy 'f the FSAR. o 1 i A page-by-page description of the changes included in Amendment 68 is attached. Minor revisions to this description have been made since the advance copy transmittal (TXX-88200 dated February 5, 1988). These revisions are identified by change bars in the margin. In addition, Sections 3.9N and s* 3.11N were rearranged to be in the correct FSAR sequence. This description also serves as a listing of the pages which contain~ technical changes in Amendment 68. Pages which have only editorial changes (e.g. typographical corrections, repagination) are not discussed in the description. In addition to the "upcoming" FSAR changes identified in the Amendment 66 description transmittal (TXX-88040 dated January 15,1988), TU Electric j anticipates further CPSES FSAR changes resulting from additional modifications j to the CPSES design and/or physical plant. While the details of these changes are not sufficiently defined to include them in Amendment 68, we would like to supply the staff with advance notice of the potential for such changes. These potential changes are noted below with a brief description:

1. LOCA and Main Steam Line Break (MSLB) analysis in containment

~ The LOCA and MSLB accident analyses and impacts upon the containment pressure-temperature transient are being revised to correct the error found in the CONTEMPT computer code.

2. Reanalysis of boron dilution event The boron dilution event is being reanalyzed for an increased boron dilution flow rate from the Volume Control Tank (VCT).

3. Containment spray pH The containment spray pH control is being reanalyzed.

Design changes may be required as a result of the reanalysis. L : ' ~ L

February 15, 1988 - Page 6 of 6 If you have any questions concerning this letter or the attachment, please do not hesitate to contact me or my staff. Very truly yours, I '? Zt'. t W. G. Counsil BSD/bsd Attachment c-Mr. R. D. Martin, Region IV CPSES Resident Inspectors - 3 copies 4 - _ =,. .- ;.= - - ~ ~,

Attachment to TXX-88229 February 15, 1988 o Page 1 of 85 FSAR Page jasAmended) Description l 1A(N)-23 Editorial: This change is to correctly reflect the revision date for Revision 1 to Reg. Guide 1.38. Change the typographical error from "10/75" to "10/76". 1 A(B)-10 Revision: No iodine absorber efficiency was considered when the fuel handling accident was reanalyzed in Amendment 66. 1A(B)-43 Clarification: Clarifies description of separation provided for non-Class 1E security lighting. Separation is provided by two separate Class 1E feeder breakers connected in series. These breakers are coordinated with their supply breaker and will be tested periodically to ensure that coordination is maintained, 1A(B)-45 Revision: Adds two applications of splices in raceways justified by Appendix 8A (thermocouple reference junction boxes and field routed power cables spliced in manholes). 1A(B)-74 Editorial: Replaces text for Regulatory Guides 1.138, 1.139 and 1.140 which was inadvertently deleted in Amendment 66. t i 4 l

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 2 of 85 FSAR Page (as Amended) Description 2-1 thru 2-xlix Update: Tatele of contents for Chapter 2 has been updated to provide consistency with the changes described below for Sections 2.4 and 2.5. Sections 2.4.3 Clarification: Corrects various typographical errors and and 2.4.5 ommissions and provides changes to ensure _ consistency between the text, tables and figures. 2.4-17 Editorial: Corrects typographical error by changing "overload" to "overland" to improve clarity of meaning and consistency within the text. 2.4-28 Clarification: Corrects the text for.the maximum wave height runup from "10.2" to "6.8" for the Squaw Creek dam to be consistent with T2.4-14. Clarification: Adds the reference for T2.4-14 to provide clarity and consistency between the text and table. 2.4-29 C'lari fication: Corrects typographical ommissions to provide consistency between text, tables and figures. Revises wave runnup and setup elevations. 2.4-31 Clarification: Corrects typographical error by changing "over-water wind of 95 mph" to "over-water wind of 81 mph" to provide consistency between text, tables and figures. 2.4-42 Clarification: Corrects the typographical error from "Figure 2.4-15" to "Tigure 2.4-25". 2.4-18 Update: Incorporates the results of a reanalysis using a "more conservative" Source Tena. The analysis is taken from the Westinghouse "Radiation Analysis Design Manual," Revision 5. ~2.4-56 Clarification: Changes the wording."has been observed" to "were used" to clarify the use of borings to determine water levels. Clarification: Adds reference for F2.5.5-77 to clarify i the observed static water levels for the onsite water { table and provide consistency between the text and table. Update: Added reference for Section 2.5.4.13 for the permanent system of piezometers to measure the onsite groundwater levels. See Justification (Addition) for p. 2.5-151, 2.4-68 Editorial: Corrects typographical error from "Section 2.4.3.3.1" to Section 2.4.13.3.1". 3 7

. r ~ AIENDMENT 68 DESCRIPTION i Attachment to TXX-88229 hbruary 15, 1988 Paqa 3 of 85 FSAR Page ]<* (as ' Amended)_ Description , ~, T2.443 Editorial: Corrects typograph.ical errors to improve .' N clarity and provide consistency with the text. x, ~ See Justification for T2.4-13. ^ T2.4-l4 4 . s. T2.4-20 See Justification for p. 2.4-48. 1 7 2,'t'-21 See Justification for p. 2.4-48. b gd* pr* M Ni,, = g / sp' e i /% s_ 'g h< O N J_, e j e / N Bru J b P h ( 9 en' 1 q ) .s s' s l 1 n;_ -

AMENDMENT.68 DESCRIPTION Attachment to TXX-88229 i February 15,.1988 Page 4 of 85 FSAR Page (as Amended) Description Section 2.5 As a result of the SWEC validation effort of design basis documents relating to Geology and Seismology, Section 2.5 has been reorganized and reworded to support the new infomation made available from the review of existing design documents and the development of new design studies. These changes have been made to improve the clarity of meaning and consistency of wording within the text, and to support updates to figures and tables. 2.5-1 Clarification: Adds references for' Figures 2.5.1-1, 2.5.1-3, 2.5.1-4, 2.5.1-5, 2.5.2-2, 2.5.2-3, 2.5.2-6 and 2.5.2-8 to improve consistency between the text and figures. 2.5-6 Editorial: Corrects typographical error by changing "100 feet" to 1000 feet". 2.5-14 Clarification: Corrects ommissions of "Arch" and "Uplif t" to improve clarity of meaning. Clarification: Restructures the sentence to improve the clarity of meaning. 2.5-20 Clarification: Restructures sentence to improve clarity of meaning. 2.5-28 See Justification f,or p. 2.5-20. Clarification: Changes "70" to "60-70" to improve consistency between the text and the 1985-1986 Dames and Moore geophysical study. Editorial: Deletes "(Orbitolina, a megascopic toraminifera)". 2.5-29 Clarification: Changes "30" to "30-40" to improve consistency between the text and the 1985-1986 Dames and Moore geophysical study. 2.5-30 Update: Adds new text from the 1985-1986 Dames and Moore geophysical study on site geology which confims the preexcavation foundation design parameters. 2.5-31 See Justification for p. 2.5-30. m, ~ A.

AMEN 0 MENT 68 DESCRIPTION - Attachment to TXX-88229 February 15, 1988 Page 5 of 85 FSAR Page jas Amended) Description l 2.5-33 Clarification: Corrects errors in figure references frem "2.5.1-24, 25" to 2.5.1-23A, 24A" to improve consistency between the text and figures. See Justification for p. 2.5-20. 2.5-34 Clarification: Corrects errors in figure references, from "2.5.1-33 and 34" to "2.5.1-34 and 35" to improve consistency between the text and figures. 2.5-37 Clarification: Adds section title "3.1.2.2 011 and Gas Wells" to improve clarity.of meaning with the text. Editorial: Adds "hydrocarbon" to improve clarity at meaning. 2.5-38 Clarification: Adds "exploratory or" to improve clarity of meaning. Clarification: Adds "Paleozoic" to improve clarity of meaning. 2.5-51 Clarification: Corrects error in figure reference from "2.5.1-26" to "2.5.1-20" to improve consistency between the text and figure. 2.5-65 Clarification: Correctserrorforreferencefrom"[83]" to "[70]" to improve consistency between the text and references. ' ~ ~ 2.5-76 Clarification: Corrects error in figure reference from "2.5.2-12" to "2.5.2-2" to improve consistency between the~ text and figure. 2.5-82 Clarification: Corrects error in figure reference from "2.5.2-3" to "2.5.2-13" to improve consistency between the text and figure. 2.5-94 See Justific.ation for p. 2.5-20 and 2.5-30. and 2.5-95 2.5-97 See Justification for p. 2.5-20 and 2.5-30. and 2.5-98 2.5-100 See Justification for p. 2.5-20 and 2.5-31 thru 2.5-1.02 s v.

AMENDHENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 6 of 85 FSAR Page (as Amended) Description 2.5-102 Clarification: Rewords title for Section 2.5.4.2.3 from "Rock Core Analyses" to "Rock Core Composition Analyses" to improve consistency and clarity of meaning. 2.5-123 See Justification for p. 2.5-20. See Justification for p. 2.5-20. 2.5-124 Clarification: Chagnes "explorations" to "surveys", adds "P-10, M-1, 01-2, D1-8A and 01-9" and changes "Figure"- to "Figures 2.5.5-5 and" to improve clarity of meaning and consistency between the text and figures. See Justification for p. 2.5-30. 2.5-125 See Justification for p. 2.5-20. Clarification: Changes table references from "2.5.4-6 and 2.5.4-7" to "2.5.4-58 and 2.5.4-5C" to provide new information to improve clarify of meaning and consistency with the text and tables. 2.5-126 Clarification: Adds table references for "Table 2.5.4-5B and 2.5.4-5C" to provide information to improve clarity of meaning. 2.5-127 See Justifications for pp. 2.5-20 and 30. 2.5-128 Clarification: Changes "uphold survey" to "uphole shear ~ survey". See Justification for p. 2.5-20. %.5-129 Clarification: Adds "compressional and", "in the initial survey". See Justification for 2.5-20. Changes figure references from "2.5.4.4-1 and 2.5.4.4-2" to "2.5.4-5B and 2.5.4-5C" to improve consistency between text and tables. 2.5-130 and See Justification for p. 2.5-30. 2.5-131 2.5-132 Clarification: Rewords title for Section 2.5.4.4.6 from "Gamma Ray and Resistivity Logs" to "Borehole Geophysical Logs" to improve consistency and clarity of meaning. See Justifications for pp. 2.5-30, 2.5-133 Update: Adds new text to improve the clarity of meaning. This addition of new text does not constitute a technical change.

AMEN 0 MENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 7 of 85 FSAR Page (as Amended) Description 2.5-134 See Justifications for p. 2.5-20 and 30. 2.5-135 See Justification for p. 2.5-20. Clarification: Adds "43-ft thick" to improve consistency between the text and figure. Changes "Class !" to "Category I" to use the most correct CPSES tenninology. Update: Adds description and reference for new Figure 2.5.4-30A. See Justification for p. 2.5-30. See Justification for p. 2.5-20. Clarification: Changes "Class 1E" to "Seismic Category I" to use the most correct CPSES terminology. 2.5-136 Clarification: Restructures sentence to improve consistency with p. 2.5-135. l Editorial: Corrects the number of sheets for Figure j 2.5.4-37 from "31" to "21". 2.5-137 Clarification: Restructures sentence to improve consistency the text and figures. Clarification: Changes "Class I" to "Category 1". See Justification for p. 2.5-20. Clarification: Changes "Class 1" to "Seismic Category I". See Justification for p. 2.5-20. Clarification: Restructures sentence to provide consistency with text changes in Section 2.5.4.5. 2.5-138 Clarification: Depicts new infonnation on dry, moist and saturated unit weight values for Category I backfill t based on in-place density tests, i Clarification: Changes "Class 1" to "Seismic Category I". See Justification for p. 2.5-20. Clarification: Restructures text to improve clarity of meaning and consistency with referenced figures. Clarification: Depicts new information on dry, moist and saturated unit weight values for Category I bedding based on in-place density tests. i c n ,4 n,

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 _ Page 8 of 85 s FSAR Page (as Amended) Description 2.5-139 Clarification: Rewords title for Section 2.5.4.7 from "Response to Class I Backfill and Bedding to D Loading" to "Response to Soll Dynamic Loading"ynamic to improve clarity of meaning within the text. Clarification: Adds new text to improve clarity of meaning and consistency within the text. This clarification does not constitute a technical change. Clarification: Changes "cyclic characteristics" and "cyclic strength characteristics" to "cyclic shear strength characteristics"; "Class I" to "Category I", and "cyclic strength criteria" to "cyclic shear strength criteria", to improve the consistency between the text and the figure. Clarification: Deletes reference to Gibbs and Hill Inc. specification. See Justification (Clarification) for p. 2.5-150. Clarification: Changes "peak to peak axial strain" to "double amplitude strain" to improve the consistency between the text and the table. See Justification for p. 2.5-20, 2.5-140 Clarification: Changes "sampled" to "tested" and "physical properties" to "density" to improve clarity of meaning and consistency between the text and the figure. Clarification: Changes "accurate" to "conventional", i "particle cell" to "triaxial cell" and "triaxial testing" to "cyclic triaxial testing". See Justificatton for p. 2.5-20. 2.5-141 Clarification: Changes "described by" to "recommended by". See Justification for p. 2.5-20. . t

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 c February '15,1988 Page 9 cf 85 FSAR Page (as Amended) Description 2.5-141 Clarification: Changes "cyclic shear testing" to "cyclic triaxial testing". See Justification for p. 2.5-20. j Clarification: Changes "cyclic shear testing" to "cyclic triaxial testing" and "cyclic strength criteria" to "cyclic strain criteria". See Justification for p. 2.5-20. Clarification: Changes "Four representative plots" to "One plot for each material tested at various confining pressures" and "strength" to "strain". See Justification for p. 2.5-20. Clarification: Adds "the Glen Rose cru-hed limestone". See Justification for p. 2.5-20. 2.5-142 Addition: Adds reference for new Table 2.5.4-13A for the summary of additional cyclic strength tests. Clarification: Adds "at reduced stress levels" and changes "cyclic shear criteria" to "cyclic strain criteria". See Justification for p. 2.5-20. Clarification: Adds "at reduced stress levels". See Justification for p. 2.5-20. See Justification for p. 2.5-20, 2.5-143 Clarification: Deletes references to Gibbs and Hill specification and adds references for T2.5.4-11 for cyclic shear strength criteria to improve consistency between the text and table. Clarification: Changes "Category" to "Category I" and "rock" to "crushed stone". See Justification for p. 2.5-20. 2.5-144 Clarification: Changes "Class I" to "Category I" and "bending" to "bedding". See Justification for p. 2.5-20. Clarification: Changes title for Section 2.5.4.9 from "Earthquake Design Basis-Reliquefaction" to "Earthquake Design Basis" to improve consistency and clarity of meaning. Clarification: Provides additional information and references for Section 2.5.4.9 to improve clarity of meaning and consistency within the text. See i Justification for p. 2.5-20. j J

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 i February 15, 1988 Page 10 of 85 FSAR Page (as Amended) Description 2.5-144 Clarification: Changes title for Section 2.5.4.10.1 from "Safety Against Shear Failure" to "Bearing Capacity" to improve the consistency and clarity of meaning with revised text. Clarification: Revises text to discuss the bearing capacity analysis performed during the validation effort and references the revised tables. See Justification for Tables 2.5.4-1 and 2.5.4-6. 2.5-145 Addition: Adds additional text to discuss the bearing capacity analysis performed during the validation effort and references revised tables. See Justications for Tables 2.5.4-1 and 2.5.4-5. 2.5-146 ' Addition: Adds new text to discuss the bearing capacity analysis performed during the validation effort and references new Table. See Justification for T2.5.4-6a. Clarification: Changes "toe" to "edge", "35 kips" to 24.9 kips" and "1.9" to "2.0" to be consistent with design analyses and referenced figure. Update: Adds and revises the text to Section 2.5.4.10.2, Settlement of Foundations, to describe the settlement analysis for Category I structures to improve clarity of meaning and consistency between the text and referenced tables and figures. 2.5-147 See Justification (Update) for p. 2.5-146, 2.5-148 Addition: Delete the old text and adds new text to Section 2.5.4.10.3 to more clearly explain the lateral forces used for design purposes. See Justification for

p. 2.5-20.

2.5-149 See Justification for p.~ 2.5-148. Adds reference to F2.5.4-54 to provide consistency between text and j figures. j i 2.5-150 Addition: Deletes old text and adds new text to Section 2.5.4.11 to include the minimum allowable factors of safety for static and dynamic bearing capacity and slope stability design criteria. Adds references for sections on bearing capacity settlement, lateral loads, slope i stability and rock and soil properties. 4 I l = - - - -

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 - i i February 15, 1988 ~ Page 11 of 85 s FSAR Page (as Amended) Description 2.5-150 Clarification: Deletes references to Gibbs and liill, Inc., specifications. In general, design and J construction specifications are being deleted because (1) specific identification of these specifications is not necessary in the FSAR, and (2) some specifications are being superceded in the design validation process. 2.5-151 Addition: Adds title for Section 2.5.4.13.1 "Extensometer" to improve clarity of meaning and consistency with the, text. Addition: Adds new text for Section 2.5.4.13.2 to describe the postconstruction groundwater monitoring program which is part of a commitment to NRC Question 371.12. 2.5-152 Addition: Adds new text for Section 2.5.4.14 to improve clarity of meaning and consistency within the text on in-leakage and groundwater monitoring. 2.5-153 See Justification for p. 2.5-152 Clarification: Delete "Nuclear Power" and "the failure of which" and add "whose failure". See Justification for

p. 2.5-20 Clarification:

Deletes "Reservoir" and adds "of a part 1 of the reservoir in the plant site vicinity shown". See Justification for p. 2.5-20 2.5-154 Clarification: Adds title "Log of Borings" to improve clarity of meaning, j 2.5-155 Clarification: Deletes "and the quantity of" to provide consistency within the referenced section. 2.5-156 Clarification: Corrects error in the figure reference from "2.4-16" to "2.4-1" to improve the consistency between the text and figures. 2.5-158 Clarification: Changes "intervals" to "vertical interval". See Justification for p. 2.5-20 2.5-159 Clarification: Changes "permeability characteristic" to "permeability". See Justification for p. 2.5-20 l Clarification: Changes "recorded, at the surface" to' l "and". See Justification for p. 2.5-20. i 2.5-160 See Justification.for p. 2.5-161. j 4 i e p 9 (y 4 v-c ir* , i

Attachment to TXX-88229 l February 15, 1988 Page 12 of 85 FSAR Page (as Amended) Description 2.5-161 Clarification: Changes "balancing" to "equalization". See Justification for p. 2.5-20. t 2.5-163 Clarification: Changes "Rock" to "Limestone". See Justification for p. 2.5-20. 2.5-164 See Justification for p. 2.5-163. Clarification: Deletes "plan view and" to provide consistency between the text and the referenced figure. 2.5-167 See Justification 2.5-20. 2.5-171 Clarification: Changes "cyclic strength" to "cyclic shear strength" and adds reference numbers 130 thru 133 to the text. See Justification for p. 2.5-20. 2.5-172 Clarification: Adds reference number "136" to the text. Clarification: Adds "the relationship shown in" and corrects typographic error in figure reference from "2.56-47" to "2.5.6-47". See Justification for pp. 2.5-20. 2.5-173 See Justification for p. 2.5-20 Clarification: Changes "cyclic strength" to "cyclic shear strength". See Justification for p. 2.5-20 Clarification: Changes "shear strength" to "cyclic shear strength" and "ultimate" to "conservative". See Justification for p. 2.5-20. See Justification for p. 2.5-20 2.5-174 Clarification: Changes "Excaiation" to "Excavetion operations" and "embankment" to "test-embackment". See Justification for p. 2.5-20. Clarification: Changes "embackment" to "test-embackment" and "test" to "source of material". See Justification for p. 2.5-20. 2.5-177 Clarification: Adds "rockfill embankment material and the " to improve clarity of meaning and consistency of text. 2.5-179 Editorial: Removes reference from text and adds the reference number "134" to the text. I

AMENDMENT 68 OESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 13 of 85 FSAR Page {asAmendedl Description 2.5-180 Clarification: Deletes "approximately". See Justification for p. 2.5-20 t 2.5-181 Clarification: Changes "Design verification" to "Verification". See Justification for p. 2.5-20. 2.5-182 Clarification: Deletes "uniform slope of". See Justification for p. 2.5-20. Clarification: Deletes "in the range of". See Justification for p. 2.5-20. Clarification: Deletes "in the range of" and "a value in the range of". Adds "...the shell, the safety factor was found to be 1.38. The.... See Justification for 2.5-20. 2.5-183 Clarification: Removes reference from text and add the reference numbers "135", "136" and "137" to the text, 2.5-184 Clarification: Removes references from the text and adds reference mumbers 138 thru 141 to the text. ^ 2.5-185 Clarification: Removes reference from the text and adds reference number "142" to the text. I Clarification: Chan See Justification for p.ges "mini-dam" to "SSI Dam". 2.5-20. 2.5-186 Clarification: Removes reference from the text and' adds reference number "143" to the text. 2.5-190 Clarification: Changes section reference from 1 "2.5.6.5.2" to "2.5.6.5.2.6" to improve consistency within the text. 2.5-201 See Justification for 2.5-20. 2.5-205 Clarification: Adds "The piezometers were grouped in three ranges". See Justification for p. 2.5-20. Clarification: Adds "(we11 point)" and "(pneumatic)". See Justification for p. 2.5-20. 2.5-206 See Justification for p. 2.5-20. 2.5-207 Clarification: Changes section reference from "2.5.6.3" to "2.5.6.3.1" to improve consistency within the text. a 4 b ~.

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 Fcbruary 15, 1988 Page 14 of 85 s FSAR Page (as Amended) Description 2.5-208 Clarification: Changes "plasticity index" to "liquid limit". See Justification for p. 2.5-20. 2.5-209 Clarification: Changes section reference from "2.5.6.7" to "2.5.6.7.1" to improve consistency within the text. 2.5-210 Clarification: Changes section reference from "2.5.6.3" to "2.5.6.3.2" to improve consistency within the text. 2.5-212 Clarification: Adds "Originally up to a 12-inch loose lift thickness was al wwed". See Justification for p.' 2.5-20. 2.5-228 Clarification: Adds references to improve clarity of meaning and consistency within the text. 2.5-229 T2.5.4-1 , Addition: Adds additional compressive strength data. T2.5.4-5 Clarification: Revises the table title to provide more clarity of meaning and consistency with the text. T2.5.4-5A See Justification for T2.5.4-5. T2.5.4-5B See Justification for T2.5.4-5. T2.5.4-5E See Justification for p. 2.5-31. T2.5.4-5F See Justificaiton for p. 2.5-31. T2.5.4-5G See Justification for p. 2.5-31. [ T2.5.4-SH See Justification for p. 2.5-31. T2.5-4-6 The original T2.5.4-6 has been subdivided into two tables i to list the bearing capacity analysis as a static (T2.5.4-6) and dynamic (T2.5.4-6a) sumary. i Revision: Revises values in T2.5.4-6 as changed by the validation bearing capacity calculations. T2.5.4-6A Update: Adds T2.5.4-6A to include the "Dynamic Bearing Capacity Analysis" in the FSAR. -J

~~ AMENDMENT 68 DESCRIPTION s Attachment to TXX-88229 Fsbruary 15, 1988 { Page 15 of 85 FSAR Page (as Amended) Description j T2.5.4-7 Clarification: Updates table to reflect revised text for section 2.5.4.10.2 describing the settlement analysis for Category I structures. T2.5.4-11 Update: Adds more details on the cyclic shear strength criteria for backfill, bedding and filters. T2.5.4-12 See Justification for T2.5.4-11. T2.5.4-13 See Justification for T2.5.4-11. i T2.5.4-13A See Justification for T2.5.4-11. i e s .m ) l i m.

^ ~ AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 16 of 85 FSAR Page (as Amended) Description Section 2.5A Clarification: Corrects typographical errors and rewords aortions'of this section to ensure the consistency aetween the text, tables and figures. 2.5A-2 Clarification: Changes "SSI embankment" to "SSI Dam" and adds "depth of the" to improve clarity of meaning and consistency with the text and the referenced figure. 2.5A-3 Clarification: Deletes "of height" to improve clarity of meaning and consistency with the text and the referenced figures. Clarification: Adds references for Figures 2.5A-19 and 2.5A-20 for histograms of grain size distributions for the rock fill, Filler A and Filler B. T2.5A-1 Clarification: Adds note to the table to clarify the unit of measure for the vane readings. T2.5A-2 See Justification for T2.5A-1. T2.5A-4 See Justification for T2.5A-1. i

-m. AMEN 0HENT 68 DESCRIPTION Attachment to TXX-88229 ~ Fcbruary 15, 1988 Page 17 of 85 FSAR Page (as Amended) Description Table 3.2-1 Editorial: inis table is being reissued in the computerized format. (sheet 1) Addition: This change adds "NC-3200" to the Safety Class 2 (Notes 2 and 5) quality standards requirements for Pressure Vessels. Section NC-3200 was used for the Safety Injection Accumulator Tanks. e j 1 i 1 l t l l j 'l 1

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 18 of 85 FSAR Page (as Amended) Description Section 3.3 Editorial: Section 3.3 refssued with page renumbering and editorial corrections (typographical errors) incorporated. 3.3-4 Correction: Changes the word "before" to "when" in describing the differential pressure required to partially blowout door F-4E. Correction: Changes the article "the" to "a" in several places to correctly modify the words they designate.' 3.3-5 Correction: Corrects identification of roll-up door from "E-3" to "E-3A". Correction: Changes to word "before" to "when" in describing the differential pressure required to partially blowout door E-3A. 3.3-11 Correction: Changes reference 2 to a later version which incorporates code addendum. Table 3.3-1 Revision: Changes door "E-208" to "E-208." (Sheet 1) (Sheet 3) Addition: Adds note to table clarifying the 1 applicability of the door numbers and positions. Revision: Deletes door S-33 from table. This door was required to be open therefore its removal will not affect tornado venting. Addition: Adds doors S-11, S-11X, S-12X, S-37, and S-37X to the table. (Sheet 4) Revision: Deletes section of table regarding ti;e Safeguards Building-Unit 1 and the Safeguards Building ' Unit 2. The doors affecting tornado venting for both--- buildings are now listed under the section titled "Safeguards Buildings-Units 1 & 2."

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 ~ February 15, 1988 - Page 19 of 85 FSAR Page (as Amended) Description 3.68-4 Clarification: Deletes the words "in any 'possible direction" since the break location and the hinge location determine the direction of pipe movement. Clarification: Deletes the words "nearest pipe whip restraint" and replaces it with "location determined by calculation". Plastic hinge locations are determined by calculations. 3.68-18 & 3.68-19 Revision: Deletes reference to selection of breaks at intermediate locatio.ns based on potent'ial high stress points such as pipe fittings, welded attachments and valves. This was considered to be one of two acceptable methods for choosing intermediate break locations. The second method, the application of the' sum of equations (9) and (10) in paragraph NC-3652 of the ASME Code, Section III, is now used for the determination of all intermediate break locations for class 2 and 3 piping. Revision: Deletes portions of the text previously requiring the postulation of arbitrary breaks and re-arranges the remaining paragraphs. Section 3.6 of SSER 12 indicates the elimination of arbitrary intermediate breaks for CSES is under review. However, the deletion of this requirement was approved in Generic Letter 87-11 and specifically for CPSES in an NRC letter dated October 13, 1987. t t 3.6B-20 Clarification: Deletes the word "ranges". 4 I i t ~ u

AMENDMENT 68 DESCRIPTION Attachemnt to TXX-88229 February 15, 1988 Page 20 of 85 FSAR Page (as Amended) Description 3.68-21 Revision: The text is revised to redefine Break Exclusion Area (BEA) inside containment..These require-ments impact only the Safety injection System (SIS) and the Chemical / Volume Control System (CVCS). The BEA requirements of Branch Technical Positions HEB 3-1 Section B.1.b. The BEA, for outside reactor containment, are shown on FSAR figures 3.6B-15 thru 18, 23, 25 thru 30, 42, 82, 85, 87 and 88. 3.68-29 Revision: Replaces the symbol for steady state thrust coefficient et with the symbol k. Also adds t reference 22 for calculation methods used to determine the coefficient. Revision: Replaces "RELAP-3" with "RELAP-5". Reflects the use of the improved version of this computer code. 3.68-30 Revision: Replaces computer program "PLOTR" with "CALPLOTF" for plotting of break force time-history plots. Revision: Replaces "RELAP-3" with "RELAP-5". Reflects the use of the improved version of this computer code. e 1 l e l i i I a .. pr s3

~ 4MENDMENT 68 DESCRIPTION ~ ~ Attachment to TXX-88229 Eebruary 15, 1988 Page 21 of 85 FSAR Page (as Amended) Description i 3.68-31 Clarification: Revises the word "in" to read "within". Addition: Adds computer codes SHPLAST 2267 and ABAQUS to the computer codes that ma piping dynamic responses. y be used for determination of These codes are modeled using multilinear stiffness curves. Previously, only PIPERUP, which is modeled with a bilinear stiffness curve was used. The application of the multilinear modeled computer codes permits more realistic modeling of the various plant piping configurations. Correction: The PIPERUP code is corrected to be modeled using a bilinear stiffness curve instead of the previously stated trilinear stiffness curve. As can be seen from Figure 3.68-7, the "perfectly plastic" region of the stiffness curve is the constant stress region. It is not useful to consider this region as a separate linear region and this stiffness curve is more corrertly considered to be bilinear, a i N. + i b ) l J s a 9 d -..J

AMEN 0HENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 22 of 85 FSAR Page (as Amended) Description 3.6B-38 Revision: Deletes reference to pipe whip restraint design for RCS main loop pipino. The pipe whip restraints are no longer required for the RCS main loop piping as a result of the application of the leak-before-break technology permitted in GDC-4 3.68-39 Clarification: Adds reference to the ASME Code for determination of minimum ultimate uniform stress. -3.68-46 Revision: Deletes the word "two" with respect to intermediate break postulation since arbitrary intermediate breaks are no longer considered. 3.68-50 Revision: Deletes the word "two" with respect to intennediate break postulation since arbitrary intermediate breaks are no longer considered. 3.6B-54 Revision: Deletes the word "two" with respect to intermediate break. postulation since arbitrary in'termediate breaks are no longer considered. 3.68-59 Revision: Deletes the word "two" with respect to intennediate break postulation since arbitrary intermediate breaks are no longer considered.

AMENDHENT 68 DESCRIPfl0N Attachment to TXX-88229 February 15, 1988 . Page 23 of 85 FSAR Page (as Amended) Description 3.68-69 Revision: Provides the reference for the RELAP-5 computer code. 3.68-71 Revision: Provides references for the CALPLOTF, ABAQUS-ND and SHPLAST 2267 computer programs. Revision: References ANSI /ANS 58.2. Revision: References the Federal Register with regard to the modification to GDC 4. Figure 3.68-15 Revision: The revised figures provide the latest break 3.6B-16 thru 18 locations postulated in accordance with the requirements 3.68-23-1,3.68-23-2 of FSAR section 3.6B. Note that the revised figures omit 3.68-27 thru 30, stress tables previously provided. This analysis 3.6-42, infonnation is maintained b'y TV Electric in Systems Interaction Program "Claculation Books". Figures 3.68-50-1, Revision: The listed "Stress Node Break Point a'nd 3.68-50-2, Restraint location" figures are revised to be consistent 3.6B-51-1, with the revised definition of' Break Exclusion Area 3.68-51-2, piping plus revision in break location. Revised figures resulted in additional break 3.68 52, locations and relocation of break locations in some 3.6B-53, cases. 3.68-54, 3.68-55, 3.68-70 3.68-72, 3.68-78 thru 3.68-81 Figure 3.68-82-1, Revision: The revised figures provide the latest break 3.68-85 locations postulated in accordance with the requirements 3.68-87-2, and of FSAR section 3.68. Note that the revised figures omit 3.68-88-2 stress tables previously provided. This analysis information is maintained by TV Electric in Systems Interaction Program "Calculation Books." e t 1

AMENOMENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 24 of 85 FSAR Page (as Amended) Description 3.7N-32 Revision: Revises the active dynamic degrees of freedom from 27 to 23 for the vertical seismic model for the Reactor Internals based on seismic qualification reports. Revision: Revises the results from the model analysis of the horizontal system from 17 to 12 modes present with frequencies less than 33 Hz based on seismic qualification reports. 3.78-1 Clarification: Provides a clearer description by deleting the superfluous information. 3.78-2 Correction: Corrects the discussion by stating that the design floor spectra were devoloped from only one vertical and one horizontal artificial time history record not 5 as previously implied. 3.78-3 Correction: Revises the text describing how the artificial time histories for the seismic analyses were s. validated. The artificial time history records meet the minimum acceptance criteria given by Table 3.7.1-1 in section 3.7.1 of the Standard Review Plan. 3.78-5 Correction:* Deletes reference to FSAR sections 2.6 and 2.7 since they do not exist. 3.78-7 ~ Correction: Corrects the techniques used to generate the stiffness properties for the seismic Category I structure models. Standard structural techniques (not finite elements) were used for the Category I Tanks and the Service Water Intake Structure models. 3.7B-8 Correction: See justification for page 3.78-7. 3.78-10 Clarification: Deletes the word "smoothed" from the phrase "smoothed instructure response spectra." The enveloping technique was used for all spectra not only smoothed spectra.

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 25 of 85 FSAR Page (as Amended) Description 2 3.78-11 Clarification: Adds statement to indicate that FSAR section 3.78.2.9 is the primary location which discusses 4 parametric studies and spectra widening. 3.78-12 Correction: Deletes discussion of spectra widening and adds statement refering to FSAR section 3.78.2.9 which deals with parametric studies and spectra widening. 3.78-24 Correct!on: - Adds the Category I Tanks to the list of - structures which have mathematical models. Clarification: Changes the word "buildings" to "structures." 3.78-25 Correction: Adds the word "circular" to address Category I Tanks. Clarification: Clarifies the discussion regarding best estimate values, upper bound values, and lower bound values used in the parametric anal All three values were not used for all structures (yses. see FSAR section 3.78.2.5 for further explanation). 3.78-26 Correction: Revises text to indicate that the stiffness properties for the Category I Tanks and Service Water Intake Structure are generated by hand calculations. Correction: Replaces the word "all the" with "rearesentative" to reflect the fact that Category I Tan (s are not included in the tables. It should be noted that the natural frequencies and modal particip6 tic'n factors have been determined for the Category I Tanks but have not been included in the tables at the end of this section. 3.78-28 Clarification: Clarifies the definition of the mass atio Rm. l 3.78-32 Correction: Replaces the word "the" with "re)resentative" to reflect the fact that Category I Tan (s are not included in the tables. It should be noted that the values of effective foundation masses and mass moments of inertia have been determined for the Category I Tanks but have not been included in the tables at the end of this section. I i 3 3 -- a 4 - *. _.. r, e - o,- , 3-N

~ . AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page~26 of 85 FSAR Page (as Amended) Description 3.70-34 Correction: Deletes text which discusses the analysis of a structure when the mat cannot be considered rigid with respect to the foundation meduim. The next sentence states, "The analysis of all... is based upon a rigid mat approach," therefore the discussion of a non-rigid mat approach is superfluous. 3.78-38 Correction: Deletes text which stated that the effect of embedment on rotational foundation rigidities for structures with shallow depth of embedment is neglected. The effect is negligible'but need not be neglected. 3.78-39 Correction: Deletes sentence regarding parametric variations and spectra widening as this is discussed previously in this section. Correction: Revises-discussion for the development of the individual floor response spectra. The simplified text meets the intent of the Standard Review Plan section 3.7.2(11)5. The three components of earthquake motion are considered by using the "square root of the sum of the squares" method to predict the resulting response spectra at a particular location. Only two kinds of 1 response spectra were used, "refined response spectra" and res)onse spectra at selected locations (for Westing 19useanalysis). 9 i 3.78-40 Correction: Deletes subsection title as the following paragraph is self explanatory. 3.7B-43 Clarification: Deletes superfluous information as the' artificial ground spectra exceed the minimum acceptance criteria of the Standard Review Plan section 3.7.1 and are therefore conservative. 3.78-44 Correction: Provides a clearer explanation of the enveloping techniques used at CPSES. 3.78-45 Correction: Corrects discussion of stiffness properties' calculations. For the Service Water intake Structure and i the seismic Category I Tanks, the stiffness properties are determined using standard structural techniques not the finite element technique, i s. y.

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 27 of 85 .) FSAR Page (as Amended) Description I 3.78-49 Correction: Provides an alternative method by which the overturning moment for a structure may be calculated. l This alternate method is consistent with the discussion in FSAR section 3.78.2.2. 3.78-50 Correction: See justification for page 3.78-49. Correction: Deletes discussion of foundation pressure 3 calculations. This subject is addressed in FSAR section' 3.8.5 and does not belong in this section. Table 3.78-1 Correction: Changed to reflect the use of ASME Code Case N411. Table 3.78-2 Correction: Changed to reflect the recalculated Category (Sheet 1) I Tank results based on reanalysis perfonned as part of the design validation for CPSES. Tables 3.78-13, Revision: Revised to reflect the new Service Water 18,23,29,44,45 Intake Structure analysis. performed as part of the design 4 and 50 validation for CPSES. i Figures Correction: Corrects the horizontal response saectra for 3.7B-2 to -5 2%, 5%, 7%, 10% and 15% damping for the SSE. T1ese i figures are based on one horizontal artificial earthquake not 5 as previously implied in the FSAR. Figures Correction: Corrects the vertical response spectra for il 3.78-8 to -12 2%, 5%, 74, 10% and 15% damping for the SSE. These l i figures are based on one vertical artificial earthquake not 5 as previously implied in the FSAR. Figures Correction: Deletes five figures and replaces with 3.78-13,14 Figure 3.78-14. Only one horizontal artificial 15,16,17 acceleration time history record was used. 1 Figures Correction: Deletes five figures and replaces with 3.78-18,19, Figure 3.78-19. Only one vertical artificial 20,21,22 acceleration time history record was used. Figure 3.7B-38 Revision: Revises figure to indicate the new structural model for the Service Water Intake Structure based on reanalysis performed as part of the design validation for CPSES. t Figures Correction: Deletes these figures since the 3.7B-41 to -50 interpolation procedure was not used at CPSES. Figures Correction: Corrects the instructure response spectra 4 3.7B-51, for the steam generator support. The previous figures 52,53 have been superseded. I ~ x,.

\\ [ AMENOMENT 68 DESCRIPTION Attachment to TXX-88229 i February 15, 1988 Paga 28 of 85 FSAR Page (as Amended) Description Section 3.8 Editorial: Section 3.8 reissued with new format, page renumbering and editorial corrections (typographical errors) incorporated. 3.8-3 ' Clarification: Provides a clearer description of local thickened liner plate sections and discussas the use of overlay plates and/or for structural shapes which may be attached on the interior side of the liner of (section 3.8.1.1.5 "Steel Liner"). 3.8-4 Correction: Corrects the diameter of the personnel airlock as described in Section 3.8.1.1.6.1 "Personnel Airlock". Changes the diameter from "10 ft" to "9 ft," reflecting the as-built configuration. Clarification: This change clarifies the FSAR description of the personnel airlock door gaskets and equalizing valve arrangements. Automatic and manual equalizing valve operations are discussed in Vendor Manual CP-0214-001 and schematically shown on vendor prints 74-2427-119, i and 74-2427-122 thru 74-2427-126. The personnel and emergency airlock gasket testing arrangement is shown in FSAR Figure 3.8-21 as a dogtooth cross section instead of a double gasket arrangem(nt. 3.8-4 and Clarification: This change clarifies the FSAR 3.8-5 description of the emergency airlock equalizing valve arrangement and overall airlock leakage check requirements. Equalizing valve operations and' testing arrangements are discussed in vendor manual CP-0214-001 and schematically shown on vendor prints 74-2427-242 and 74-2427-200. 3.8-5 Correction: Corrects the diameter of the equipment hatch as described in Section 3.8.1.1.6.3 "Equipment hatch". Changes the diameter from "15 ft" to "16 ft," reflecting the as-built configuration. 3.8-5 and Clarification: Deletes the discussions of electrical 3.8 5 penetrations from Section 3.8.1.1.6.5, "Fuel Transfer Tube Penetration" and includes these items under the new Section 3.8.1.1.6.6 "Electrical Penetrations." 3.8-6 Clarification: Provides an expanded and clearer description of liner attachments in Section 3.8.1.1.6.7 (previously Section 3.8.1.1.6.6). Adds items welded to the thickened liner plate and discusses use of overlay plates and/or structural plates attached to the interior side of the liner.

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 Fcbruary 15, 1988 Page 29 of 85 FSAR Page (as Amended) Description 3.8-7 Clarification: Corrects the reference to article CC-2000 by stating which sections do not apply. The value of the coefficient of thennal expansion used for the SWEC design of the containment is 5.5x10-6 per degree F; in accordance with Appendix A of the ACI 349-76 Code. Thus testing to determine a reasonable value to use is not necessary. Thermal conductivity for concrete is dependent on its moisture content. The actual water content in the concrete depends on various factors, such as the age of the concrete and environmental factors i.e., temperature and humidity histories. In order to bound the problem a conservative thermal conductivity value (high) was used. This will maximize the heat transfer into the concrete. Creep and shrinkage of the concrete are not critical to the design of the containment because the containment is not prestressed. That is, creep and shrinkage characteristics of the concrete are important only for prestressed reinforcement. Because the concrete used for the containment structure does not contain special high densty aggretate for J radiation-shielding, special testing of the aggregate is not required. 3.8-9 Clarification: Deletes a sentence concerning ACI 318-71 which was unnecessary and confusing. Addition: Describes which code was used for concrete punching shear. The 1973 Edition of the ASME-ACI 359 Code did not address punching shear, thus the criteria in Section 11.10.3 of ACI 318-71 was used. 3.8-10 Correction: Incorporates Appendix A of the ACI 349-76 Code. ASME-ACI 359 Code does not provide guidance in determining thermal stresses. Therefore, additional ACI Code provisions are given. ACI 307 was previously stated as the applicable code for determining thermal stresses. However, ACI 307 is not applicable to the concrete containment structure. 3.8-11 Correction: Provides the correct ASME Code applicability date and sections used for the construction of the containraent liner and penetrations (3.8.1.2.3(1)). The referenced codes are technically acceptable.

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 30 of 85 FSAR Page (as Amended) Description 3.8-11 Revision; Clarifies the applicability of the AISC and 3.8-12 specification. Connections using A325 or A490 high strength bolts need not be pretensioned to the values required by AISC specification, Table 1.23.5. There are some connections in which pretensioning is undesirable, j such as thermal connections that allow movement between the connected parts. 3.8-12 and Addition: Provides material specifications used on the 3.8-13 constructionofthelinerandpenetrations(3.8.1.2.3(1)). 3.8-18 Revision: Allows the use of NB-2432 in lieu of CC-2612.2. NB-2432 provides requirements for a more complete chemical analysis. The ccatainment structure is designed and constructed to the proposed ASME-ACI-359 Code as invoked by the FSAR. Alternate methods and requirements may be used provided they meet the intent of the code. This change re) resents the as-built condition and meets the intent of tie code. This change is incorporated in the appropriate CPSES specification but had not previously been identified in the FSAR. 1 m s I I l

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 ~ Page 31 of 85 FSAR Page (as Amended) Description 3.8-18 Revision: Allows 1100 aluminum to be used as flux without a chemical analysis of each batch as stipulated by CC-2623.2 as discussed above, alternate methods and N requirements may be used provided they meet the intent of ^ i the code. The allowance to not reoutre a chamical i analysis of each batch of flux is based on the successful welding of studs on the liner. This change is consistent s with the applicable CPSES specification but had not previously been identified in the FSAR. 3.8-19 Revision: As previously discussed, alternate methods and requirements may be used provided they meet the intent of the code. 1) Char, V-Notch impact test temperatures: c Meti ^Jology described to establish the material transition curve which meets the intent of the code. 2) CPSES preheating requirements: Allows use of the applicable section of the ASME III B&PV Code as a generic rec uirement for preheating. A review of the ACI-359 Coce Section III found the preheating requirements to be equivalent. 3) Stud welding equipment: Allows the engineer to approve the use of other equipment on a case by case basis. Where the use of automatic welding equipment is not feasible due to space limitations during ~ construction, it is necessary to use alternate equipment. These requirements are consistent with the CPSES specification but had not previously been identified in the FSAR. 3,8-20 Editorial: Removes "CC-554C..." and inserts at correct - chronological position in text. 5 Revision: Allows the engineer to review post-weld heat treatment records in lieu of CC-4552.2.2 requirements of an inspector's review. The term inspector refers to the "ANI," however, FSAR Section 3.8.1.2.1 specifically takes exception to the requirement for an "ANI" (inspector). The code 'n force for CPSES was issued as a "Draft" document and this administrative requirement is not applicable for CPSES. .~ . ~.

AMENDMENT 68 DESCRIP' TION Attachment to TXX-88229 February 15, 1988 Page 32 of 85 FSAR Page (as Amended) Description 3.8-20 thru Revision: Allows use of alternate non-destructive 3.8-25 examination methods and acceptance standards. The alternate acceptance criteria for attachments to the liner, and non-destructive examination thereof, has been reviewed and found to be technically acceptable and meets the intent of the code. That is, the welds have sufficient size to be structurally adequate and t'ie non-destructive examinations demonstrate that the welds are free of defects that would degrade either the structural adequacy or the containment liner system. 3.8-26 Addition: Includes applicable code reference for concrete temperatures (3.8.1.2.5.2 (b)). 3.8-28 Editoricl: Corrects the version of NRC Reg. Guide 1.29 from "Revision 1, 8-73" to "Revision 2, 2-76." This change will bring the reference to Reg. Guide 1.29 into conformance with the Appendix 1A(N) and 1A(B) listing of the FSAR. Clarification: Geletes the reference to Reg. Guide 1.57 as it does not apply to Section 3.8.1 (Concrete Containment). 3.8-30 Clarification: Deletes wording "... if additive in the calculation of maximum stresses" because the words are unnecessary and confusing. 3.8-31 Clarification: This change clarifies and expands the load definitions for Wt, Yr, Yj and Ym. 3.8-35 thru Correction: Changes the description of the design and 3.8.40 analysis procedures used for the containment structure based on the reanalysis performed as part of the design validation for CPSES. 3.8-39 Editorial: Spelled out General Design Criteria. 3.8-49 See Justification for page 3.8-9. 3.8-50 Clarification: This change clarifies the statement (3.8.1.5.2) discussing allowable stress increases by adding the phrase "which include thermal." The revised l statement is consistent with the ASME-ACI 359-73 Coda and the SRP.

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 l February 15, 1988 ~ Page 33 of 85 s { FSAR Page (as Amended) Description 3.8-54 Clarification: Adds clarification that the penetration nozzles are to be designed to ASME III, Division 1. Clarification: Adds overlay plates to description.of attachments to liner. See Justification for page 3.8-12. Addition:, Adds design requirement to evaluate through the thickness properties of the liner for attachments. 3.8-66 See Justification for page 3.8-12. Editorial: Corrects to reference where clarifications are provided (Section 3.8.1.2. 5(2) (a)). 3.8-67 Revision:' Deletes UT of liner materials. The CPSES s)ecification does not require this VT inspection )ut this criteria was not clarified in the FSAR. The following provides evidence that the exception to the proposed 1973 Edition, ASME III, Div. 2, Subsection CC, (CC-3750) for UT examination of the liner plate in the vicinity of attachments would not degrade the integrity ~ f the liner systems. o During construction of the liner plate studs were applied to the outer surface. A minimum of one stud per a group of each 100 studs applied is bend tested to 15 degrees then strr.ightened. The studs are arranged on either a nominal one foot square pattern or a nominal one foot diamond pattern. For a typical liner plate which measures 30 foot by 10 foot there are approximately 270 studs. Thus approximately 3 studs per plate are bend tested. Should lamellar type defects (laminations) exist the bending of the stud would uncover lamellar defects in the area of stud bending, i Also during construction, wind bracing was attached to each ring of liner plate (Ref. CB&l Dwgs. 3A Rev. 6, 4A Rev. 7, 48 Rev. 11). The wind brace has 4 clips welded to each plate (10 foot by 30 foot). The wind brace clip then has a knee brace installed in the clip and rests on the liner. The wind brace is then supported on the knee brace and stitch welded to the liner. The clip and the stitch weld both experience a force normal to the liner plate during constructiom i.e., thermal, wind, and live loads. = j

AMENDMENT 68 DESCRIPTION s Attachment to TXX-88229 February 15, 1988 ~ Page 34 of 85 FSAR Page (as Amended) Description 3.8-67 Additional attachments to the surface of the liner which impose forces normal to the liner plate are fit-up gear, stiffeners for liner cut outs, and temporary attachments. The construction of the studs, wind bracing, and the additional attachments did not develop lamellar tearing of the liner plate. The permanent attachments to the liner at CPSES have had the welds to the liner examined by either the magnetic particle or liquid penetrant examination method. These examinations have not developed evidence of lamellar tearing of the liner plate. The requirement for the performance of UT for plates that are loaded in the through-the-thickness direction was deleted from the ASME code by the 1979 Winter Addenda, to the 1977 Edition. The NRC has considered the issue of lamellar tearing in NUREG-0577 Rev. 1(see reference A below). The staff concluded that such a research program would resolve the outstanding questions regarding lamellar tearing and that continued operation and licensing are justified during the course of the program. This is based on (1) the knowledge that lamellar tearin problem as initially thought (g is not as urgent a failures have been rare) and (2) the staff's conclusion that the likelihood of support failure as a result of lamellar tearing is small because applied stresses during operation are low and the probability of an initiating event (strong stresses on a torn joint) is very small. The staff also considers lamellar tearing to be a lower order failure mechanism than others that are possible in heavy weldments (e.g., weld toe cracking). l f e

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 Fcbruary 15, 1988 Page 35 of 85 FSAR Page (as Amended) Description 3.8-67 The staff asked the Electri: Power Research Institute (EPRI) to fund and manage a research program. Preliminary results from the EPRI program support the conclusion that the problem generally is detected and corrected during construction and that a reasonable safety factor on strength car, bound the experimental results on torn joints. Based upon the above it can be concluded that attachments to the liner, with examinations of the welds without UT examination of the liner material in the area of the attachment, can be performed without degrading the integrity of the liner system. Reference A: ' Potential for low Fracture Toughness and Lamellar Tearing in PWR Steam Generator and Reactor Coolant Pump Supports, HUREG-0577, Rev. 1, 1 Published October 1982 Government Printing Office. l 1

AMENOMENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 36 of 85 s FSAR Page (as Amended) Description 3.8-67 and Editorial: Corrects to reference where clarifications 3.8-68 are provided (section 3.8.1.2.5.2.a.) 3.8-70 Clarification: Removed the conjunction "and" and two commas to make the sentence clearer. No technical change intended. 3.8-72 Clarification: This change clarifies Section 3.8.1.7.2 to eliminate redundancy between the second and third paragraphs and avoid confusion between the periodic and preoperational Type A tests. Reporting of the maximum allowable leakage rate in a %/ day or %/24 hours format is also being clarified. 3.8-74 Correction: Provides correct ASME code applicability date and sections used for the construction of the containment liner and penetrations (3.8.2.2.1). The referenced codes are technically acceptable. Correction: Deletes codes, specifications, and standards from Section 3.8.2.2.2 as they are listed in Sections 3.8.1.2.3 and 3.8.1.6.6. - Clarification: Adds reference to Reg. Guide 1.57 as it applies to steel containment not backed by concrete. 3.8-75 thru Revision: Revises load equations and acceptance 3.8-77 criteria to be consistent with Reg.-Guide 1.57. The equations for Class MC components were not as per the licensing commitment, i.e., Reg. Guide 1.57. The revised format is clearer and similar to the format contained in the Standard Review Plan. 3.8-80 Clarification: Provides clarified description of the containment operating floor. Clarification: Removes unnecessary slab thickness dimension to provide consistency with the other discussions. Addition: Provides additional information regarding the design of the containment interior base slab. l e 'h *

• 4

^ f m* ^

AMENDMENT 68DESCRIPUON ~ Attachment to TXX-88229 February 15, 1988 Page 37 of 85 FSAR Page (as Amended) Description 3.8-81 Revision: The discussion on polar crane derailment is and 3.8-82 clarified in regard to load combinations. ASME B&PV Code, Section III, Appendix XVII, Subarticle XVII-2110 allows local plastic deformation for critical equipment parts which are required to maintain the capability of the equipment to perform its safety function (See FSAR Section 9.1.4.3.2 for fuel handling and storage equipment). FSAR Section 3.8.3.1.2 for the containment polar crane has been clarified to. identify the use of this design allowance. Also, the discussion on SSE has been deleted from this FSAR Section and expanded in FSAR Section 9.1.4.3.2. 3.8-82 See Justification for page 3.8-12. 3.8-83 Editorial: Clarifies description. Correction: Incorporates Appendix A of the ACI 349-76 code. ASME-ACI 359 Code does not provide guidance in determining thermal stresses. Therefore additional ACI Code provisions are given. ACI 307 was areviously stated as the applicable code for determining tiermal stresses. Powever. ACI 307 is not applicable to the concrete contai'nment structure. 1 1 3.8-84_ Addition:- Includes "Specification for Structural Joints using ASTM A325 of A490 Bolts" as an applicable Code. This specification has been endorsed by AISC "Specification for the Design, Fabrication and Erection of Structural Steel for Buildings." 3.8-85 See Justification for page 3.8-12. 3.8-86 Editorial: Provides correct cross-reference (3.8.3.3.1) Clarification: Corrects description of live load, since containment internal structures are not affected by outside atmospheric changes. 3.8-88 and See Justification for page 3.8-12. 3.8-89 3.8-90 Clarification: This change clarifies the discussion (3.8.3.3.2.2) of allowable increase in local strength capacities to match the wording contained in the Standard Review Plan. See Justification for page 3.8-12. i i e g g ye g>* - ^ ~ - -

'AMENDHENT 68 DESCRIPTION. Attachment to TXX-88229 ~ c February 15, 1988 Page 38 of 85 FSAR Page (as Amended) Description 3.8-91 Correction: This change clarifies the load combinations for the plastic design of steel structures as stated in the Standard Review Plan. 3.8-94 thru Correction: Changes the description of the design and 3.8-96 analysis procedures to correct inconsistencies within FSAR Sections and to reflect the new methodologies used during design validation activities. 3.8-98 See Justification for page 3.8-83. Correction: Corrects description to clearly state that AC1 349-76, Appendix A is to be used for factored load combinations. The justification for page 3.8-83 provides additional information. Revision: Removes reference to Appendix A of the ACI 318-71 Code. ACI 318 is intended for Commercial buildings and the design seismic load is based on building code such as the Uniform Building Code (UBC) where the design seismic load is a fraction of the full elastic seismic load calculated based on elastic analysis. Thus, in the event of an earthquake, large deformation is expected. Therefore, the code (ACI 318, Appendix A) requires special provisions to accommodate the large deformation. For nuclear power plant structures, the structures are designed for full elastic seismic load and the provisions i in ACI 318, Appendix A are not applicable. 3.8-99 Revision: Change anchorage requirement for reinforcement to allow required length to be based on testing. The standard detail for development of reinforcement using a 900 hook is not in agreement with Chapter 12 of ACI { 318-71. New Test Data is available which allows a reduction of development length. It should also be noted that the anchorage requirements for standard 900 hooks were revised in ACI 318-83 to allow a similar reduction of development length. See Justification for page 3.8-12. 3.8-102 See Justification for page 3.8-12. See justification for page 3.8-98. .......~. ~ -

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 39 of 85 FSAR Page (as Amended) Description 3.8-105 Clarification: Clarifies note at the beginning of Section 3.8.3.6.4.1 "Materials." As previously stated, the phrase "unless otherwise noted" could be misinterpreted to mean "unless otherwise noted in the FSAR." The list of materials is not intended to be a complete listing of all structural and. miscellaneous steel material used at CPSES. This change allows the use of other acceptable materials conforming to ASTM Standards when specified by the Engineer on design documentation. 3.8-106 See Justification for page 3.8-12. 3.8-111 and Correction: Provides changes to the technical discussion 3.8-112 for outdoor seismic Category I tanks (Section 3.8.4.1.6). The changes clarify the text and make discussions consistent with analy, sis done in the validation effort. 3.8-112 See Justification for page 3.8-99. 3.8-115 See Justification for page 3.8-12. 3.8-117 Clarification: This change clarifies the discus'sion (3.8.4.3.2(2)) of allowable increases in local strength capacities to match the wording contained in the Standard Review Plan. See Justification for page 3.8-12. 3.8-118 Clarification: Clarifies load combinations for the elastic working stress design methods of steel structures as stated in the Standard Review Plan. 3.8-121 Correction: Provides changes to the technical discussion regarding design and analysis procedures (3.8.4.4). The changes make the discussion consistent with analysis done in the validation effort, i See Justification for page 3.8-12. 3.8-123 Revision: Adds Alternative design criteria for brackets and corbels when considering shear stress. This change permits design of brackets or corbels based on PCI design handbook Second Edition 1978. The PCI committee on connection details suggested this alternative me.thod place of the applicable Section of ACI 318-77. 4 ~ ~ '

AMENDMENT 68 DESCRIPTION ~ Attachment to TXX-88229 February 15, 1988 Page 40 of 85 FSAR Page (as Amended) Description 3.8-125 Revision: Presently Section 3.8.5.1.3 states a minimum of 1" gap exists at base mats. Investigation in accordance with CPRT ISAP IIc revealed that some debris existed in the separation gaps. In general, resolution of ISAP IIc requires the removal debris and maintenance of the minimum gap required by analysis. However, debris located between foundation mats may remain in place since mats are constructed on bed rock and are very stiff, resulting in minimal interaction between adjacent foundations. Hence, building response will not be affected by debris in gaps located at some foundation locations. 3.8-134 See Justification for page 3.8-12. Addition: Adds reference to reflect changes in Section 3.8.1.2.2. Editorial: Adds reference to reflect change in Section 3.8.4.5.4 of the FSAR. Table 3.8-1 Revision: The values indicated in this, Table 3.8-1 will i change based on the analysis performed during validation. Therefore, the contents in this table are being deleted. Upon completion-of-the design validation activity this summary table will be updated for each Category I j structure, showing the loading condition considered, the related stresses computed and their corresponding l allowable stresses at key locations of the structure will be provided. Figure 3.8-7 Update: Revises details to reflect as-built configureat_ ion i with proper r s and give information which is consistent eferences { { Figure 3.8-9 Update: Deletes drawing reference to revision-number and the scale to prevent mis-interpretation of the figure, i j O O 3 4 d

i AMENDMENT 68 DESCRIPTION Atta~chment to TXX-88229 February 15, 1988 Page 41 of 85 FSAR Page (as Amended) Description 3.9N-15 Editorial: Deletes the reference to boron injection tank use and inserts that these pumps now deliver cold water from Refueling Water Storage Tank (RWST). The boron injection tank was deleted in a previous Amendment to the FSAR but was missed at this location. This is a non-technical change. 3.9N-42 Revision: Revise the values used for percentage damping for reactor coolant pump seismic analyses to be consistent with percentage damping utilized for seismic analysis of Westinghouse supplied reactor internals. This revision results in a more conservative seismic analysis of the reactor coolant pump. 3.9N-83 & 84 Correction: The majority of the E-specifications covering Westinghouse supplied active valves specify accelerations of either 39/2g (horizontal / vertical) or 2.lg/2.lg/2.lg (two horizontal, vertical directions). 2.1g in three directions is the equivalent of 3g/2g in two directions. A few E-Specifications which were written i.n the latter stages of valve procurement for Comanche Peak, specify 4g/4g/4g. This did not reflect a change in CPSES design criteria, but was a result of multi-plant valve orders supplied by Westinghouse. Included in these orders were plants which were committed to the higher acceleration values (i.e., 4g/4g/4 ) - All 9 piping analyses performed by Westinghouse have maintained the valve accelerations within the limits specified in the appropriate valve E-specifications. Any valve acceleration resulting from the piping analysis which exceeds the E-Specification allowables is evaluated and resolved on a case by case basis. Likewise, the piping analyses performed by SWEC utilize the E-Specification acceleration limits for each Westinghouse supplied valve. g -v e

Attachment to TXX-88229 Fcbruary 15, 1988 Page 42 of 85 FSAR Page (as Amended) Description 3.9N-83 and An upgrade of the qualification documentation 3.9N-84 for all active valves to 4g/4g/4g would require a (Cont'd) significant effort in revising each valves calculation to addre.ss the higher accelerations. In addition, selected valves may require retesting and the potential exist for having to replace hardware if qualification to the higher levels cannot be demonstrated. Revision: Based upon the above discussion'on how the requirement to qualify active valves to the 4g/4g/4g level was incorrectly incorrected onto FJAR pg. 3.9N-72 and 71, the wording is revised to reflect the 2.lg/2.lg/2.lg level which CPSES is in compliance with and connitted to. Table 3.9N-2 Clarification:.A note is added to the Table to clarify that the consideration of the OBE for class 1 piping and valves consistent with the design basis is in agreement with the ASME Code Section !!! Division 1 and CPSES class 1 piping and valve specification. Westinghouse class 1 piping and valve specifications (E-Specs.)'do not include' the OBE in the Design Condition loading combination for f which Service Level A (Normal) limits are applicable. Rather, the OBE is included in.the Upset Service Condition loading combination for which Service Level B l (Upset) limits are applicable. This treatment of the OBE is consistent with both Regulatory Guide 1.48, Regulatory Positions C.1 and C.2; the Standard Review Plan, Appendix A, Section 1.3.2; and the FSAR Section IA(N) discussion ' of Regulatory Guide 1.48. The ASME Code Section III Division 1 provisions further supports that the treatment of OBE for class l' piping and valves at CPSES is in compliance with code requirements, i Table 3.9N-S Clarification: ASME stress limits previously referenced by the Table are directly incorporated into the Table for clarity. Table 3.9N-21 Update: Incorporation of Table which is a summary of maximum stresses in the Reactor Coolant loop piping to complete our connitment provided in Response to NRC Question 112.14. l l l - _ _b

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Paga 43 of 85 FSAR Page (as Amended) Description 3.98-19 Editorial: Editorial changes are made to page 3.98-19 of the FSAR. This is a non-technical chanc.. 3.98-26 Update: Provides a commitment to update the FSAR concerning the usage of code cases N-318, N-397 and N-411 in the design of piping and pipe supports in a future FSAR amendment. T3.98-10 Revision: Table revised to incorporate 1/2 inch check (Shts 4 and 5) valves (typical 8 places) that prevent air loss from accummulator air supply.to ensure the operability of Steam Generator PORV after loss of Instrument Air. (Shts 7, Revision: Table revised to incorporate 1/2 inch valves 8, 9 and 10) (typical 16 places) that prevent air loss from accummulator air supply to ensure the operability of Auxiliary Feedwater Regulating valves after loss of Instrument Air. (Sheet 10) Revision: Table revised to incorporate 1/2 inch check valves (typical 4 places) that prevent air loss from accummulator air supply to ensure the operability of the AFW Turbine Isolation valves after loss of Instrument Air. (Sheet 12) Revision: Valve identification and train function revised for two valves (Diaphragm Motor) to correspond to the containment spray system flow diagram. (Sheet 14) Revision: Table is revised to incorporate the addition of active relief valve CC-1067 provided to prevent overpressurization in Component Cooling Water penetration piping during Containment isolation. (Sheet 17) Revision: Table revised to incorporate 3/4 inch check valves (typical 4 places) that close on a non-safety line break to maintain nitrogen accumulator pressure. Revision: Revises this Table to show the addition of active relief valve 00-430 to Demineralized Water System penetration piping to prevent overpres::urization during containment isolation. (Shts 18 and 19) Revi< ion: Table revised to incorporate 1/2 inch check valvm (typical 4 places) that prevent accummulator air loss for Control Room Damper after a non-safety air line break. (Sheet 20) Clarification: Eliminate numerical prefix indicating Unit 1 since tag number applies to Unit 2 also. g e e P=- e 1 = ~ e I g i

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 44 of 85 FSAP. Page (as Amended) Description T3.98-10 Revision: Revises Table to show the addition of active (Sheet 20) relief valves to chilled water penetration piping, (Cont'd) classified as active valves to prevent overpressurization during containment isolation. Section 3.11N Correction: The changes in section 3.11N were intended to be incorporated in A6&. However due to problems within this section, it was pulled from A66 and is now being incorporated into A68. 3.11N-1 Revision: Reflects new consolidated table Appendix 3A Table 4-1. 3.11N-2 Update: Reflects a current status of WCAP-8587 and the new consolidated table, Table 4-1, where the NSSS equipment is listed. Revision: Describes qualification program as applied to Class 1E equipment located in a mild environment. s. 3.11N-3 Revlsion: Adds reference to the Environmental Equipment Qualification Summary Packages (EQSP) and the new Appendix 3A Table 4-1. Revision: Corrects reference from 3 to 1 since the Environmental Qualification Data Packages are supplements to the basic WCAP. Revision: Deleted references to the EQDP's for radiation and chemical environments used in NSSS equipment qualification program. This information has been incorporate into Appendix 3A Table 4-1. Table 3.11N-1, See p. 3.11N-1 2 and 3 1

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 45 of 85 FSAR Page (as Amended) Description Section 3.11B Editorial: Portions of section 3.118 are being reissued & Appendix 3A to correct typographical errors and to include changes / text that were previously omitted from A68. 3.118-2 Correction: A portion of this sentence was unintentionally omitted in A66 and is being added. Correction: Part "a" of the definition of-a potentially harsh environment should define "pressure" limitations not "temperature". 3.118-4 Correction: Part "2a" of the ESF safety related equipment ouside containment that must remain operational during or following a DBA was unintentionally omitted in A66 and is being added. 3.118-5 Correction: The word "Sumary" was unintentionally omitted in the title of Environmental Equipment Qualification Sumary Packages in A66 and is being added. 3.118-9

orrection

The word "Equipment" was unintentionally omitted in the title of Environmental Equipment 'l Qualification Summary Packages in A66 and is being added. q Appendix 3A, 1-1 Correction: The word "potentially" was unintentially omitted in the reference to a potentially harsh environment. 1 l

AMENOMENT 68 DESCRIPTION Attachment to TXX-88229 February 13, 1988 Page 46 of 85 FSAR Page (as Amended) Description Notes to Revision: Revises notes to delete references to RTO Figure 5.1.2 bypass manifold connections. The RTD bypass loops were capped as a result of a modification to install N-16 power monitors (for flow measurement) and cold leg RTO thermowells (for temperature measurement). Also updates loop process data. Section 5.4.7 The RHR cooldown analysis was re-performed by Westinghouse based on validated input parameters provided by the Stone and Webster Engineering Corporation (SWEC). The SWEC input parameters included revised auxiliary heat loads and service water input temperatures which were based on conservative SWEC assumptions and methodology. The revisions to FSAR Sections 5.4 and 9.2 reflect revised input assumptions and the results of the revised cooldown analysis. The changes include ' revised cooldown rates as well as revised temperatures for portions of the RHR, CCW and SSW systems. SER Section 5.4.3 references a cooldown time of 17 hours to get from 350 degrees to 200 degrees (cold shutdown). This time has been changed in the current analysis to 21 hours. 5.4-51 Revision: Revises various times associated with RHR cooldown. Also see description under Section 5.4.7. 5.4-57 Revision: Revises a time associated with RHR cooldown. Also see description under Section 5.4.7. 5.4-67 Revision: Revises maximum component cooling water temperature during c'ooldown. Also see description under Section 5.4.7. Table 5.4-1 Revision: Revises maximum continuous cooling water (sheet 1) inlet temperature for the reactor coolant pumps. Also see description under Section 5.4.7. Table 5.4-7 Revision: Revises maximum component cooling water temperature and time to cooldown on the RHR system. Also see description under Section 5.4.7. Table 5.4-8 Revision: Revises RHR heat exchanger inlet and outlet temperatures and flowrate. Also see description under Section 5.4.7. Figure 5.4-7 Revision: Revises maximum component cooling water-(Notes sheet 1) temperature. Also see description under Section 5.4.7. Figure 5.4-8 Revision: Revises normal RHR cooldown curve. Also see description under Section 5.4.7. Figure 5.4-9 Revision: Revises single Train RHR cooldown curve. Also see description under Section 5.4.7. . ~.

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 47 of 85 FSAR Page _(asAmended) Description 6.2-60 Correction: Corrects the design pressure of the suction lines from the recirculation sumps and RWST from 50 psig to 70 psig. 6.2-69 Revision: Deletes the exception to Regulatory Guide 1.1. The NPSH calculation is performed in accordance with.- Regulatory Guide 1.1. Clarification: Adds the injection phase to the referenced phases for the determination of Containment Spray pump NPSH. Revision: Deletes the words "including a 10-percent-margin" from the description of the NPSH curve in Figure 6.2.2-2. The NPSH curves in this figure have been revised. The NPSH complies with the requirements of Regulatory Guide 1.1. 6.2-72 Clarification: Clarifies the automatic functioning of the <.ontainmeht spray pump minimum recirculation lines. 6.2-73 Clarification: Adds "channels" with reference to level signals. 6.2-78 Revision: Adds the Auxiliary Feedwater valves and Auxiliary Feedwater Turbine supply valves as valves whose safeguard function to remain open overrides the containment isolation function to close. 6.2-82 Revision: Adds the Main Steam Isolation Val _ve (MSIV) bypass valves as containment isolation valves which are normally locked closed. These valves are similar in function and in the method for providing containment isolation to the Turbine Driven Auxiliary Feedwater (TDAFW) pump steam supply bypass valves. 6.2-88 Revision: Provides an alternate criterion for - ~~ containment isolation valves in lines which provide a direct connection from the containment atmosphere to the environment but do not have closing times of 5 seconds or less (i.e. the valves are locked closed). 6.2-90 Revision: The wording which states that "each penetration is provided with test connections" has been revised since not all penetrations shown in Figure 6.2.4-1 require testing.

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 49 of 85 FSAR Page (as Amended) Description Table 6.2.4-3 Revision: Deletes items 24 and 26. These were secondary (sheet 4) sampling connections to steam generators 3 and 4. They were determined to be unnecessary and the sample lines were capped thus eliminating the need for containment isolation valves IFW-110 and 1FW-119. (sheet 6) Correction: Revised valve power failure mode in item 42. (sheet 13) Revision: Added new items lila and 111b which are thermal relief valves located inside containment for the Component Cooling Water System. These valves were inadvertently omitted from Amendment 66. (sheet 14) Revision: Valve closure time for item 122 is revised to 3 seconds. Table 6.2.4-5 Revision: Deletes items 24 and 26. These were secondary-(sheets 2 & 3) sampling connections to steam generators 3 and 4. They were determined to be unnecessary and the sample lines were capped thus eliminating the need for containment isolation valves IFW-110 and 1FW-119. (sheet 13) Revision: Added new ite's lila and 111b which are m thermal relief valves located inside containment for the Component Cooling Water System. These valves were i nad y.. tently omitted from Amendment 66. Table 6.2.4-6 Revision: Deletes items 24 and 26. These were secondary (sheets 3 & 4) sampling connections to steam generators 3 and 4. They were determined to be unnecessary and the sample lines were capped thus eliminating the need for containment isolation valves IFW-110 and 1FW-119. (sheet 11) Revision: Added new items lila and 111b which are thermal relief valves located inside containment for the Component Cooling Water System. These valves were inadvertently omitted from Amendment 66. Figure 6.2.2-2 Revision: The NPSH curves for the containment spray pumps are revised based on new calculations. The NPSH complies with the requirements of Regulatory Guide 1.1. Figure 6.2.4-1 Correction: Valve arrangement 16 is revised to reflect (Sheet 4) the proper convention for showing a test vent. ~. . ~

AMEN 0 MENT 68 DESCRIPTION Attach ent to TXX-88229 February 15, 1988 Page 50 of 85 FSAR Page (as Amended) Description 6.3-15 Revision: Revises the method by which the accumulator motor operated valves are prevented from inadvertent opening during plant shutdown. Previously it was stated that control power is disconnected from the valves via control room switches. The key lock switches in the control room are used to prevent the valves from being inadvertently closed while the RCS is above 1000 psig (See Tech Spec 3/4.5.1). However, the switches do not effect the ability to open the valves. The statement is corrected to state that during plant shutdown the valves are prevented from inadvertent opening by locking open the valve breakers after valve closure. Table 6.3-3 Revisien: Adds source range flux doubling as an (sheet 2) additional signal which causes automatic opening of the CVCS suction valves (LCV-112 B,C,D and E). Revision: Adds description of alarm function for the CVCS normal discharge valves which was previously inadvertently omitted. (sheets 3 & 4) Addition: Adds description of additional motor operated ECCS isolation valves (charging pump miniflow isolation valves. RHR hot leg suction isolation valves, charging pump miniflow isolation bypass valves, charging pump relief isolation valves and RHR pump recirculation valves) which were not previously included. 6.4-2 Lorrection: Revises the table reference from 6.5-2 t.o 6.5-6. Revision: Provides a statement that a concurrent release of toxic gas due to a seismic event and a radiological release due to a LOCA is not considered in the design basis. This is because: 1 1 i 1 i l j

' AMENDMENT 68 DESCRIPTION

Attachment:

to TXX-88229 February 15, 1988 Page 51 of 85 FSAR Page (as Amended) Description 6.4-2

1. CPSES is located in an area of very low seismic activity.

Therefore the probability of a significant seismic event is extremely low. The seismic design of the Reactor Coolant System precludes a seismic event as the cause of a LOCA. The probability of a LOCA (from any cause) is very low. Thus the probabilit seismically induced toxic gas (chlorine)y of a release (from the circulating water chlorination facility) concurrent with a radiological release from an independently caused LOCA is extremely low, essentially zero. 2. Even if concurrent toxic gas release and radiological release were postulated, the effects should not be worse than either release occurring independently. This is because of the location of the control room air intakes relative to the sources of chlorine and the LOCA fission products. For a postulated chlorine release to be significant, the wind direction would have to be such that the chlorine is blown toward the control room air i nt aki.s. kosever, this wind direction will cause the l LOCA teleases to propagate away from the control room. Therefore, the simultaneous release of both is not - l significantly worse than the release of either individually. 6.4-3 Revision: Deletes "...in the plant ventilation discharge vent stacks and...".- The design no longer uses a signal from the plant vent stacks to switch to the recirculation made. 6.4-4 Clarification: Clarifies sentence to read "where continuous or f'requent operator occupancy may be required" instead of "which require". Clarification: Provides a more detailed listing of the rooms within the control room envelope. Correction: Provides the correct name for the control room HVAC and equipment rooms. 6.4-5 Correction: Revises referenced figure to 9.4-1. Clarification: Deletes previous reference to 10CFR50 App. A, GDC 19. This reference was not clear and is not necessary in this description. ..s ,,m

AMENOMENT 68 DESCRIPTION i Attachment.to TXX-88229 February 15, 1988 Page 52 of 85 FSAR Page (as Amended) Description 6.4-11 Clarification: Defines the isolation mode as the preferred ventilation mode for chlorine events. Revision: Adds a new paragraph to the Toxic Gas Protection section to describe the analysis performed to verify that the rupture of non-seismic refrigerant lines in the control room pressure boundary would not cause the refrigerant concentration released in the area to exceed acceptable levels. 6.4-16 Revision: Adds new reference for the refrigerant analysis described undor 6.4-11. Table 6.4-1 Revision: This table is revised to list noble halogen inventories release after an accident (ps and the table previously listed the instantaneous direct gamma source strength). The new table provides the source strength used in the CPSES design. Table 6.4-2 Revision: Deletes this table. The data used in the CPSES design is found in Table 6.4-6. Table 6.4-3 Clarffication: Adds footnote to indicate that the control room is in the isolation mode during chlorine or smoke events and thus the control room is not pressurized. Revision: Adds the operator radiation doses to this table.

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229' February 15, 1988 1 Page 53 of 85 FSAR Page (as Amended) Description i 6.5-10 Correction: Adds number of spray nozzles (48) in the I lower ring. This number.was previously inadvertently omitted. 6.5-11 Revision: Revises the orientation and number of nozzles for the Region 8 spray headers. 6.5-14 Revision: Revises opening time of the spray pump { isolation valves. The new opening time is based on 1 controlled throttling of the discharge flowrate to prevent the containment spray pump runout. 6.5-20 Revision: Provides the total volume in containment which is sprayed and the percentage of containment free volume which that represents. Table 6.5-6 Revision: Revises the table based on the Westinghouse, "Radiation Analysis Design Manual, Standard Plant Model 412," Revision 3 as applied to CPSES. 4 1

AMENDNENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 54-of 85 FSAR Page (as Amended) Description 7.1-15 Correction: Reflects the correct year, 1974, for IEEE Standard 308 which CPSES complies to. 7 ~.1 -26 Correction: Adds word "Series" which was inadvertently omitted from the title for the 7300 Series Process Control Equipment. 7.3-12 Revision: Deleted "RWST level" from the text since there is no local level indication at the RWST. In addition, the level alann for the spray additive tank is "low-low" level alarm instead of "low" level alarm. 7.3-92 and Addition: Adds a description to clarify the difference 7.3-93 between valves and dampers and the 6.9kV pump override circuits. For valve and dampers, the position of the spring actuated control switch determines the component - position. When switched the components are in an alternate position and when released the components return to their original position. When pumps are switched to the stop position, the control switch must be held in the stop position if the sequencer has not timed out. However, if the sequencer has timed out, the pumps must be restarted manually when the initiating condition has cleared. Continuous indication when overriding a pump is d.isplayed in the control room. The override and the indication is automatically removed when the initiating condition is cleared. med' 4 t. a +

AMENDMENT 68 DESCRIPTION s Attachment to TXX-88229' February 15, 1988 Page 55 of 85 FSAR Page fasAmended) Description 7.4-19 Correction: Identifies type of cause for which a Control Room evacuation is expected and for which the event could degrade Control Room equipment. 7.5-7 & 7.5-17 Clarification: Added the word "variables" to be consistent with the remainder of this chapter. 7.5-19 Clarification: Deleted the word "Control" from the title Reactor Coolant System Inventory to be consistent with the remainder of this chapter. Table 7.5-5 Correction: Adds the word "Centrifugal" to be more (Sheet 3) descriptive with regard to the charging pump. (Sheet 5) Correction: Corrects the title for the Primary Plant Exhaust Fan Cooler. 7.6-16 Revision: Delete "torque" from the alarm requirement. The alarm requirements for the accumulator isolation valve for indication of valve malpositioning when the RCS pressure is above the SI unblocking pressure is not the torque limit switch. The torque limit switch does not monitor valve position. i i I

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 56 of 85 FSAR Page (as Amended) Description 8.1-9 Correction: Consistent with Amendment 66, the version of the IES Lighting Handbook in use at CPSES is the Application Volume, 1981. 8.1-12 Clarification: Clarifies compliance to IEEE Std. 494-1974 at CPSES. The. description is moved from Section 8.3 and placed here as a more appropriate location. A description of vendor supplied documents and drawings is added. 8.3-9 Clarification: Clarifies that 40 degrees reflects the setting of the synchronism check relay and not the actual value where transfer will occur. ' Addition: Adds time of transfer and disable function to description, 8.3-10 Clarification: Clarifies that the 30 second delay is a normal part of the circuitry and gives basis. 8.3-13 Clarification: Clarifies non-Ciass 1E loads which are isolated from Class 1E loads via reference to revised Section 8.3.1.2.1.7.a. for consistency. 8.3-16 Clarification: Clarifies that the control switches are-for Class 1E 480-V Switchgear incoming supply and bus tie circuit breakers. 8.3-40 Correction: Consistent with A'mendment 66, corrects the number of offsite power sources available to the Class IE AC buses. The Class 1E buses can no longer be backfed through the main step-up transformer and auxiliary transformer, 8.3-42 and 8.3-49 Clarification: Moves discussion that "... adequacy of penetration protective devices to protect the penetrations is established by detailed calculations..." i from the end to the beginning of the discussion of compliance with Reg. Guide 1.63 for clarity. 8.3-42 thru 8.3-49 Revision: Updates the containment electrical penetration protection description to the latest design review calculation. x.

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 ~ February 15, 1988 ~ Page 57 of 85, s FSAR Page (as Amended) Description 8.3-49 & 8.3-50 Revision: Revises the description of non-Class 1E loads I connected to Class 1E buses and describes the methods of separation used, based on current design review. This revision requires review and update of the SER (Section 8.4.5). Isolation transformers will no longer be used for an isolation device. Additional information is provided on associated circuits. Greater detail is provided by new Table 8.3-11. The isolation devices provided meet the criteria and pdrformance requirements of IEEE Std. 279-1971, Rev.1, and the electrical isolation methods comply with the intent of IEEE Std. 384-1974. 8.3-51 ' Clarification: Clarifies the discussion on isolation devices used at CDS5! between. Class 1E and non-Class 1E control circuits. 8.3-52 Addition: Adds description of separation provided for non-Class 1E security lighting. Separation is provided by two separate Class 1E feader breakers connected in series. These breakers are coordinated with their supply i breaker and will be tested periodically to. ensure that coordination is maintained. 8.3-59 Correction: Corrects the-description of equipment tag numbers to reflect the current equipment tagging procedure. 8.3-60 & 8.3-61 Editorial: The color code for "Ortnge" is the symbol "0" (Amendment 65). Due to the computerized format of the FSAR this symbol is not repeatable between amendments and therefore the phrase "O with a slash' will be used to designate this symbol. 8.3-61 Addition: Adds nomenclature used for associated trains. 8.3-62 Correction: The discussion is now in Section 8.1.5.2 which is referenced and redundant information is removed. 8.3-68 Correction: Deletes discussion on isolation device and associated cables. Discussion in revised Section j 8.3.1.2.1 applies. 8.3-71 Revision: Replaces exi.iting table with text for describing instrumentation and control circuit minimum separation criteria. Adris criteria for certain AWG wire sizes. Clarifies methods of separation which can be used. i .._.e

AMENOMENTi>8 DESCRIPTION s Attachment to TXX-88229 February 15, 1988 Page 58 of 85 FSAR Page (as Amended) Desc ri,'t i on 8.3-75 Clarification: Clarifies reference to separation between associated cables and non-Class 1E and Class 1E channels and redundant train cables. 8.3-83 Correction: Consistent with Amendment 66, adds reference i to Tables 8.3-48 and 8.3-4C in text. i 8.3-85 Correction: The discussion is now in Section 8.1.5.4. i 8.3-88 Addition: Adds "conduit support design is adequate" to conduit fill criteria. Table 8.3-1A Correction: Corrects number of Technical Support (sheet 3) Center isolation transformers to two. l Table 8.3-1B Correction: Adds total kW back to table. i (sheet 7) Table 8.3-2 Addition: Adds kW for Containment Air Radiation (sheet 3) Monitoring System sample pump to table. The value was not previously specified. 4 (sheets 10 & 11) Correction: Adds value for for Containment Air Radiation Monitoring System sample pump to total kW values for table. Tables 8.3-4, -4A, Update: Updates tables for 125-VDC Class 1E battery load -4B & -4C requirements based on new design calculations by SWEC. Table 8.3-7 Clarification: Deletes "and supplied by Train B battery" (sheet 2) since the redundant loads will not necessarily be supplied off the battery but could be on the charger or alternate power supplies. m., Table 8.3-11 Addition: Adds new table which describes non-Class 1E loads connected to Class 1E Power buses and the methods. ..of separation used, based on the current design review. 8A-1, 8A-2 & 8A-5 Revision: Adds two applications of splices in raceways justified by Appendix 8A (thennocouple reference junction boxes and field routed power cables spliced in manholes). 8A-8 Correction: Scope describes splice types by groups, not drawing details. Group 2 is depicted by drawing detail 18. .a

AMENOMENT 68 DESCRIPTIO0 Attachment to~TXX-88229 . February 15, 1988 Page 59 ci 85 FSAR Page (as Amended) Description 9.1-15 Revision: Adds GDC 1 as it applies to safety related-portions of spent fuel pool cooling and purification system. Deletes GDC 3 as fire protection program does not apply to this system. Adds GDC 56 as it applies to containment isolation portion of the system (for skimmer line). Adds GDC 61 as it applies to this system for capability i of periodic testing, provisions for containment of radioactivity and decay heat removal from the spent fuel, reduction in fuel storage inventory under accident condition and purification of the pool water. Adds GDC 63, as it app)fes to the monitoring systems to detect loss of heat removal, excessive radiation levels, and for initiating appropriate safety action. Adds "Wet Cask Pit" in the list of components served by this system, j 9.1-16 Revision: Deletes one loop operation for case no.1 as single active failure need not be postulated for full load core (see SRP 9.1.3). Deletes all the references in the Section 9.1.3. -l 9.1-17 Editorial: Corrects typo error from "in" to "is". Correction: Corrects the unit measurement of maximum activity of fission and corrosion products consistent with table 9.1-1. 9.1-25 Revis!on: Deletes reference to one loop operation as per page 9.1-14 (above) Table 9.1-1 Editorial: Revises the table to show the number of years af ter the plant is operational instead of actual years, since the startup dates for units 1 & 2 have been changed. Revision: Revises the table for decay heat produced, maximum SFP temperature and temperature rise time columns to indicate the latest revised data based on a new calculation. Deletes temperatures and time to rise to 1800F for full core unloading and one cooling loop operation (see page 9.1-14). l 4

. AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 ' ~ fcbruary 15, 1988 Pago 60 of 85 ~ - v.. FSAR Page (as Amended) Description Table 9.1-3 Revision: Revises "minimum developed head" to "total (Sheet 1) m dynamic head" consistent with project specifica.tions, .s. (Sheet 2) Revision: Revises design pressure of spent fuel pool demineralizers to 200 psig in lieu of 150 psig, which is s censistent with project specifications. (Sheet 3) Revision: Revises project specification and vendor drawing of the purification loop resin traps strainer to show 100 mesh, which corresponds to 0.0060 in, or 0.15 nn perforation as per ASTM standards part 41 Section E437 (1977 Edition). Table 9.1-4 Revision: Revises the startup dates to the dates after (Sheets 1 &.7) the plant is operational (see T9.1-1 above). SER IMPACT,: SER, Section 9.1.3, page 9-6, paragraph 2, -~ states "the system is in conformance with the requirements of 10CFR50, a)pendix A, GDC 2, 4, 5, 44, 46, 61 and 63". As described )y the FSAR change, the system was slso designed to meet GDC's 1 and 56, 9.2-2' Revision: Revises various SSW and CCW temperatures and time to cooldown on RHR. Also see discussion under Section 5.4.7 Clarification: Deletes sentence regarding continuous ~ ~ ~~~ supply to lube oil coolers to pumps in one of two redundant safeguard trains per unit. This sentence was confusing as written. FSAR Section 9.2.1.2.1 provides a s correct discussion. This discussion is not necessary in Ethis location. 9.2-7 Correction: Deletes figure 9.2-2 which is replaced by figure 9.2-1 for process flow and figures 1.2-45 & 1.2-46 for equipment layout, 9.2-13 Revision: Revises time to cooldown on RHR and revises m CCW temperatures. Also see discussion under Section 5.4.7 9.2-17 Revision: Adds Rotary instrument air compressor package for non safeguards loop to provide additional instrument air capacity. k s 'L h.-- y_oen.e y, DD

AMENDMENT 68'DESCRIPT!0N ~ Attachment to TXX-88229 February 15, 1988 ~ Paga 61 of 85 FSAR Page (as Amended) Description 9.2-30 Clarification: CCWS pumps train A & B control switches are located on hot shutdown panel. CCWS pump train A transfer switch is located on shutdown transfer panel and CCWS pump train B transfer switch is located on hot shutdown panel. 9.2-32 Revision: Adds "that control grade al. arms are provided for output high flow and temperature". These alarms alert the operator to a potential rupture of the RCP thermal barrier. 9.2-34 Revision: Revises as follows: a) Corrects the system title at various places in the text. b) Adds 10 CFR 50, l App-A, to GOC for the proper title, c) Adds, "system Containment penetrations are designed to the requirements as described in Section 6.2.4." 9.2-35 Editorial: Corrects the system name for the Water Treatment System. Correction: Deletes the reference to Figure 9.2-11 as it was deleted in Amendment 63,of CPSES FSAR. 9.2-36 Editorial: Corrects the system name for water treatment-System.- Revision: Revises and clarifies that the minimum quantity of water is available during normal plant operation to achieve and maintain safe, cold shutdown. This includes modes 1 through 5 of the CPSES technical specifications. Adds a description of the systems that require a seismic category I makeup supply. ~ Editorial : Corrects the system title. 9.2-37 and Editorial: Corrects the system title. 9.2-38 9.2-39 Editorial: Corrects the system name for Waste Treatment System. i 1 1 t F ~**e. g SS' 4 i***

AMF.NOMENT 68 DESCRIPTION Attachment to TXX-88229 l - February 15, 1988 Page 62 of 85 FSAR Page (as Amended) Description 9.2-47 Revision: Revises (conservatively) the basis for heat rates of cooling water discharged into the SSI from one train to two train operation. Also see discussion under Section 5.4.7. Revision: Revises basis of spent fuel pool heat loads. Also see description under Section 5.4.7 9.2-48 Correction: Corrects name of the spent fuel pool. 9.2-49 Revision: Revises temperatures for component cooling water end service water. Also see description under Section 5.4.7. 9.2-49 Revision: Revises the text based on the results from the and 9.2-50 revised safe shutdowniimpoundment heat load calculation, which uses maximum heat loads in lieu of gradient heat load during the duration of LOCA period. 9.2-50 Revision: Revises,various component cooling water temperatures. Alsy see description under Section 5.4.7. T9.2-9 Revision: Revises:the soluble silica concentration in demineralized' water to less than 0.1 ppm in lieu of less than 0.2 ppm. 0.2 ppm was an typo-error for 0.02 ppm. S)ecification MS-150 originally specified 0.02 mg/ liter w11ch is equivalent to 0.02 ppm., and was subsequently revised to 0.1 ppm to provide less restrictive concentration.of silica,but still meet the Reactor water makeup requirements.- T9.2-11 Revision: Deletes these tables (see p. 9.2-49/50above). T9.2-14 Figure 9.2-2 Revision: Deletes figure 9.2-2 as per page 9.2-7 (above). Figure 9.2-8 Revision: Deletes these figures (see P. 9.2-49/50 j above). Figure 9.2-10 ] i 9.4-1 Clarification: Provides a more detailed listing of the rooms at elevation 830 ft 0 in. 9.4-2 Clarification: Provides a more detailed listing of the rooms at elevation 840 ft 6 in. Correction: Provides the correct name for the control rocm HVAC and equipment rooms. g

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K E[DMENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 63 of 85 FSAR Page (as Amended) Description 9.4-10 Revision: Deletes "plant vent stack high radiation from the primary plant ventilation exhaust". Two redundant radiation monitors are provided for each control room intake air vent in lieu of an earlier design which employed one intake air monitor with backup from a plant vent stack high radiation monitor located on primary plant ventilation exhaust. Revision: Provides a statement that the chlorine detectors are not missile 3rotected. This is because locating the detectors wit 1in the protected area adversely effects their operating sensitivity. Credit for their operation is not taken during postulated tornado events. 9.4-11 Editorial: Deletes the sentence refering to Section 12.2.6, as that section does not exist. SERSection9.4.1,page9-21,2ndparagraph$ indicates that, "The control room emergency system automatically switches to recirculation mode upon failure of instrument air or offsite power, or upon receipt of a control room high radiation signal, a stack high-radiation signal, a safety injection signal..., as a result of the design-change

• described by this FSAR change, the SER is no longer correct and the phrase "plant vent stack high radiation signal" needs to be removed.

9.4-18, 9.4-23 and Clarification: These changes are being made for 9.4-31 consistency between HVAC components indicated on these pages and the changes made to Table 17A-1. (See justification for Table 17A-1, Sheets 21, 23 thru 26.)' Table 9.4-2 Correction: Adds elevation for valve room and corrects I minimum temperature for operating valve room in Auxiliary Building. 9.48-1 Revision: Revises the maximum indoor design temperature I to 1320F based on new calculation. Figure 9.5-43 Clarification: Clarifies the location of the (Sheet 1) information regarding the Fire Protection Water Supply System. These changes are being made to accomodate the structure of the new computer aided design drawings i provided in this amendment. The figures in this i amendment have been completely regenerated and therefore, interface points and reference drawings (figures) have been modified. 4

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l-AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 l February 15, 1988 l Page 64 of 85 FSAR Page (as Amended) Description ( Figure 9.5-43 Addition: Adds information regarding the Fire Protection (Sheet 1) Water Supply System. This change is made to reflect current design conditions. The design has been revised in this amendment to include information pertaining to the Permanent Treated Fire Protection Water Supply. Addition: Adds information regarding the Fire Protection Water Supply System. This change is made to reflect current design conditions. The design has been revised in this amendment to include information pertaining to additional required equipment (strainer and flushing valve) provided for system 334.791-5021. Figure 9.5-44 Clarification: Clarifies the location of information (Sheet 1) regarding the Fire Protection Water Sup)1y _ System. These changes are being made to accommodate t1e structure of the new computer aided design drawings provided in this amendment. The figures attached in this amendment have completely regenerated and therefore, interface points and reference drawings (figures) have changed. Correction: Corrects the technical depiction of.the Fire Protection Water Supply System. These corrections are made to replace erroneous information previously contained in the drawing. Included in these revisions are corrected typos, corrected drafting-errors, and the inclusion of omitted infonnation. Addition: Adds information regarding the Fire Protection Water Supply System. This change is made to reflect current design conditions. The design has been revised in this amendment to include information pertaining to an additional Fire Suppression System provided in the Unit 1 Turbine Building.

AMEN 0HENT 68 DESCRIPTION ~ e Attachment to TXX-88229 ~ i February 15, 1988 Page 65 of 85 FSAR Page (as Amended) Description Figure 9.5-45 Clarification: Clarifies the location of the information (Sheet 1) regarding the Fire Protection Water Supply System. These changes are being made to accommodate the structure of the computer aided design drawings provided in this amendment. Figures.9.5-45 sheet I and sheet 2 attached in this amendment have been completely regenerated from a-single sheet and therefore, interface points and reference drawings (figures) have been modified. Clarification: Clarifies the design of Fire Protection Water Sypply System Piping. Tfits change is made to reflect current design conditions. The documentaton of i design has been revised in this amendment to include information as indicated on a reissuance of the system installation drawings. Figure 9.5-45 Correction: Clarifies the design of Fire Protection 1 (Sheet 1) Water Supply System. This correction is made to replace i erroneous information previously contained in the drawing. This revision relocates a line number designation to the proper fire protection line. Addition: Adds information. irding the Fire Protectio'n Water Supply System. This change l's made to reflect' current design conditions. The de' sign has been revised in this amendment to include information pertaining to i the status of shutoff valves (locked closed vs. locked open) provided for the Cable Spreading Room Hose Station Systems. (Sheet'2) Clarification: Clarifies the location of information' regarding the Fire Protection Water Sup)ly System. These changes are being made to accommodate tie structure of the new computer aided design drawings provided in this amendment. Figures 9.5-45 sheet 1 and sheet 2 attached in this amendment have been completely regenerated from a single sheet and therefore, interface points and reference drawings (figures) have been modified. Clarification: Clarifies the design of Fire Protection Water Supply System Piping. This change is made to reflect current design conditions. The documentation of design has been revised in this amendment to include information as indicated on a reissuance of the system installation drawings.

AMENDMENT 68DESCRIPTd ~ Attachment to TXX-88229 February 15, 1988 Page 66 of 85 FSAR Page (as Amended) Description Figure 9.5-46 Clarification: Clarifies the location of the information (Sheet 1) regarding the Fire Protection Water Sup)ly System. The changes are being made to accommodate t1e structure of the new computer aided design drawings provided in this amendment. Figures 9.5-46 sheet 1 and sheet 2 attached in this amendment have been completely regenerated from a single sheet and therefore, interface points and reference drawings (figures) have been modified. Clarification: Clarifies the design of Fire Protection Water Supply System Piping. This change is made to reflect current design conditions. The documentation of design has been revised in this amendment to include information as indicated on a reissuance of the system installation drawings. Addition: Adds information regarding the Fire Protection Water Supply System. The thange is made to reflect current design conditions. This design has been revised in this amendment to include information pertaining to an additional Fire Suppression System provided in the Unit 1 Turbine Building. P Addition: Adds information regarding ttie Fire Protection Water Supply system. Thechangeismadetoreflect current design conditions. This design has been revised in this amendment to include information pertaining to additional fire hose cabinets located in the Safeguards and Diesel Generator Buildings. (Sheet 2) Clarification: Clarifies the location of the information regarding The Fire Protection Water Sup)ly System. The changes are being made to accommodate tie structure of the new computer aided design drawings provided in this amendment. Figures 9.5-46 sheet 1 and sheet 2 attached in this amendment have been completely regenerated from a single sheet and therefore, interface points and reference drawings (figures) a have been modified. Addition: Adds information regarding the Fire Protection Water Supply System. The change is made to reflect current design conditions. This design has been revised in this amendment to include information pertaining to l additional fire hose cabinets located in the Safeguards and Diesel Generator Buildings. ~.

AMENDMENT 68 OESCRIPTION A'ttachment to TXX-88229-February 15,-1988 Page 67 of 85 FSAR Page (as Amended) Description Figure 9.5-46 Addition: Adds information regarding the Fire Protection (Sheet 2) Water Supply System. The change is made to reflect current design conditions. This design has been revised in this amendment to include information pertaining to the addition of a supply system control valve in the Diesel Generator Building. Figure 9.5-47 Clarification: Clarifies the location of the information (Sheet 1) regarding the Fire Protection Water Supply System. These changes are being made to accommodate the structure of the new computer aided drawings provided in this amendment. Figures 9.5-47 sheet 1 and sheet 2 attached in this. amendment have been completely regenerated from a single sheet and therefore, interface points and reference drawings (figures) have been modified. (Sheet 2) Clarification: Clarifies the location of the installation regarding the Fire Protection Water Supply System. These changes are being made to accommodate the structure of the new computer aided design drawings s. provided in this amendment. Figure 9.5-47 sheet 1 and 2 attached in this amendment have been completely regenerated from a single sheet and therefore, interface points and reference drawings (figures) have been modified. Correction: Corrects the technical depiction of the Fire Protection Water Supply System. These corrections are made to replace erroneous information previously contained in the drawing. Included in these revisions are corrected drafting errors and deletion of incorrect information. Addition: Adds information regarding the Fire Protection Water Supply System. This change is made to reflect current design conditions. The design has been revised in this amendment to include information pertaining to the monitoring of system operation, provided for the Control Room Standpipe and Hose System. Figure 9.5-48 Clarification: Clarifies the location of the information { (Sheet 1) regarding the Fire Protection Water Supply System. These l changes are being made to accommodate the structure of the new computer aided design drawings provided in this amendment. The figures attached in this amendment have been completely regenerated and therefore, interface points and reference drawings (figures) have been modified. 1 j 3

AMENDMENT 68 DESCRIPTION l ~ Attachment to TXX-88229 february 15, 1988 Page 68 of 85 FSAR Page (as Amended) Description Figure 9.5-48 Correction: Corrects the technical depiction of the Fire (Sheet 1) Protection Water Supply System. This correction is made to replace erroneous information previously contained in the drawing. Addition: Adds information regarding the Fire Protection Water Supply System. This change is made to reflect current design conditions. The design has been revised in this amendment to include information aertaining to the modification of the type of valve to 3e used for local leak rate testing in the Unit 1 Containment Building. Figure 9.5-61 Clarification: Regenerated the complete figure using (Sheet 1) computer aided design techniques. Interface points and reference drawings have changed to accommodate the new structure of the figures. The technical basis is not affected. s i i j l ~'* ~

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AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 69 of.85 FSAR Page (as Amended) Description Figure 9.5-61 Correcton: Relocated the water supply to Alternate (Sheet 1) Access Point Guard House to reflect the current design. The technical basis is not affected. Addition: Added the connection of the temporary treated water supply to the Fire Protection System Main Loop. This supply is an interim solution to gain control of corrosion problems pending availability of the Fire Protection Treated Water Supply System. Addition: Added connections for outlying buildings Fire Sup'ression systems. p Addition: Added valve tag numbers and a hydrant detail to reflect the current plant design. Figure 9.5-62 Clarification: Deleted instrumentation details that are (Sheet 1) not part of piping flow diagrams. Revised all instrument tag numbers to conform to CPSES tag number conventions. Regen? rated the complete figure using computer aided design techniques. Reference drawings have changed.to accommodate the new structure of the figures. Correction: Added vent valves, line numbers and revised line locations to reflect current plant design. Deleted quick disconnect design from sump pump out connection. Editorial: Deleted reference to tank volumes and clarified description of levels shown. Tank volume information is contained in Sectin 9.5.1.6.1.E.2.d. (Sheet 2) Correction: Added a new figure showing details of the chemical treatments for Fire Protection Treated Water System makeup supply. This system is provided for corrosion control within the Fire Protection System. (Sheet 3) Revision: Added a new figure showing details for diesel engine driven fire pumps added as part of the Fire Protection Treated Water Supply System shown on figure 9.5-62 sheet 1. 4 ya g .;. Jai m

AMENDHENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 70 of 85 FSAR Page (as Amended) Description 10.2-27 Revision: Revises the sentence to correct the statement that "the high-pressure turbine cannot generate missiles." The statement is not supported by design documents. The original FSAR statement appears to be an interpretation error in that the high pressure turbine can prod'ce u missiles but they are bounded by the low pressure turbine missile. 10.4-37 Revision: Deletes "two to three ppm of chlorine are added" and adds "chlorine is added". The chlorine concentration limit depends on the location of sample measurement. The NPDS permit limits to the chlorine concentration 0.2 average to 0.5 ppm maximum. The statement that chlorination is not needed and that systems can be operated with extended outages in the chlorination system is deleted. Chlorine is required to min'isnize organic fouling which could lead to microbiologically influenced corrosion. 10.4-52 Editorial: Corrects the title of NRC Reg. Guide 1.32 by and 10.4-138 deleting the incorrect words, "use of IEEE standard 308-1971." 10.4-56 Clarification: Clarifies the usable volume, design ' ~ volume and the availability of the condensate storage tank volume for emergency use by the AFW system. The "12% margin" has been removed from the list of design has for the tank. The 12% margin resulted from a previous calculation of the available water. Such calculation results are descriptions that should not be tabulated under the design basis for the equipment. SER Section 10.4.9.1, page 10-15, 2nd paragraph, indicates, "The technical specifications require a ~~ minimum of 276,000 gallons of water to be reserved in the condensate storage tank". This statement is not consistent with the revised FSAR which states that 270.000 gallons of water are reserved for emergency use for the AFW system. 10.4-59 Revision: Revises description of the steam generator sampling system to delete reference to steam generators 3 and 4. They were determined to be unnecessary and the sample lines were capped.

AMEN 0 MENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 71 of 85 FSAR Page (as Amended) Description 10.4-84 Clarification: Clarifies the AFW design basis to 1) 4 hours operation at hot standby in the event of onsite/offsite power available with single failure, and

2) 2 hours operation at hot standby in the event of main steam or feedwater line breaks.

Revision: Revises flow rates to be consistent with the requirements of Westinghouse. 10.4-85 Revision: Revises Condensate storage tank volume to be consistent with the project calculations. SER Section 10.4.9.1, page 10-15, 2nd paragraph indicates, "the technical specifications require a minimum of 276,000 gallons of water to be reserved in the condensate storage tank." This statement is not consistent with the revised FSAR which states that 270,000 gallons of water are reserved for emergency use for the AFW system. 10.4-86 Clarification: Clarifies the system description for the AFW motor driven and turbine driven pump capacities. Also clarifies the pump discharge piping configuration, and deletes th'e sentence as it is duplicate of a subsequent sentence. 10.4-87 Clarification:. Clarifies _the sentence by adding the word "three" to AFW pumps. 10.4-88 Clarification: Clarifies the sentence by adding "Large break LOCA" as per the Westinghouse system description. 10.4-89 Revision: Adds ANS Safety Class 2 for AFW system to meet the requirements of a containment penetration boundary and a connection to feedwater. 10.4-94 Revision: Revises sentence to be consistent with the Westinghouse requirements that pump response time be based upon receipt of actuation signal. Also deletes the low suction pressure trip to prevent a spurious low pressure signal from tripping the Auxiliary Feedwater System. This trip is not required per system design (see LER 50-423-87-004-00 from Northeast Utility). 10.4-95 Revision: Revises the sentence to be consistent with pages 10.4-86 and 10.4-94. ~

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 72 of 85 l. FSAR Page (as Amended) Description l Table 10.4-9 Revision: Delete item 16 suction pressure as discussed (Sheet 6) on page 10.4-94 (above). l Table 10.4-10 Revision: Adds new instrument air compressor package to l (Sheet 2 of 2) provide additional instrument air etpacity, 1 I 4 F 1 1 7 f j i h 1 i 4 I a ) i ) l l 1 1 l t i j I ^'

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 Fcbruary 15, 1988 1 Page 73 of 85 FSAR Page (as Amended) Description Table 11.5-1 Revision: Corrects principle isotopes monitored (XRE 5570 A & B, XRE 5380, XRE 5895 A & B, XRE 5896 A & B). Revision: Corrects bases for alarm set points for: XRE 5701-Adds Note 4 since personnel protection is. considered in this setpoint, IRE 5698-Changes Note from 2 to 4. These are not XRE 5700 release points and setpoint is for XRE 5702 personnel protection. IRE 5566-Deletes Note 2. This is not a release l IRE 5637 point. IRE 2959 i XRE 5251 XRE 5252 1,2 RE 5503-The bases for these setpoints is leak 1,2 RE 4269 detection. Adds Note 7 to identify 1,2 RE 4270 these bases. Thestr are not considered 1,2 RE 4509 normal effluent monitors in the CPSES 1,2 RE 4510 design, 1,2 RE 4511 1,2 RE 5502 Clarification: Lists XRE 5253 separately for clarity. Revision: Adds XRE 58958 & XRE-58968 to table, i i Revision: Changes Note 6 to "iodine absorber cartridge" instead of "charcoal cartridge collector" since collectors other than charcoal may be used. Figure 11.5-1 Editorial: Editorial clarifications to provide agreement with existing plant design. l i ~

AMENOMENT 68 OESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 74 of 85 FSAR Page (as Amended) Description 13.1-3 Update: Organizational change to form the Test Department; consolidate and reassign testing and startup responsibilities and activities 13.1-5, 13.1-7 See Justification for page 13.1-3. and 13.1-10 13.1-35/ Update: Provide resume for new TV Electric 13.1-36 Personnel assignments. 13.1-56/ See Justification for 13.1-35 13.1-57 13.1-58, 13.1-59 See Justification for page 13.1-3. 13.1-61, 13.1-63 13.1-65, 13.1-66 13.1-74/ Editorial / Update: Move Manager, Startup resume from 13.1-75 Section 13.1.1 to 13.1.2 and change title to Manager, Startup and Test. 13.1-80 Update: Delete Results Engineering Manager resume, position currently open. Table 13.1-1 Update: Add the Manager, Startup and Test (Sheet 2) qualifications. Figure 13.1-2 See Justification for page 13.1-3. 13.4-2 Update: Add Test (department) to the 50RC group. 13.4-4 Update: Revise text to indicate Initial Startup program review responsibilities of the 50RC. 13.5-5 Update: Delete develoament and implementation responsibilities for t1e Initial Startup Test nrogram from the startup department. These responsiF :i'ies tre now assigned to the Test department as descr .J in Section 13.5.2.2.10 (new). Update: Add Test to list of departments responsible for developing and implementing surveillance procedures, j 13.5-10 _ Update: Change title of Manager, Startup to Manager, Startup and Test. I 13.5-14 Update: Add Svetion 13.S.2.2.10 to establish procedural j responsibilities for the new Test Department. 1 i + *~ ~~,

AMENDHENT 68 DESCRIPTI N Attachment to TXX-88229 February 15, 1988 Page 75 of 85 FSAR Page (as Amended) Description 14.2-1, 14.2-3 thru See page 13.1-3 description. 14.2-23, 14.2-25 and 14.2-30 Table 14.2-2 Revis' ion: The test requirements are revised to reflect (sheets 35a & 35b) the new startup transformer installation (Amendment 66). There is no longer a condition which overloads the Class 1E startup transformers. The deleted test was a design test i.iade at the factory on a representative apparatus. l (Sheet 57) Clarification: Clarify Acce)tance criteria section to accurately reference applica)le sections in 3.9B that 1 provide more information concerning acceptable vibration levels for piping and components that will undergo Operational Vibration testing. Figure 14.2-1 See page 13.1-3 description. Figure 14.2-2 See page 13.1-3 description. l 1 u I i Y t , Y?

- ~- ^ AMEN 0 MENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988. .Page 76 of 85 s FSAR Page (as Amended) Description i 15.4-60 . Correction: Corrects referenced Table 15.4-5'to read 15.1-4. i e a 4 l I .1 i .~. - I i ._______j

AMEN 0 MENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 77 of"85 FSAR Page (as Amended) Description Table 17A-1 Deletion: This change is to delete the reference to Note (Shts. I thru 40) 13 in the "Remarks" section of the table. This note was originally used for the SQRT audit, and the information is now maintained in the Seismic Equipment Qualification Summary Packages (SEQSPs). This change is typical throughout sheets 1 through 40 of Table 17A-1. (Sht. 1) Correction: The Tubing and Su) ports line entry is being revised to reflect the applica)le code or standard "ASME III" and code class "3". This change is editorial in nature, since the accompanying Note 41 ex)lains that the i supports are not built to Section NF of tie ASME Code. Addition: This change added line item "Piping and valves" to the list of quality assured structures, system and components for the Reactor Coolant System (RCS) which was inadvertently omitted from the table. (Sht. 2) Addition: This change adds line items "Pump Shaft" and "Pump Impeller" to the list of quality assured structures systems and components for the Reactor Coolant Pump Motor (RCS), which were inadvertently not previously included. (Sht. 3) Correction: This changes the safety class, applicable code or standard and code class to reflect the as-built design basis for the "Motor-air coolers." This change is consistent with appropriate specifications and the technical basis is unaffected. Correction: This change corrects the "Applicable Code or l Standard" and " Code Class" information for line item Lube oil piping in the RCS. This information was incorrectly shown but now is consistent with specifications. Clarification: This change from "Supports for Class 5 piping" to "Class 5 piping and supports", is being done-to include Class 5 piping and supports which can be-Seismic Category II or None. This change is provided as clarification to coincide with the revision to Note 44, which explains the methodology to detennine which seismic category applies for Class 5 piping and its supports. This methodology satisfies the requirements for Reg. 4 Guide 1.29, position C.2. l i i -W

~ AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 78 of 85 FSAR Page (asAmende<il Description Table 17A"1 Addition: This change adds line item "Positive (Sheet 4) displacement pump discharge dampener" to the list of quality assured structures, system and. components for the Chemical and Volume Control System (CVCS) which was inadverteatly omitted from the table. (Shts. 5 and 6) See Justification for Table 17A-1, Sheet 3, i "Clarification: Class 5 piping and supports." (Sht. 6) Revision: These changes to the Valve Isolation Tanks / Expansion Joints are being made to revise the safety class from "NNS" to "N/A." These changes are necessary to show that the tanks / joints have been declassified on the system flow diagrams such that they are no longer part of the containment pressure boundary and therefore, are no longer within the scope of ANSI N18.2. The use of "N/A" for the safety class is mnore appropriate with seismic Category I than "NNS." (Sht. 8) Clarification: This change from "Piping and valves (class 5), and seismic category "II" to "Valves," and seismic category "None" is to clarify that the term "Class 5" only applies to piping, not valves and equipment. The valves are not seismic Category II and QA Note C applies in lieu of Note B which applies to piping. (Shts. 8 and 9) See Justification for Table 17A-1. Sheet 3, "Clarification: Class 5 piping and supports." t 1 (Sht. 9) See Justification for Table 17A-1, Sheet 6. Clarification: Electrical penetrations satisfy both containment pressure boundary and electrical (Class 1E) criteria. Therefore, the two criteria aspects are being reflected in the appro Table 17A-1, Sheet 33)priate sections of the table (see Add "(Mechanical and electrical)" to the Penetration assemblies line entry. Correction: The Electric hydrogen recombiner line entry for "Combustible Gas Control System" is being revised because this is not a pressure boundary component. This change to the electrical criteria (Class 1E) is appropriate rather than the ANSI N18.2 criteria. This change is consistent with appropriate specifications and the technical basis is unaffected.

AMENOMENT 68 OESCRIPTION Attachment to TXX-88229 ~ February 15, 1988 Page 79 of 85 s FSAR Page (as Amended) Description Table 17A-1 (Sht.10) Clarification: This is a change.to provide claarification to show that only the Piping and valves are applicable for this line entry.(Rad. Monitor Sample Lin s" Changed from " Monitor Sample lines)" to "(Rad. Monitor Sample lines safeguard loops)." See Justification for Table 17A-1. Sheet 3, "Clarification: Class,5 piping and supports." (Sht.11) Correction: This change to the Traveling screens safety class from "3" to "N/A" is becasue these screens are a non-fluid pressure boundary component, therefore, safety Class 3 is not applicable. The "N/A" designation implies a structural item. See Justification for Table 17A-1, Sheet 3, l* "Clarification: Class 5 piping and supports." See Justification for Table 17A-1, Sheet 1. (Sht.12) Deletion: There are no RWMS piping and valves (Piping and valves (Class 5))" in the Main Steam System. Therefore, this line entry has been deleted. This change is consistent with appropriate specifications and the technical basis is unaffected. See Justification for Table 17A-1, Sheet 3 "Clarification: Class 5 piping and supports." Clarification: This change is provided to designate the specific Auxiliary Feedwater System (AFW) valves applicable to this line entry. Change from "(AFW Control I Valves)" to "(AFW Flow and Miniflow Control Valves)" for the Air accumulators. i See Justification for Table 17A-1. Sheet 1. (Shts. 13, 15 See Justification for Table 17A-1, sheet 3 and 19) "Clarification: Class 5 piping and supports." (Sht. 19) See Justification for Table 17A-1, Sheet 8 "Clarification:" Correction: This change corrects the "Seismic Category" information for line entry Gas decay (GWPS). tank drain pump in' the Gaseous Waste Processing System This information was incorrectly shown but now is consistent with specifications. l j

AMENDMENT 68 DESCRIPTION i " Attachment to TXX-88229 February 15, 1988 Page 80 of 85 FSAR Page (as Amended) Description Table 17A-1 See Justification for Table 17A-1, Sheet 8 (Sheet 20) "Clarification:" (Shts. 20 and 21) See Justification for Table 17A-1, Sheet 3 "Clarification: Class 5 piping and supports." (Shts. 21, 23 Clarification: Changes to the Containment Ventilation thru 26) Systems (HVAC) are as follows: 1) Various safety class and seismic category HVAC lhe entries are being changed f rom "3/NNS...I" to "3/NNS... I/II" respectively, because the NNS portions of the components / systems can not be Seismic Category I pe.r the classification schemes at CPSES. Therefore, Category II is the appropriate distinction to make. 2) Similarly, changes from "NNS...I" or "NHS... I/II" to "NNS... II" is because of classification schemes. 3) A change to a large portion of the Safety Class 3, Seismic Category I HVAC systems in the Fuel Handling, Safeguards and Auxiliary Buildings have been declassified to "NNS.. 11". The ductwork has been segregated into portions of safety-related and non safety-related as indicated in the specifications.

4) Changes in reference to Note 45 is because of a reanalysis performed in accordance with the CPSES 10CFR50.55(e) program.

Therefore, reference to Note 45 is no longer required. Note: These changes to the HVAC are consistent with appropriate specifications and the technical basis is 4 unaffected. (Shts 26 and See Justification for Table 17A-1, Sheet 3, 27) "Clarification: Class 5 piping and supports." (Sht. 27 and Correction: This change revises the seismic category for 28) the Fuel handling Equipment. The refueling machine is seismic Category 11, but the spend fuel handling tool is not (seismic Category "None"). (Sheet 29) Correction: Provides a change to delete "New Fuel Elevator Winch" from this table because QA requirements are not applicable for this item (not identified as safety-related). I

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^ AMENDMENT 68 DESCRIPTION Attichment to TXX-88229 February IS,1988 Page 81 of 85 FSAR Page (as Amended) Description Table 17A-1 Correction: A change to the containment accessways to (Sheet 31) indicate the correct safety class (from "N/A" to "2"), since these accessways are covered by ANSI N18.2. (Sht. 33) Clarification: Electrical penetrations satisf containment 3ressure boundary and electrical (y both Class IE) criteria. T wrefore, the two criteria as)ects are being reflected in the appropriate sectins of tie table (see Table 17A-1, Sheet 9). (Shts. 35, 36, See Justification for Table 17A-1, Sheet 3, 38 and 39) "Clarification: Class 5 piping and supports." (Sht.39) Clarification: This tank, located in the control room ceiling, maintains a supply of survival water. There are no safety-related functional requirements. Therefore, the seismic category is being changed from "I" to "II" which now indicates the correct classification for this tank. See Justification for Table 17A-1, Sheet 8. I (Sht.40) Clarification: Pipe whip restraints do not come under the scope of ANSI N18.2, therefore, the safety class should indicate "N/A" which is an editorial improvement over " ". Editorial: Corrects editorial omission for RM-21 Report Processor by including the appropriate Operations Quality Assurance Note, "C".. (Sht. 41) Clarification: This change to Note 7.is to include safety class applicability to cotainment pressure boundary (civil) components. (See Justification for Table 17A-1, Sheet 31) Sht. 42) See Justification for Table 17A-1, Sheets 1 thru 40, "Deletion:.. delete the reference to Note 13.." (Sht. 43) Clarification: This change is an editorial correction in nature to Note 26 by clarifying that QA requirements are generic to all specifications, rather than one in particular. e a m.

AMENDMENT 68 DESCRIPTION Attachment to TXX-88229 o FGbruary 15, 1988 Page 82 of 85 FSAR Page (as Amended) Description Table 17A-1 I (Sheet 45) Clarification: This change to Note 49 clarifies that conduit is not bought as raw material, therefore, the quality is not verified by sampling and testing. However, the quality of conduit should be through certification by vendor (industry 3ractice) and receipt j inspection, and conduit fittings s1ould be through certification by vendor and/or receipt inspection. Note: Note 49 as previously written could have been. misinterpreted so it is being changed to provide a clear understanding of these activities. If this change is read literally it may appear to indicate a reduction in commitment. However, this change merely corrects a poorly written note to provide a clearer description of the procedures, instructions and practices implemented and approved at CPSES. Note 44: SeeJustificationforTable17A-1$ Sheet 3, "Clarification: Class 5 piping and supports." Note 45: See Justification for Table 17A-1, Sheets 21, 23 thru 26, "Clarification: Changes to the HVAC, see change #4)." (Sheet 46) Correction: Table 17A-1 identifies the quality assurance (QA) requirements for safety-related items for CPSES which are within the scope of the nuclear QA programs established to meet the requirements of Appendix B to 10CFR50. Delete "and associated QA" to provide consistency with the other notes and to avoid redundancy. The application of IEEE-323 and any appropriate QA requirements is applied without making a special reference to "and associated QA" in the note. This change was requested (0A comment) during the sign-off review process for Amendment 66 but was inadvertently omitted. Table 17A-2 Clarification: Changes to the table are as follows: 1) Items that are safety Class 3 and not seismic Category I (which could be either II or None) are not safety-related. This change adds a separate entry for this safety class designation. 2) An item cannot be "NNS" and "Seismic Category !" because this is a conflict for fluid system components. Therefore, within the changes to Table 17A-1, either the "NNS" was changed to "N/A", or "Seismic Category I" ) became "II" or "None" for consistency, The "N/A... Category I" combination can apply to both civil or electrical items, i I et t =

AMEN 0 MENT 68 DESCRIPTION Attachment to TXX-88229 February 15, 1988 Page 83 of 85 FSAR Page (as Amended) Description 032-6 Correction: Corrects response to Quostion 032.6 to reflect the splices inside containment which are listed in Appendix 8A (which includes those associated with the electric penetration assemblies). All splices listed will be qualified to IEEE 323-1974 and IEEE 383-1974. 040-18 Addition: Adds condition that will render the diesel generator inoperable for automatic emergency start -- the diesel generator breaker CR-HSP selector switch in the HSP position. 040-145 Revision: Revises response to Question 040.109 on 480-V Safeguard bus tolerance values due to the installation of the new startup transformers (Amendment 66). 130-17 Correction: Corrects the response for Q130-17 to indicate the computer programs used as a part of the design validation for CPSES. 130-25 Correction: Corrects the response for 0130-25 to reflect the work done as part of the design validation fo.r CPSES. 130-27 Correction: Corrects the response for 0130-27 to reflect the work done as part of the design validation for CPSES. 130-29 Correction: Corrects the response for Q130-28 to reflect the work done as part of the design validation for CPSES. 212-32 thru 212-35 Revision: Replaces the previous response with a new i response that identifies the limitations of the detectors and takes into account minimum sensitivities of the detectors. The response describes how the intent of R. G. 1.45 is met. N_ 421-19 Clarification: The subject portion of the first sentence was changed from "Table 17A-1..." to "The plant Q-list (Table 17A-1)..." to more directly answer the question, i This change was requested (QA comment) during the sign-off reviews for Amendment 66 but was inadvertently omitted. 423-22 Editorial: Deletes duplicate entry.

AMENDMENT 68 DESCRIPTION ~ ~ Attachment to TXX-88229 o

a. try 15, 1988 n

1 of 85

1. 1! '

'e i t 's An> dedl Description 42s-9. d 423-44 Revision: The test requirements are revised to reflect the new startup transformer installation (Amendment 66). XST1 and XST2 supply only Class 1E buses. Only the non-Class 1E buses can be backfed via the main step-up transformer and unit auxiliary transformer. 423-63 & 423-64 Revision: The response is revised to reflect the new startup transformer installation (Amendment 66). There is no longer a condition which overloads the C1hss 1E startup transformers, n-s i t 6 I i ? i l 6 4 v v v --+.~y -.-r..

AMENDMENT 68 DESCRIPTION $+ Attachment to TXX-88229 4' February 15, 1988 Page 85 of 85 FSAR Page (as Amended) Description III.A-7 Clarification: The discussion regarding TSC personnel being required to report to the TSC within forty (40) minutes is being deleted. The specific requirement as r discussed in the Emergency Plan is to augment the i Operations Staff within 40 minutes; and is not applicable to TSC operation (i.e., Augmentation personnel are not necesarily assigned to the TSC). 1 III.A-12 Addition: Section 7.5.3.8 references Section III.A.1.2 i for the Accident Monitoring variables which are inputs to the ERF computer. This information was previoualy ommitted from Section III.A.1.2 and is now being added. 9 i I .}}