TXX-6119, Forwards Detailed Description of 861103 Amend 60 to FSAR Addressing Listed Topics,Including Editorial Corrections & Minor Updates

Forwards Detailed Description of 861103 Amend 60 to FSAR Addressing Listed Topics,Including Editorial Corrections & Minor Updates

ML20214Q085
Person / Time
Site:	Comanche Peak
Issue date:	11/25/1986
From:	Counsil W TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	Noonan V NRC - COMANCHE PEAK PROJECT (TECHNICAL REVIEW TEAM)
References
TXX-6119, NUDOCS 8612040509
Download: ML20214Q085 (20)

Text

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++ Log # TXX-6119 File # 10010 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER . 400 NORTH OLIVE STRErr, LB. 88 . DAI. LAB. TEXAS 75201 November 25, 1986 ES^" hff.UE Director of Nuclear Reactor Regulation Attention: Mr. Vincent S. Noonan, Director Comanche Peak Project Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET N0. 50-445 AND 50-446 FSAR AMENDMENT 60 DESCRIPTION

Dear Mr. Noonan:

Amendment 60 to the CPSES FSAR (dated November 3, 1986) includes revisions that address the following topics:

(1) An update to the organization descriptions (Sections 1.4, 13.1, 13.2, 13.3, 13.4, 14.2 and 17.1).

(2) A detailed description of the Comanche Switch Transmission Line (Sections 8.1 and 8.2).

(3) The description and analysis that justifies the use of splices in raceway (Sections 1A(B) and 8.3 and Appendix 8A).

(4) Clarification of spent fuel pool design and installed capacity (Section 9.1).

(5) Responses to NRC requests for additional information on Arbitrary Intermediate Breaks (Section 210).

(6) Separation criteria between conduit and cable tray (Section 8.3).

(7) Response to THI action plan to show that a plant-specific small-break-LOCA analysis is not required (Section II.K).

(8) Clarification of non-specific term " atmospheric steam relief valves" (Section 7.4).

(9) Addition of the appurtenances for two valves to the list of Class IE equipment outside the Safeguards Building (Section 3.5).

(10) Addition of two valves to the active valve list (Section 3.118).

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TXX-6119 November 25, 1986 Page 2 of 2 (11) Logic change to close. chiller isolation valves on "S" signal

.(Section 9.2).

(12) Revised potable water sampling (Section 9.2).

(13). Deleted "zero leakage" description of isolation dampers (Section 6.4).

The FSAR Amendment 60 also includes editorial corrections and minor updates.

A page by page descriptien of changes is attached. Amendment pages which do not have changes but are included in the amendment (either because they are on the opposite side of the sheet from a page that was changed or because a change shifted the existing material to a new page) are not discussed in the attachment.

Very truly yours,

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W. G. Counsil DRW/amb Attachment 1

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,, Attachment to'TXX-6119 l November 25, 1986 l Page 1 of 18 i

l CPSES FSAR AMENDMENT 60 DETAILED DESCRIPTION FSAR Page (as amended) Descriotion xviii Editorial: Adds new Appendix 8A " Analysis to Justify Cable Splices in Raceways" to Volume Table of Contents.

See Sec. 8.3 & 8A Su nmary.

Sec. 1.4 Summary Update: Changes the narrative descriptions for agents and contractors which were no longer accurate and were not required by the Standard Review Plan or Regulatory Guide 1.70, Revision 2 and were not discussed in NUREG-0797, the CPSES SER dated July,1981. For detailed qualifications and experience see Chapter 13.

1.4-3 Update: Deletes the narrative description for the Architect-Engineer, Gibbs & Hill, Inc. and adds a description of TUGC0 design responsibilities.

1.4-6 Update: Changes the organizational description for Brown

& Root, Inc.

1.4-7 and Update: Changes the organizational description for 1.4-8 Impell Corporation.

1.4-9 Update: Changes the organizational description of Impell Corporation and clarifies the scope of TUGC0 services.

i 1A(B)-31 Editorial: Changes " comment" to " comments".

1A(B)-32 Revision: Adds a discussion on Regulatory Guide 1.75, Regulatory Position C.9. This change describes the use of splices in the CPSES design for cable terminations and references the analysis to justify such use in Appendix 8A. See Sec. 8.3 and 8A Summary, f

l 1A(B)-58 Editorial: Corrects the inadvertant deletion of words (by Amendment 59) in the discussion to Reg. Guide 1.140.

i 3.5-19 Correction: The feedwater control valves and 3.5-20 associated bypass valves located outside on the Safeguards Building are non-nuclear safety related but have Class 1E appurtenances (See FSAR Section 10.4.7.5 and Figure 7.2-1). These appurtenances (actuating solenoids, limit switches, and junction boxes) are not currently listed in the FSAR among those safety related items not in reinforced concrete buildings or structures. In order for the FSAR to be complete and accurate, these components are being added to the list and referenced in the appropriate section.

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W Attachment to TXX-6119~

1C November 25, 1986' Page' 2 of 18 b

' FSAR Page

~1 e (as amended) Description

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Table 3.118-4 Correction: Adds valves FV-4650A and FV-4650B to table Sheet 3 of 6 - with their appropriate conditions of environmental qualification. - A design modification changed the valve status from " passive" to " active" requiring their inclusion in environmental qualification program.

6.4-7 Revision: Deletes the sentence' describing shutoff and isolation dampers. The "zero leakage" dampers are neither ,

required nor used as demonstrated by Calculation #0304-IPl.

7-v Clarification: Changes title of subsection from

" atmospheric steam relief valves" to " steam generator power-operated relief valves and safety valves". This is a clarification of terms since " atmospheric steam relief valves" is non-specific.

7.4-2 Clarification: Changes " atmospheric steam relief valves" to " steam generator safety valves". This is a clarification of terms since " atmospheric steam relief valves" is non-specific and only safety valves are required for Hot Standby.

7.4-4 Clarification: Changes all references of " atmospheric steam relief valves" to " steam generator power-operated relief valves". This is a clarification of terms since

" atmospheric steam relief valves" is non-specific and the steam generator power-operated relief valves are used for controlled decay heat removal when the condenser is not in service.

Clarification: Changes title of subsection from

" atmospheric steam relief valves" to " steam generator power-operated relief valves and safety valves". This is a clarification of terms since " atmospheric steam relief valves" is non-specific and both types of valves are discussed in the subsection.

7.4-5 -Clarification: Changes all references of " atmospheric steam relief valves" to " steam generator power-operated relief valves" (see discussion under 7.4-4) 7.4-6 Clarification:- Changes all references of " atmospheric steam relief valves" to " steam generator power-operated relief valves" or " power-operated relief valves" (see discussion under 7.4-4).

Clarification: Changes the sentence on redundancy. Only the safety valves are required for hot standby and safe shutdown and the correct redundancy for them is that two of four are required. The same redundancy also exists for the power-operated relief valves.

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Attachment to TXX-6119 Novemb;r 25, 1986 Page 3 of 18 FSAR Page-fas amended) Descriotion Clarification:- Deletes sentence under diversity which says "The safety and relief valves ~ are of diverse design."

Although this is true, it could mislead the reader to believe that more than the safety valves are required for safe shutdown.

7.4-7 ' Clarification: Changes.all references on page of

" atmospheric steam relief valves" to " steam generator power-operated relief valves" (see discussion under 7.4-4).

Table 7.4-2 Editorial: Corrects typographical error of "A-1EG-1L" to

-Sheet 3 "A-1EG1-L".

Correction: Changes " alternate offsite source-amperes" to

" frequency" for F-1EA2-L. The wrong functional description was given (see next two changes).

Correction: Changes "onsite source-amperes" to " alternate offsite source-amperes" for A-1EA2-2L. The wrong functional description was given (see changes above and below).

Correction: Adds to Table "A-1EG2-L 6900-V bus IEA2, onsite source amperes". This instrument is also located on the Hot Shutdown Panel but the function had previously been listed for a similarly numbered instrument (see above two changes).

Sec. 8.1 and Update: The Comanche Peak 345-kV Switchyard was designed 8.2 Summary so that new transmission lines could be added during the service life of the switchyard. The Comanche Peak to Comanche Switch Transmission Line was a planned addition originally scheduled for installation in 1983. Prior to this change, this transmission line was specifically referenced on FSAR Figure 8.1-2 and in the Final Environmental Statement (FES-OL Section 4.2.5). The installation of this line is not related to the construction of CPSES but is instead part of the planned development of the Texas Utilities Electric Company (TUEC) transmission system to maintain high quality service to our customers in the Stephenville-Brownwood area. This transmission line is jointly owned by TUEC and Brazos Electric Power Cooperative, Inc.

The conductor for the second circuit on the existing Comanche Peak to Benbrook 345-kV line is scheduled to be installed prior to operation of CPSES Unit 2.

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Attachment to TXX-6119 November 25, 1986 Page 4 of 18 FSAR Page (as amended) Description This change effects both the text and figures for Sections 8.1 and 8.2, modifying them to reflect the addition of the Comanche Peak to Comanche Switch Transmission Line, to revise the in-service dates for the CPSES units, to show the existing plant facility support power transformer and to revise the description and designation of our company to reflect the 1984 reorganization (A detailed description of the changes and their basis follows).

8-1 Editorial: Changes page number for Section 8.2.1.1 from "8.2-8" to "8.2-9".

8-11 Editorial: Changes page number of References for Section 8.2 from "8.2-13" to "8.2-16".

8-111 Editorial: Adds new Appendix 8A " Analysis to Justify Cable Splices in Raceways" to Table of Contents. See Sec.

8.3 & 8A Summary.

8.1-1 Update: Changes Section 8.1.1 to reflect the company reorganization in 1984, the current operation of the company's interconnected system, and to clarify the types of fossil fuel plants in Texas Utilities Electric Company (TUEC) (i.e., lignite, gas and 011).

8.1-9 Editorial: Corrects typographical error of " Trail-Use" to '

" Trial-Use" in item 4.

8.1-10 Clarification: Adds a description of how operability of spliced circuits are verified (continuity check) and that the splices are qualified for anticipated service conditions. This clarifies the existing description on butt-splices used in certain Class IE panels, cabinets or racks, which reflects TUGC0 commitments to ensure their acceptability (Refer to Results Report ISAP I.a.3 (Rev.

1) dated April 30,1986).

Figure 8.1-1 Update: Provides new TE-9500 transmission map updated through December 31, 1985 to reflect changes between December 31, 1980 and December 31, 1985.

Figure 8.1-2 Update: Provides updated drawing of company power grid through October 30, 1986 to reflect changes between August 2, 1978 and October 30, 1986, in both the existing and planned company power grid.

8.2-1 Update: Changes all references of " Texas Utilities (TV)"

to " Texas Utilities Electric Company (TVEC)" to reflect company reorganization in 1984.

8.2-2 Upaate/ Clarification: Changes the total number of transmission lines from "four" to "five", "TU" to "TUEC",

" lines" to " circuits" and " feeders" to " circuits" (for

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Attachment to TXX-6119 Nsvember 25, 1986 Page 5 of 18 FSAR Page (as amended) Descriotion consistency), and changes the list of transmission lines and their- respective length to reflect the new Comanche Switch circuit and a corrected mileage for the-Venus line.

This clarification reflects the installation of the new-Comanche Peak to Comanche Switch Transmission Line, reflects the company reorganization in 1984, changes references to individual conductor pairs to " circuits" for consistency, and reflects a corrected distance for the Venus line provided by the company's operating division.

8.2-3 Update / Clarification: Changes the paragraph on switchyard circuit breaker ratings to reflect the rating for the new breakers used for the new Comanche Switch line and relocates the hyphen for "close-open". This clarification reflects the new installation, which has a higher rating; the remainder are typographical corrections.

8.2-4 Update / Clarification: Changes "H-frame" to " wood H-frame", "125/250-V" to "125/250-VDC", contains some minor grammatical changes (e.g. "approximately" to

" approximate"). The type of H-frame and voltage are specified. Adds the plant facility support power transformer to the descriptive test and adds description of the existing plant facility support power (non-lE stepdown) transformer which is located on company-owned property outside the protected area; the remainder are editorial corrections.

8.2-5 Update / Clarification: Changes reflect the installation of the new Comanche Switch line (i.e., new tower installation and separations), adds the existing plant facility support power transformer to the descriptive text, changes reference of " Venus " to " future Venus" for uninstalled second circuit, corrects the distance between Benbrook and future Venus lines, and corrects "second angle of the DeCordova" to "first turn point for the Benbrook". This clarification reflects the new installation, adds description of the existing plant facility support power

- (non-1E stepdown) transformer which is located on company-l- owned property outside the protected area, corrects t

terminology for the first turn point for the Benbrook line and for the future second circuit Venus line and corrects distance between phases based on correct terminology.

8.2-6 Update / Clarification: Deletes discussion on future construction of Parker-Venus tieline as construction is

complete, corrects the terminology for the existing and l future 90 degree angle towers for the Benbrook-DeCordova l' lines and corrects the height for the Benbrook Tower

! (height for the second turn point towers was originally I

given), and adds discussion on spare startup transformer available at the site. This clarification reflects l

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Attachment to TXX-6119 November 25, 1986 Page- 6 of 18 FSAR Page (as amended) Descriotion current status of Parker-Venus tieline, corrects terminology and height for existing and future 90 degree angle towers for the Benbrook-DeCordova lines, and-

-provides information on the spare startup transformer.

8.2-7 Clarification: . Changes "125-V" to "125-VDC" to specify the type of voltage.

8.2-8 Update / Clarification: Changes' list of 345-kV transmission line conductor sizes to raflect new Comanche Switch

. installation, . adds the proper units to conductor-size (MCM), and changes "2-1590 ACSR" to "2-795 MCM ACSR" for Benbrook and part of Venus (for 24.62 miles). This clarification reflects the new installation, the proper units for the conductor size, and the actual conductor-

-size used for installation of the Benbrook line and portions of Venus line as provided by company's operating division. Note: 1) conductor size was and continues to be selected based on projected system configuration and power flows, 2) the Benbrook line was limited by tower size between DeCordova and Benbrook to 2-975 ACSR, and

3) the 2-795 MCM ACSR portion of the Venus line was an existing line which was tied to CPSES with the 2-1590 MCM ACSR portion.

8.2-10 Editorial: Corrects typographical error of "multiunit" to

" multi-unit".

i 8.2-11 Editorial: Minor grammatical change to delete two unnecessary "the"'s and changes "ESE" to "ESF".

(- t 8.2-12 Update / Clarification: Adds Comanche Switch to list of 345-kV transmission lines and changes "line" to " circuit" in same sentence (for consistency - see description for I

8.2-2), changes "TU" to "TUEC", changes "five percent" to "5.7 percent", deletes reference to specific in-service dates for the CPSES units, and contains minor typographical corrections (e.g. "345kV" to "345-kV").

This clarification reflects the new Comanche Switch line installation, reflects company reorganization in 1984, reflects changes in ERCOT load since 1979, reflects change .

in the in-service dates for CPSES, and makes reference to I i' conductors more consistent (i.e. circuit); the remainder are typographical corrections.

[ 8.2-13 Update / Clarification: Deletes reference to specific in-service dates for the CPSES units, and contains minor typogra-phical corrections (e.g. "345kV" to "345-kV").

This change reflects the change in the in-service dates for CPSES; the remainder are typographical corrections.

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.e Attachment to TXX-6119 N:vember 25, 1986' Page 7 of :18

-l FSAR Page -

- (as amended) Descriotion 8.2-14 Update:. Changes "The Texas Utilities operating companies

- are members of the Texas Interconnected System..." to "TUEC is a member of ERCOT...", changes " TIS" to "ERCOT",

- and contains minor typographical . corrections. This

. clarification reflects the company reorganization in 1984 n '

and the formation of ERCOT; the remainder are typograph; cal corrections.

8'. 2 - 15 ~ Editorial: Minor grammatical and typographical corrections.

. Figure 8.2-1 Update: Adds new Comanche Switch transmission circuit installation.

Figure 8.2-2 Update: Adds new Comanche Switch transmission circuit

- installation and updates figure to expected configuration for placing Unit 1 in service.

Figure 8.2-3 Update: Adds new Comanche Switch transmission circuit installation and updates figure to expected configuration 7

for placing Unit 2 in service.

Figure 8.2-4 Update: Adds new Comanche Switch installation, adds exis- .

ting plant facility support power transformer, and adds circuit breaker disconnects which previously weren't shown.

Figure 8.2-5 Update: Adds new Comanche Switch transmission circuit installation and adds drawing details (based on current constructiondrawing).

Figure 8.2-6 Update: Adds new Comanche Switch transmission circuit F

installation, adds minor drawing details and deletes L unnecessary notes (based on current construction drawing).

Figure 8.2-8 Update: Adds new Comanche Switch transmission circuit and adds minor drawing details (based on current construction drawing).

Figure 8.2-12 Update: Adds new Comanche Switch transmission circuit and existing Plant Facility Support Power Transformer.

i Sec. 8.3 and Revision: This change incorporates an analysis performed

! 8A Summary to justify the use of cable splices in raceways to

! terminate field cables at CPSES. The incorporation of this analysis into the FSAR complies with Regulatory Guide 1.75, Revision 1, Regulatory Position C.9. An advance l copy of this FSAR change was provided to NRR by TUGC0

letter TXX-6014 dated October 3, 1986.

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N2vember 25, 1986 Page .8 of 18 i l

FSAR Page.. l (as~ amended). .Descriotion This change consists of an additional comment on Regulatory Guide 1.75 in Appendix 1A(B), the creation of a new Appendix 8A, to incorporate the analysis, and appropriate changes to Section 8.3 and the indices for consistency (A detailed identification of the changes and their basis follows).

8.3-40 Editorial: Adds reference to Appendix 1A(B) under discussion of Regulatory Guide 1.75 for consistency.

Information Only, i 8.3-51 Editorial: Adds reference to Appendix 1A(B) and Appendix 8A under discussion on cable separation for consistency.

Information Only.

8.3-53 Addition: Adds a description of the conduit to cable tray separation to the existing cable tray to cable tray separation to clarify the methodology used at CPSES for separation of conduit and cable tray for compliance with '

the requirements of IEEE Standard 384-1974 and Regulatory Guide 1.75 (Rev. 1, 1/75).

8.3-54 Clarification: Changes "as stated in the beginning of

'this section" to "as. stated above", changes " solidly enclosed raceways or other barriers" to " solid tray covers, bottoms, or other barriers", removes an unneeded  ;

"these", and adds "IEEE-384" to Regulatory Guide 1.75.

This clarification makes the paragraph clearer to the '

reader-by cleaning up the English, ' replaces an undefined

" solidly enclosed raceways" with specifics, and adds an appropriate reference (IEEE-384). I 8.3-60 Correction: Changes " electrically interlocked" to

" mechanically interlocked" for the battery charger circuit breakers. Clarification in that all figures in Section 8.3 had correctly shown these breakers as mechanically interlocked, while the text had incorrectly said electrically interlocked.

Appendix 8A Revision: New appendix describing CPSES analysis to justify cable splices in raceways. This appendix is based upon the analysis submitted to NRR by TUGC0 letter TXX-4839 dated June 6, 1986. References to specific i procedures and drawings in the original analysis have been removed for usage in the FSAR. See Sec. 8.3 and 8A Summary.

9.1-5 Correction: Revises the design bases description to i reflect the " design" storage capacity in the Number 1 and  !

2 spent fuel pools. '

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+ Attachment to TXX-6119 N:vember 25, 1986 Page 9 of 18 FSAR Page las amended) Description 9.1-6 and. Correction: Revises-the facilities description to reflect 9.6a the total " design" storage space and the miminum installed capacity for the pools when Unit I receives its operating license.

9.1-7 Editorial: The typographical error "ve".is corrected to "be".

9.1-9 Clarification: -Deletes the statement that both pools are required in the event that an entire core must be unloaded from one of the units for inspection. At the time Unit 1

. receives its operating license, the Unit I spent fuel pool I will have a minimum storage capacity of 260 fuel assemblies with 16 inch center-to-center spacing. This installed capacity will allow for the full core off-load of Unit I fuel or the spent fuel from approximately 4 refueling outages.

1 9.1-11 Editorial: The typographical error "keff g 0.95" is '

corrected to "keff < 0.95".

9.2-28 Correction: Adds "and Letdown Chillers" to Section l 9.2.2.5.3.2 item 6 title and following sentence to text:

"In addition, the CCWS inlet and outlet valves to the ventilation chiller and letdown chiller condensers are closed automatically on an "S" signal." Design modification changed valve status from " passive" to

" active" necessitating the ability to close these valves on an "S" signal (FV-4650A and FV-46508).

9.2-29 Correction: Changes Section 9.2.2.5.3.2 item 9.f to add

" letdown chiller condensers" and changes " ventilation condensers" to " ventilation chiller condensers". Design modification now includes the letdown chiller condensers isolation valve as closing on "S" signal due to reclassification from " passive" to " active". This change also clarifies terminology and number (all ventilation chiller condensers isolate off one inlet and one outlet valve versus a pair for each chiller condenser).

9.2-33 Correction: Corrects the discharge location for the Water Treatment System from the evaporation pond to the Low Volume Waste Treatment Facility to make it consistant with Sections 9.2.3 and 9.2.8 as updated in Amendment 52.

9.2-36 Correction: Changes the sewage treatment plant capacity from 10,000 gpd to 105,000 gpd. This change revises the capa-city of the treatment plant to reflect actual plant conditions.

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Attachment to TXX-6119 Nav mber 25, 1986 Page 10 of 18 FSAR Page (as amended) Description 9.2-38 Revision: Changes the requirement for drawing samples of potable water from several buildings to a single sample drawn daily. This change-is consistent with the Texas Department of Health Drinking Water StandardsSection VI, Paragraph A..

10.4-134 Update: Assigns a' number to a Westinghouse memo which is listed as reference number 19 in section 10.4. At the time of entry into the FSAR, the number was not assigned.

13.1-1 Update: Provides distinction between the TUGC0 fossil and nuclear groups and defines the general scope of the new TUGC0 Nuclear Engineering and Operations (NEO)-Group.

13.1-2 Update: Changes the responsible organizations to the NE0 divisions.

Editorial: Substitutes " Engineering and Construction division" for "TUGC0 Nuclear Engineering and Construction".

13.1-3 Editorial: Substitutes " Nuclear Operations" for "TUGC0 Nuclear Operations".

Update: Deletes the position of Director of Start-up.

The Manager, Start-up has assumed responsibility for the start-up and test program.

Clarification: Changes the description of where technical

• services and back-up support for Nuclear Operations can be obtained within TUGCO.

13.1-4 Editorial: Deletes the unnecessary words " corporate" and

" administrative".

Editorial: Changes the format for the responsibilities of the Executive Vice President, NE0.

Editorial: Changes the format for the responsibilities of the Manager, Safeteam.

13.1-5 Update: Changes the text to reflect the responsibilities of the Vice President, Nuclear Operations.

Update: Changes the text to reflect the responsibilities of the Manager, Plant Operations.

Update: Changes the text to reflect the responsibilities of the Director, Nuclear Training.

Update: Changes the text to reflect the responsibilities of the Superintendent, Support Services.

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y;; y Attachment to TXX-6119 November 25, 1986 Page 11 of 18 FSAR Page (as amended) Description 13.1-6 Update: Deletes the position of Director of Start-up.

Update: Changes the text to reflect the responsibilities of the Operations Performance Evaluation Engineer.

Update: Changes the text to reflect the responsibilities of the Manager, Start-up.

Update: Substitutes "Vice President, Administration" for "Vice President". Contains changes which reflect the responsibilities of the Vice President, Administration.

13.1-7 Update: Changes the text to reflect the responsibilities of the Health Physics Supervisor.

Update: Changes the text to reflect the responsibilities of the Supervisor, Engineering and Administrative Services.

13.1-8 Update: Changes the text to reflect the responsibilities of the new position of Director, Nuclear Services.

Update: Changes the text to reflect the responsibilites-of the new position of Project Engineer, Nuclear.

Update: Changes the text to reflect the responsibilities of the new position of Project Manager, Records.

Update: Changes the text to reflect the responsibilities of the Vice Presidont, Engineering and Construction.

13.1-9 Update: Deletes the position of Project Manager - Unit 1.

Update: Changes the text to reflect the responsibilities of the Director of Engineering.

Update: Changes the text to reflect the responsibilities of the Director of Construction.

Update: Changes the text to reflect the responsibilities of the new position of Director of Projects.

13.1-10 Update: Substitutes "Vice President, Nuclear Engineering" for "Vice President". Contains changes which reflect the responsibilities of the Vice President, Nuclear Engineering.

Update: Changes the text to reflect the responsibilities of the Manager, Nuclear Licensing.

Update: Removes discussion of the Manager, Nuclear Fuel Services from the FSAR.

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IE - Attachment to.TXX-6119 N:,vember 25, 1986 Page 12 of 18 '

,FSAR Page (as amended) Description Update: Changes the text to reflect the responsibilities of the new position of Director, Reactor Engineering.

13.1-11 Update: Changes the text to reflect the responsibilities of the Director, Quality Assurance.

Update:~ Changes the text to reflect the responsibilities of the Manager, Quality Assurance.

Update: Changes the text to reflect the responsibilities ,

of the Manager, Quality Control.

Update: Changes the text to reflect the responsibilities of the new position of Manager, Operations QA. The previous position of Operations Quality Assurance Supervisor (who reported to the Manager, Plant Operations) was deleted in favor of the new position of Manager, Operations QA (who reports to the Director, Quality Assurance).

13.1-12 -Update: Substitutes "Vice President, Support" for "Vice President, Nuclear Support". Contains changes which reflect the responsibilities of the Vice President, Support.

13.1-17 and Update: Substitutes "Vice President, Administration" for 13.1-18 "Vice President". Contains changes which reflect current j membership activities.

13.1-19 Update: Substitutes "Vice President, Support" for "Vice President,-Nuclear Support".

l 13.1-20 Update: Substitutes "V'ce President, Nuclear Engineering" for "Vice President". Deleted unnecessary discussion of responsibilities on resume'.

13.1-22 Update: Deleted unnecessary discussion of responsibilities on resume'.

13.1-24 Update: Substitutes " Director, Quality Assurance" for

" Director of Quality Assurance".

13.1-25 Update: Corrected description of TUGC0 job position.

13.1-27 Update: Changes the text to show the Manager, Quality Assurance as a TUGC0 employee.

l 13.1-29 Update: Changes the text to show the Manager, Quality l

Control as a TUGC0 employee.

'13.1-32 and Update: Provides resume' for the new position of r 13.1-33 Director, Reactor Engineering.

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f Attachment to TXX-611'9.

November 25, 1986

- Pege 13 of 18-FSAR Page fas amended)' Descriotion Update: Removes resume' of the Manager, Nuclear Fuel Services from the FSAR.

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13.1-34'and Update: Changes the text to reflect the continued 13.1-35 education of the Health Physics Supervisor and to reflect current membership activities.

13.1-38 and Update: Provides resume' for the Manager, Start-up.

13.1 13.1-40 and Update: Provides. resume' for the new position of 13.1-41 Director, Nuclear Services.

13.1-42 and Update: Provides resume' for the new position of 13.1-43 - Project Engineer, Nuclear.

13.1-44 and Update: Provides resume' for the new position of -

13.1-45 Project Manager, Records.

13.1-50 Update: Deletes resume' of the previous Director of Construction (who also served as the Director of Start-up).

Update: Deletes resume' of the old position of Project Manager, Unit 1.

13.1-53 Update: Changes the text to place the overall operation responsibilities of CPSES under the Vice President, Nuclear Operations (instead of the Manager, Plant Operations).

Update: Removes the Operations Quality Assurance Supervisor (now the Manager, Operations QA) from the direction of the Manager, Plant Operations.

I 13.1-58 Update: Deletes from the Results Engineer the responsibility to provide onsite licensing and engineering

(. support to all CPSES departments.

r 13.1-59 Update: Changes the text to show the new reporting i

relationship for the new position of Manager, Operations

[ QA.

Update

Removes the position of Personnel Supervisor from i the FSAR description of the Administrative Department.

The responsibilities for this position are currently being redefined.

13.1-61 Clarification: Provides a rewrite of the Computer Services Supervisor's responsibilities.

13.1-66 Update: Changes the text to show the previous Maintenance l Superintendent as the present Engineering Superintendent. ,

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-0 Attachment to TXX-6119 N:vember 25, 1986 Page 14 of 18 FSAR'Page

-(as amended) Description 13.1-70 Update: Provides resumefor the new Operations Superintendent.

13.1-71 and Update: Provides resume' for the new Results. Engineer.

13.1-72 Deletes resume' of the previous Results Engineer.

-13.1-73 and Update: Changes the text to show the previous I & C 13.1-74 Engineer as the present Maintenance Superintendent.

13.1-76 and Update: Changes the text to show the previous 13.1-77 Operations Quality Assurance Supervisor as the present Manager, Operations-QA.

13.1-79 and Update: Provides resume' of the Operations Engineer.

13.1-80 T13.1-1 Update: Substitutes the " Manager, Operations QA" for the

" Operations Quality Assurance Supervisor". Deletes the unnecessary qualification of " Desirable, but not niandatory" under the B.S. Engineering column for the Manager, Operations QA.

'T13.1-2 Editorial: New format.

F13.1-1 Editorial: Re-print.

F13.1-2 Update: Changes the figure to reflect the new Nuclear Engineering and Operations (NED) Group.

F13.1-3 Update: Changes the figure to reflect the new station organization.

F13.1-4 Editorial: Re-print.

13.2-13 Update: Removes reference to Manager, Nuclear Operations and Superintendent, Operations Support.

13.3-2 Update: Removes reference to Manager, Nuclear Operations.

Reflects present reporting requirements and delegation authorities between the Vice President, Nuclear Operations and Manager, Plant Operations.

Editorial: Removes reporting requirement previously discussed in Section 13.38.

I 13.4-2 Update: Changes Operations Quality Assurance Supervisor to Manager, Operations QA.

14.2-5 Update: Shows Start-up personnel as a member of the Joint Test Group.

Update: Changes " Manager, CPSES Start-up" to " Manager, Start-up".

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q Attachment to TXX-6119 l N;vember 25, 1986 Page 15 of 18 FSAR Page (as amended) Descriotion 14.2-8 Update: Removes reference to " Manager, Nuclear Operations" and reolaces with "Vice President, Nuclear Operations" to reflect present organization. Also, removes Vice President, Nuclear Operations from Joint Test Group (JTG).

Update: Shows Manager, Plant Operations to be JTG Chairman. Removes responsibility regarding review of preoperational test procedures which is reassigned to the Engineering Superintendent as noted below.

14.2-9 Update: Shows Engineering Superintendent to be the Vice Chairman of the JTG and coordinator for the review of all preoperational test procedures.

Editorial: Removes "TUGC0" from title (was TUGC0 Engineering and Construction).

14.2-11 Clarification: Westinghouse, as a vendor, supplies technical support versus direction to TUGCO.

Update: Deletes reference to " Manager, Nuclear Operations" and replaces with "Vice President, Nuclear Operations".

14.2-12 Update: Changes to JTG membership reflect present organization:

1) " Manager, Nuclear Operations" to " Manager, Plant Operations".

2) " Manager, CPSES Start-up" to " Manager, Start-up".

3) " Manager, Plant Operations" to " Engineering Superintendent".

4) " Assistant Manager, Nuclear Engineering" to " Director of Engineering".

14.2-24 Update: De Mtes " Manager, Nuclear Operations" and replaces with 'Vice President, Nuclear Operations".

F14.2-1 Update: Shows new start-up organization.

F14.2-2 Update: Reflects changes made to Section 14.2.2.5 regarding JTG Membership.

Sec. 17.1 Summary The following changes reflect the reorganization of responsibilities within TUGCO, a clarification of assigned responsibilities by referencing specific departments or positions rather than "TUGC0 Management" and text i

revisions to more clearly define the extension of TUGC0 QA Program requirements to our contractors, and/or vendors.

These changes have been reviewed by Dallas QA and have been determined not to constitute a reduction in commitments made in the QA Program previously accepted by

, the NRC.

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Attachment to TXX-6119 Nsvemb:gr 25, 1986 Page~ 16 of 18

.FSAR Page

--(as amended) Descriotion

-17.1-1 Clarification: Provides changes which do not alter the intent of the previous wording. In some cases, additional explanatory narrative has been provided.

17.1-2 Update: Provides changes or deletions due to.

classifying Architect Engineering firms under the general category of. an engineering services contractor...

vice prime contractor and due to TUGCO. assuming-lead

-responsibility for certain tasks. This philosophy does not alter the intent of the previous wording since the same 10CFR50 Appendix B requirements apply regardless of whether the contractor / vendor or TUGC0 has lead responsibility. See also 17.1-1.

17.1-3 and See 17.1-1.

17.1-4 17.1-5 and See 17.1-1 and 17.1-2.

17.1-6 17.1-7 and See 17.1-1.

17.1-8 17.1-9 See 17.1-1 and 17.1-2.

17.1-10 Clarification: Deletes narrative describing the TUGC0 Corporate QA Program procedures for procurement, audits, design verification and file control. These narratives are redundant to other sections of Chapter 17.1. See also 17.1-1.

17.1-11 Clarification: Designates the Director, QA as responsible for construction site QA/QC programs versus the TUGC0 organization. This change is a designation of responsibility specific to a position versus an organization. See also 17.1-1, 17.1-2, and 17.1-10.

17.1-12 and See 17.1-1 and 17.1-2.

17.1-15 17.1-16 and See 17.1-1.

17.1-17 17.1-19 Clarification: Changes the text to specify that the TUGC0 Corporate QA Program requires the establishment of hold points related to purchasing documents versus the Purchasing Department. This change is basically a reference clarification. See also 17.1-1.

17.1-20 See 17.1-1.

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• . Attachment to TXX-6119 N:;vember 25, 1986 Page 17 of 18 FSAR Page (as amended) Description 17.1-22 Correction: Deletes coatings from the list of materials, parts and components which need to be controlled under the TUGC0 Corporate QA Program. This change is consistent with TUGC0's commitment to Reg. Guide 1.54 as previously accepted by the NRC. See also 17.1-1 and 17.1-2.

17.1-23 thru See 17.1-1 and 17.1-2.

17.1-26 17.1-27 See 17.1-2.

17.1-28 and See 17.1-1 and 17.1-2.

17.1-29 17.1-30 See 17.1-1.

17.1-31 Update: Changes the text to specify that construction versus prime contractors are responsible for reporting NCR's to TUGC0 Engineering versus TUGC0 management. This change designates specific groups within certain organizations as being responsible for certain activities.

See also 17.1-1 and 17.1-2, 17.1-33~ Clarification: Changes the text to specify that QC is responsible for reviewing NCR's and trends versus the QA organization. This change designates the specific QA organization responsible for the activity. See also 17.1-1.

17.1-34 See 17.1-1 and 17.1-2.

17.1-35 thru See 17.1-1.

17.1-38 T17.1-2 Update: Changes "1.1 Quality Assurance Division" to "1.1 Quality Assurance Department".

F17.1-2 Update: The noted figure is deleted and incorporated into Figure 17.1-6. Figure 17.1-6 is also being updated.

F17.1-3 See 17.1-2.

F17.1-5 Update: Changes the figure to reflect the new Nuclear Engineering and Operations (NEO) Group. See also Figure 13.1-2.

F17.1-6 See Figure 17.1-2 L.

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Attachment to TXX-6119 November 25, 1986 Page 18 of 18 FSAR Page (as amended) Descriotion Table 17A-1 Correction: Adds note 13d to safety class 3 piping and Sheet 10 valves for item 10 " Component Cooling Water System" as valves FV-4650A and FV-4650B are now environmentally qualified and were seismically qualified by testing and analysis.

Table 17A-1 Correction: Revises the table to clarify the material Sheet 22 to be ASTM. The Control Room Air-Conditioning System refrigerant piping and tubes (ASTM 888) are produced to national standards in an industry in which quality is assured by the pressures of competition.

II.K-17 thru Update: RevisesSection II.K.3.31 response to include II.K-19 reference to WOG analyses which generically demonstrates that WFLASH LOCA code is conservative compared to the NOTRUMP code.

210-1 through Update: Incorporates responses to Questions 210.1 210-14 through 210.1 previously submitted to the NRC concerning Arbitrary Intermediate Break elimination.

212-111 Editorial: Provides the correct FSAR reference for the alternative test description. Section 14.2.7 does not contain the referenced information.

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