ML20246H141

Forwards Advance Submittal of FSAR Changes Re Tech Specs to Be Included in Future FSAR Amend

ML20246H141
Person / Time
Site:	Comanche Peak
Issue date:	08/23/1989
From:	William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TXX-89612, NUDOCS 8909010126
Download: ML20246H141 (25)

Text

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EE Log # TXX-69612 L

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File # 10010' i

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916-Ref. # 10CFR50.34(b)'

99gLgg7gjg n

l' William J. Cahill, Jr.

Extative We President U. S. Nuclear Regulatory Commission Attn: Document Control Desk L

Washington, D. C.

20555 1

SUBJECT:

COMANCHE PEAK STEAD ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 ADVANCE FSAR SUBMITTAL

. TECHNICAL SPECIFICATIONS i

Gentlemen:

The enclosure to this letter provides an advance submittal of FSAR changes related to Technical Specifications. These changes w'ill be included in a-l future FSAR amendment.

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In order to facilitate NRC staff review of these changes, information related

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to the FSAR change is. organized as follows:

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1.

Draf t revised FSAR pages, with changed portions iredicated by a bar in the margin, as they are to anpear in a future amendment (additional pages % mediately preceding and/or following the revised

.pages are provided if needed to understand the change).

2.

Line-by-line description / justification of each item revised.

3 A copy of related SER/SSE't sections.

1 4.

An index page containing the title of " bullets" which consolidate I

and categorize similar individual changes by subject and related SER l-section.

1 5.

A discussion of each " bullet" which includes:

The line-by-line description / justification for each item related to the " bullet" which has been screened as a group 1 or 2 item or a group 3 or 4 item which impacts the existing SER/SSER's.

(Although the changes included in this advance submittal do nnt meet the criteria discussed in TU Electric letter TXX-88467 dated June 1, 1988, the " bullet" is included I

to be consistent in format with other advance submittals.)

l 8909010126 890023 i

PDR ADOCK 05000445

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I 400 Mrth Olive Street LB 81 Dallas, Texas 7520!

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. TXX-89612.

August 23, 1989

- Page 2'of-2 l

The bold / overstrike version of the revised FSAR.pages '

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referenced _by the' description / justification for each item identified.above. The bold / overstrike version facilitt.tet review offthe revision by highlighting each addition of new n

. text.in bolditype font and overstriking with a slash.(/) the portion of the text that is deleted.

In some cases, where.

H the bold / overstrike version is unavailable, a hand rerkee:-up.

E versiorfwill be provided.

If you have any questions regarding this submittal please contbet Jimmy Seawright at'(214) 812-4375.

Sincerely, William J. Cahill, Jr.

By:

D. R. Woodlan l-Docket Licensing Manager 1:

JDS/vid Enclosure-c - Mr. R. D. Martin, Region IV Resident Inspectors CPSES (3) l-l-

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Enclosure to TXX-89612 August 23, 1989 Advance FSAR Change Related to Technical Specification Certification Process Part 1 Draft FSAR pages pg. 2 thru 6 Part 2 Description / Justification pg. 7 Part 3 Related SER/SSER pages pg. 8 thru 16 Part 4 Index P6ge Containing the Title pg. 17 of " Bullets" Part 5 Discussion of " Bullets" pg. 18 thru 23 i

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Enclosure. to :TXk-89612-CPSES/FSAR-i

.Page'2 of 23:

TABLE 1.6-1

.(Sheet 18)

O_-

TOPICAL REPORTS INCORPORATED BY QLFERENCE Reference' Review Report ~

Section(s)- Status

" Evaluation Of Surveillance Frequencies 16.2 A

69

~And Out Of Service Times.For The Reactor 69 Protection Instrumentation System" 69-qj,

'WCAP-10271-P-A, May 1986 69

" Evaluation Of Surveillance Frequencies 16.2 A

69 And Out Of Service Times For The Reactor 69 Protection Instrumentation System" 69 l

Supplement 1 69 WCAD-10271, Supplement 1-P-A, May 1986 69

" Evaluation Of Surveillance Frequencies 16.2 A

DRAFT l

And Out Of Service Times For The 69 Engineered Safety Feat.:ures Actuati?n 69 System" 69 WCAP-10271, Supp1tment 2, Revision 1, 69 harch 1987 69

" Reactor Trip Breaker Maintenance /

16.2 U

69 Surveillance Optimization Program" 69 WCAP-11312, April 1987 69 i

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i Draft Version 4

CPSES/FSAR Enclosure to'TXX-B9612 Ea913 cyg,}

PROPOSED FINAL TECHNICAL SPECIFICATIONS g

16.2.1 DISCUSSION

'The pr2vious information included in this Section was removed to DRAFT facilitate compliance with the Standard Technical Specifications for Westinghouse Pressurized Water Reactors provided to TU Electric by the NRC. Section 16.2.2 briefly describes the applicability.. format, and j

implementation of the Westinghouse Standard Technicel Specifications.

l 16.2.2 TECHNICAL SPECIFICATION DEVELOPMENT DRAFT l

DRAFT APPLICABILITY This Standard Technical Specification (STS) has been structured for the broadest possible use on Westinghouse plants currently being reviewed for an Operating License. Accordingly, the document contains DRAFT specifications which may not be applicable to all plants. Optional specifications are provided for those features and systems which may br. included in individual plant designs but.are not generic in their scope of application. Alternate specifications are provided in a DRAFT limited number of cases to cover situations where alternate specification requirements are necessary on a generic basis because of der.ign differences.

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16.2-1 Draft Version

! Enc 1csure to.TXX-89612-c

.Paga 4 of 23 CPSES/FSAR FORMAT The format of-the STS addresses the categories required by 10 CFR and Eensists of six sections covering the areas of: Definitions, Safety-Limits. and Limiting Safety System Settings, Limiting Conditions for.

Operation, Surveillance Requirements, Design Features, and Administrative Controls. The Limiting Conditions for Operation.and Surveillance Requirements (Sections 3 & 4) are presented in a combined format with each LCO appearing at the top of the page followed DRAFT immediately by.the applicable Surveillance Requirements. The combined Section 3/4 is further subdivided into subsections covering the areas of:

Applicability,

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DRAFT DRAFT Reactivity Contro1' Systems,

. DRAFT Power Distribution Limits, DRAFT Instrumentation.

DRAFT Reactor Coolant System.

DRAFT Emergency Core Cooling Systems, DRAFT Containment Systems, DRAFT Plant Systems.

Electrical Power Systems, DRAFT ORAFT Refueling Operations, DRAFT Special Test Exceptions, and Radioactive Effluents.

DRAFT The values of those parameters and variables which may vary because of plant design appear as either blanks or parenthesize numbers throughout the STS. The actual value for each parameter will be provided by individual applicants as appropriate for their plants.

The values in parentheses are for illustration only.

Draft Version 16.2-2 L

Enc 1csura to'TXX-89612 CPSES/FSAR Paga 5 of~23 Certain information from the Techndcal Specifications has been DRAFT reiocated to a separate document titled the CPSES Technical Requirements Manual (TRM). The Technical Requirements Manual is

,d1vided into subsections covering the following areas:

Administrative Controls DRAFT Instrumentation DRAFT i

Containment DRAFT Plant Systems DRAFT Electrical DRAFT Changes to the CPSES TRM are subject to safety evaluations completed DRAFT in accordance with the provisions of 10CFR50.59.

IMPLEMENTATION The implementation of the STS on an individual license application will proceed in three phases. The major steps within each phase are indicated below.

Phase I The applicant should:

1.

Obtain copies of the STS from the NRC.

2.

Select the appropriate containment specification section and set aside the non-applicable containment sections and related bases.

3.

Identify and mark those specifications not required because of plant design or other factors.

Specifications within this category should be retained ire position within the document package for later review and discussion.

4.

Identify those areas where specifications are required but are not provided in the STS.

l 16.2-3 Draft version i

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Enc 1csure to TXX-89612

,Page 6 of 23 CPSES/FSAR 5.

Provide the applicable values of the parameters and variables identified by blanks or parentheses in the STS. This information j

must be consistent with the SAR and other supporting documents.

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6.

Provide the figures, graphs and other information required to complete the STS document package.

Phase LL 1.

The Commission staff will review the information provided in the marked up STS document package resulting from the Phase I preparation.

2.

Applicant / staff meetings will be held to resolve noted differences of position and other. elated comments from the applicant, vendor and A.E.

Phase III 1.

The Commission will provide a Proof and Review edition of the technical specification for final review by all parties based upon the resolution of comments and positions in Phaso II.

2.

Final comments and corrections will be incorporated into the document as received.

3.

The Technical Specifications will be issued by the Commission as Appendix "A" of the Operating License.

Draft Version 16.2-4

CPSES FSAR AMENDMENT Enclosura to.TXX-89612 DETA! LED DESCRIPTION.

Page 1

,Page 7 cf 23;

FSAR Page (as amended)

Group Description Table 1.6-1.,

4 See. Sheet No(s):18 Show WCAP 10271 Supplement 2. Revision 1. March 1987 as approved by the NRC.

Update:

NRC provided the Safety Evaluation accepting the use

' of WCAP 10271. Supplement 2, Revision I in letter dated:

February 22, 1989, from C.E. Rossi of the NRC to R,/, Newton of Westinghouse.

FSAR updated to reflect the'spproved status of the document.

FSAR Change Request Number: 89-555 SER/SSER Impact: No 16.2-1, 2 4

Provide updated description of the Technical Specification development and approval process.

Revision:

The Technical Specification Description is update 6 in the FSAR to reflect the process, agreed upon by TU tiectric and the NRC which was used to develop and approve the CPSES Unit 1 Technical Specifications.

FSAR Change Request Number: 89-555 SER/SSER Impact: No 16.2-3, 4 3

Add description of Technicci Requirements Manual (TRM)

Revision:

Certain information from the Technical Specifications.

was relocated to a separate document titled the CPSES' Technical Requirements Manual. The FSAR is updated to reflect the acceptance of the TRM by the NRC as a licensing document.

FSAR Change Request Number: 89-555 SER/SSER Impact: No I

Enclosure to TXX-89612 l

,Page 8 of 23-I:

16 TECHNICAL SPECIFICATION 5 l

The Technical Specifications in a license define certain features, character-n istics, and conditions governing operation of a facility that cannot be changed without prior approval of the NRC.

The finally aporoved Technical Specifica-tions will be made a part of the Operating License.

Included will be sections covering definitions, safety limits, limiting safety system settings, limiting conditions for operation, surveillance requirements, design features, and administrative controls.

The Technical Specifications for this facility will be based on " Standard Technical Specifications for Westinghouse Pressurized Water Reactors" (NUREG-0452, Revision 2).

This document has been updated from earlier revisions as a result of continued discussion with Westinghouse and other licensees with Westinghouse pressurized water reactors.

The staff is working with the applicant to prepare a draft of the Technical l

Specifications for the Comanche Peak Steam Electric Station. On the basis of its review to date, the staff concludes that normal plant operation within the i

limits of the Technical Specifications will not result in offsite exposures in i

excess of the 10 CFR Part 20 limits.

Furthermore, the limiting conditions for l

operation and surveillance requirements will ensure tnat necessary engineered g

safety features will be available in the event of malfunctions within the facility.

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Enclosuro to TXX-89612 Page 9 of 23 16.. TECHNICAL SPECIFICATIONS In the SER, the staff identified certain conditions which must be included in the Comanche Peak Technical Specifications in addition to Standard Technical' Specifications.

In this supplement,.the staff has identified the need for additfor.a1 plant-specific Technical Specifications. The complete list of plant-specific Technical Specifications is given below; they are discussed further in sections of the SER or this supplement as indicated.

Technical Specifications' Identified in the SER (1) Control of mineral exploration within the exclusion area (Section 2.1.2).

(2) The constant axial offset control band will be limited to +5% AI for the

' first 3000 MWD /MTU burnup, and to +3 to -12% AI thereafter (Section 4.3.2.1).

(3) DNBR penalty for rod bow (Section 4.4.1).

(4) Surveillance for detection of crud buildup (Section 4.4.1).

(5) Prohibit operation in the N-1 mode (Section 4.4.4).

(6) Pressure-temperature limits for the reactor vessel (Section 5.3.3).

(7) Inspection of steam generator tubes (Section 5.4.2.2).

(8) Restrictions on isolation valves in the containment purge system and containment pressure relief system (Section 6.2.3 and Section 22. II.E.4.2).

e (9) Containment leak testing requirements (Section 6.2.5).

(10) Testing of safety system response times (Section 7.2.4).

(11) Testing of auxiliary feedwater pumps (Section 7.3.1.6).

(12) Methodology for establishing safety system set points (Section 7.3.2.6)

(13) Trip setpoints for offsite power undervoltage protection (Section 8.2.4)

(14) List valves that require power lockout (Section 8.4.3).

(15) Sampling and analysis of demineralized resins from condensate cleanup system (Section 11.2.1.2).

(16) Process control program for solid waste syster; (Section 11.2.3).

(17) Restrictions on boron dilution rates (Section 15.2.3.1).

(18) limitations and surveillance of auxiliary feedwater system (Section 22, II.E.1.1, Recommendations GS-1 and GS-2).

i Comanche Peak SSER #1 16-1

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~ Enclosure to TXX-89612-u,

-page'10 of 23 1

Additional Technical Specifications Identified in this Supplement (1) Mor,itoring of-safe shutdown impoundment dam for erosion and weathering

..(Section 2.4.3.1).

(2) Monitoring for sediment buildup in the service water intake. channel +

(Section 2.4.8).

(3) Leak testing of pressure isolation valves for reactor coolant pressure boundary (Section 3.9.6)

.(4) Inservice inspection of reactor coolant pump flywheel (Section 5.4.1).

-(5). Adherence.to ~ accepted secondary water chemistry monitoring and control:

program (Section 5.4.2.3).

(E)--Fire protection program (Section 9.5.1.6).

Comanche Peak SSER #1 16-2

Enclosure to TXX-89612

,Page 11 of 23 16 TECHNICAL SPECIFICATIONS In this supplement, the staff has idantified the need for additional plant-specific Technical Specifications as listed belcw, They are discutsed further in sections of this supplement as indicated.

1.

Maintenance restrictions on condenser circulating water system during high water levels on Squaw Creek Reservoir (Sectin 3.4.1).

2.

Controls for feedwater line isolation actuation (Section 7.3.1.5).

Comanche Peak SSER 3 16-1

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. Enclosure to TXX 89612

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.16 TECHNICAL SPECIFICATIONS

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In thisIsupplement, the staff has. identified the.need for an additional plant-l specific Technical Specification as' listed below.

This item i: discussed. fur-j ther in this supplement as indicated.

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. Eddy current testing of steam generator tubes.(Appendix H, paragraph 3.6).

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Comanche Peak SSER 4 16-1

!EnclosuretoTXX-89612l T

'Paga 13 of 23 f.

16 TECHNICAL SPECIFICATIONS A composite list lof the items for which a Technical Specification will be required for Comanche Peak, in addition to the Standard Westinghouse PWR -

Technical Specification, follows (the SER/SSER section in'which each. item is discussed is indicated,in parentheses):

(1) Control of. mineral exploration within exclusion area (2.1.2)

(2) The. constant axial offset control band will be limited to 15% AI for the first 3000 MWD /MTU burnup, and to 3 to -12% al thereafter (4.3.2.1)

L (3) Departure from nucleate boiling ratio (DNBR) penalty for rod bow (4.4.1)

(4) Surveillance for detection of crud buildup (4.4.1)

'(5) Prohibit operation in 'he N-1 mode (4.4.4)

(6) Pressure-temperature limits for the RV (5.3.3)

(7) Inspection of steam generator tubes (5.4.2.2.)

(8) Restriction on isolation valves in the containment purge system and containment pressure relief system (6.2.3, 22 (II.E.4.2))

(9) Containment leak testing requirements (SER Section 6.2.5, SSER 6, Section 6.25)

(10) Testing of safety system response times (7.2.4)

(11) Testing of auxiliary feedwater pumps (7.3.1.6)

(12) Methodology for establishing safety system setpoints (7.3.2.6)

(13) Trip setpoints for offsite power undervoltage protection (8.2.4)

(14) List valves that require power lockout (8.4.3)

(15) Sampling and analysis of demineralized resins from condensate pump system (11.2.1.2)

(16) Process control program for solid waste system (11.2.3)

(17) Restrictions on boron dilution rates (15.2.3.1)

(18) Limitation and surveillance of auxiliary feedwater system (22 (II.E.1.1 Recommendations GS-1 and GS-2))

Comanche Peak SSER 6 16-1

Enclosure to TXX-89612 Pags 14 of 23 (19) Monitoring of safe shutdown impoundment dam for erosion and weathering (SSER 1, Section 2.4.3.1)

(20) Mp.nitoring for sediment buildup in the service water intake channel (SSER 1, Section 2.4.E)

(21) Leak testing of pressure isolation valves for reactor coolant pressure boundary (SSER 1, Secticn 3.9,6)

(22) Inservice inspectio'i of reactor coolant pump flywheel (SSER 1, Section 5.4.1)

(23) Adherance to accepted secondary water chemistry monitoring and control program (SSER 1, Section 5.4.2.3)

(24) Fire protection program (SSER 1, Section 9.5.1.6)

(25) Maintenance restrictions on condenser circulating water system during high weter levels on Squaw Creek Reservoir (SSER 3, Section 3.4.1)

(26) Controls for feedweter line isolation activities (SSER 3, Section 7.3.1.5)

(27) Eddy current testing of steam generator tubes (SSER 4, App. H, para. 3.0)

(28) Heatup and cooldown curves (29) Turbine valves testing /overspeed pr;tection system (20) Flow uncertainty factors using N-16 flow calculations (31) Environmental protection plan (32) Type C leak test program for isolation valves (SSER 6, Section 6.2,3.2) i Comanche Peak SSER 6 16-2

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Enclosure to TXX-89d12 l

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,Page 15 of 23 a

16 TECHNICAL 30ECIFICATIONS A' composite list of the items for which a Technical Specification will be required for Comanche Peak, in addition to the Standard Westinghouse PWR Technical Specification, follows (the SER/SSER section in which eacn itera 1

is discusseo is indicated in parentheses):

(1) Control of minera) exploration within exclusion area (SER Section 2.1.2)

(2) The constant axial offset control band limited to 5% AI for the first l

3,000 MdD/MTU burnup, and to 3 to -12% AI thereafter (SER Section 4.3.2.1)

(3) Departure from nucleate boiling ratio (DNBR) penalty for rod bow (SER Section 4.4.1)

(4) Surveillance for detection of crud buildup (SER Section 4.4.1)

(5) Prohibit operation in the N-1 mode (SER Section 4.4.4)

(6) Pressure-temperature limits for the reactor vessel (SER Section 5.3.3)

(7) Inspection of steam generator tubes (SER Section 5.4.2.2)

(8) Restrict ion on isolation valves in the containment purge system and containment pressure relief system (SER Sections 6.2.3, 22 (II.E 4.2))

(9) Containment leak testing requirements (SER Section 6.2.5)

(10) Testing of safety system response times (SER Section 7.2.4)

(11) Testing of auxiliary feedwater pumps (SER Section 7.3.1.6)

(12) Methodology for establishing safety system setpoints (SER Section 7.3.2.6)

(13) Trip setpoints for offsite power undervoltacje protection (SER Section 8.2.4)

(14) List valves that require power lockort (SER Section 8.4.3)

(15) Sampling and analysis of deniineralizer resins from condensate pump system (SER Secti6n 11.2.1.2)

(16) Process control program for solid waste system (SER Section 11.2.3)

(17) Restrictions on boron dilution rates (SER Section 15.2.3.1)

(18) Limitation and surveillance of auxiliary feedwater system (SER Section 22 (II.E.1.1 - Recommendations GS-1 and GS-2))

(19) Monitoring of safe shutdown impoundment dam for erosion and weathering (SSER 1, Section 2.4.3.1)

Comanche Peak SSER 12 16-1 AW

Y EnclosurG to TXX-89612 l_

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.Page 16 of 23 (20) Monitoring for sediment buildup in the service water intake channel (SSER 1, Section 2.4.8)

(21) Leak testing of pressure isolation valvet for reactor coolant pressure boundary (SSER 1, Section 3.9.6)

(22) Inservice inspection of reactor coolant pump flywheel (SSER 1, Section 5.4.1)

(23) Adherance to accepted secondary water chemistry monitoring and control program (SSER 1, Section 5.4.2.3; SSER 12, Section 5.4.2.3)

(24) Fire protection program (SSER 1, Section 9.5.1.6; SSER 12, Section 9.5.1)

(25) Maintenance restrictions on condenser circulating water system during high water levels on Squaw Creek Reservoir (SSER 3, Section 3.4.1)

(26) Controls for feedwater line isolation activities (SSER 3, Section 7.3.1.5)

(27) Eddy current testing of steam generator tubes (SSER 4, App. H, para. 3.6) a s

f (28) Type C ?.eak test program for isolation valves (SSER 6, Section 6.2.3.2) 1 (29) Flow uncertainty factor using N-16 transient time flow meter for flow meter calibration (SSER 12, Section 4.4) l' E

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Comanche Peak SSER 12 16-2

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T; Enclosure to.TXX-89612 Paga 17.of 23

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SECT!0!i 16 - TECHillCAL SPECIFICATI0!JS 1

OTSB 8.

The FSAR has revised the description of the T/S development and certification process (77; l

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-CPSES FSAR'AMENDMENV-

'.. Enclosura to TXX-89612 DETt.ILED DESCRIPTION Page l'

"'} Page' 18 of 23 g

IFSAR Page

f as amen._dgjF Group. DescriDtiO_q iTable 1.6-1..

-4 See Sheet Wo(s):18

.Show WCAP 10271 Supplement 2. Revision l,, March 1987 as approved by the NRC.

' Update:

NRC provided the Safety Eva;uation accepting the use of WCAP,10271. Supplement 2. Revision 1 in letter dated o

Februa:y 22, 1989, from.C.E. Rossi of the NRC to R.A. Newton of Westinghouse.: FSt.R-updated'te reflect the approved status of the document, FSAR Change Request Number:.89-555 SER/SSER Impact: No 16.2-1, 2 4

Provide updated description of the Technical Specification development and approval process.

Revision:-

The Technical Specification Des;;ription is updated in the FSAR to reflect the process, agreed upon by-TU Elactric and the-NRC, which was used to develop and approve the CPSES Unit 1 Technical Specifications.

FSAR Change Request Number: 89-555 SER/SSER Impact: No 16.2-3, 4 3

Add description of Technical Requireinents Manual (TRM)

Revision:

Certain information from the Technical Specifications was relochted to a separate document titled the CPSES Technical Requirements Manual. The FSAR is updated to reflect the acceptance of.the TRM by the NRC as a licensing document.

FSAR Change Request Number: 89-555 SER/SSER Inspect: No m

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Enclosure to TXX-89612 -

CPSES/FSAR Pagg 19 of 23 TABLE 1.6-1 (Sheet 18)

TOPICAL REPORTS INCORPORATED BY REEERENCE w

Refercnce Review Report Section(s) Status

" Evaluation Of Surveillance Frequencies 16.2 A

69 And Out Of Service Times For The Reactor 69 Protection Instrumentation System" 69 WCAP-10271-P-A, May 1986 69

" Evaluation Of Surveillance Frequencies 16.2 A

69 And Out Of Service Times For The Recctor 69 Protection Instrumentation System" 69 Supplement 1 69 WCAP-107.71, Supplement 1-P-A, May 1986 69

" Evaluation Of Surveillance Frequencies 16.2 A

69 And Out Of Service Times For The 69 Engineered Safety Features Actuation 69 System" 69 WCAP-10271, Supplement 2 Revision 1, 69 March 1987 69

" Reactor Trip Breaker Haintenanee/

16.?.

U 69 Surveillance Optimization Program" 69 WCAP-11312, April 1987 69 i

l-Bold /0verstrike Version

' Enclosure to TXX-89612 CPSES/FSAh l'

'Pt.ga 2.0 of 23 16.2 EROPOSED FINAL TECHNICAL SPECIFICATIONS 4

1 16.2.1 DISCUSSION l'

l l

The previous information included in this Section was removed to facilitate complience with the Standard Technicol Specifications for Westinghouse Pressurized Water Reactors provided to TU Electric by the NRC. Section 16.?. 2 briefly describes the applicability, format, and implementa?. ion of the Westinghouse Standard Technical Specifications NWRE6/0452/ Rd/fifdd Zl Jd7f 1979. THd /d4di/ddddts f6t EP5EE tdtHditd7 ipelffitdtf6dt df77 Ed idpiddddtdd fd dtt6fdddtd With NURE6/

0452/ 7Hd fdtid/d 16 NORE6/0dBZ ft /dpffdtdd Mdtd fdf inforddtiddl I

16.2.2 TECHNICAL SPECIFICATION DEVELOPMENT FOREWARO 70 NORES/0452 THd f6II6didd pdfddtd, phi B/fdfff ddittfBd tHd dppfftdBfIfffl f6/ddt 4

l ddd idpIddddtdtidd 6f tHd WditiddH6did 5tdddd/d IntHdiddl Epdtifftstidd pdtKdddl 1

i APPLICABILITY This Standard Technical Specification (STS) h6s been structured for the broadest possible use on Westinghouse pisnts currently being reviewed for an Operating License.

Accordingly, the document contains l

specifications which may not be applicable to all plants ditH 11 ditMit 3 6t 4 166pf ddd 21 AftM ddd AftH66t 166p ittp idlidt didiffid.

In dddiff6dl f6dt idpdfdtd ddd ditttstd tidtdididnt ipitiffidtl6d idttf6di did pf6diddd 16f dith 61 tHd 16116didd (6dididdddt ifpdit Atd6tpHdtitt Idd Edddddifft EdB/AtidspHd/ftl ddd Oddll Optional specifications are provided for those features and systems which may 1

be included in individual plant designs but are not generic in their scope of application. Alternate specifications are provided in a limited number of cases to cover situations where alternate specification requirements are necessary on a generic basis because of design differences.

THit (difff6d 6f tHd 575 d6dt d6t ifpitd77f intiddd (44difidtsti dHith dif Vd ddddd 6t fdifidd di d flidit 61 tdd NRE tidffli fdttHMt (dtidd 6f tHd TH/dd Mild Isiddd istidddtl 16.2-1 Bold /0verstrike I

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,,Page 21 of 23:

.CPSES/FSAR-FORMAT 1

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'The format. of the STS addresses the categories required by 10 CFR and l

' consists of six sections coveririg the arees of: Definitions, Safety i

Limits and Limiting Safety System Settiligs, Limiting Conditions for Operation, Surveillance Requirements, Design features a >.d e

Administrative Controls. The Limiting Cond!tions for Operation and Surveillance Requirements (Sections 3 & 4) are presented in a coubined format with each LCO appearing at the top of the page followed l

.immediately by the applicable Surveillance Requirements. The' combined i

Section 3/4 is further subdivitied into fdd subsections covering the areas of:

Applicability,

-Il Reactivity' Control Systems,

-2/ Power Distribution Limits.

-31 Instrumentation, i

-4/ Reactor Coolant System, j

-El Emergency Core Cocling Systems.

61 Containment Systems.

-71 Plant Systems, l

-81 Electrical Power Systems, l

-9l Refueling Opert.tions, ddd j

-20t Specia Test Exceptions, and l

Radioactive Effluents.

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The values of those parameters and variables which may vary because of l

plant design appear as either blanks or parenthesize numbers throughout the STS. The actual value for each parameter will be provided by individual applicants as appropriate for their plants.

The values in parentheses are for illustration only.

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• EnclusurG to TXX-89612' CPSES/FSAR~

aPage 22 of 23 Certain. informat' ion front-the Technic &l Specifications has been relocated to a separcte document titled the CPSES Technical' Requirements t[anual (TRM). The Technical Require 2snts Manual is

, divided into subsections covering the follotting areas:

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' Admir:Istrative Controls.

Instrumentation Containment Plcnt Systems Electrical' Changes to the CPSES TRM are subject to safety evaluations completed in accordance with the pi'ovisions of 10CFR50.59.

IMPLEMENTATION The implementation of the-STS on an individual-license applicatica will proceed in three phases. The major steps within each phese are indicated belcw.

l Phase I_

The applicant should:

1 1.

Obtain copies of the STS from the NRC.

2.

Select the appropriate c.ontainment specification section And set aside the re-spplicable containment sec'.4ons and celated beces.

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'3.

Identify and mark those specifications not required because of plant design or other factors.

Specifications within this category should oe retained ir position within the doctoent package for later review end discussipa.

j 4.

Identify those area.t where specifications are rrquired bet are not provided in the STS.

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I en Enclosure to-TXX-89612;

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5.

Provide the applicab}e values'of the parameters:end variables identified by blanks or. parer. theses in the STS. This itiformation -

must b? consistent with the SAR and other supporting documerits.

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6.

Provide'the figures, graphs and other information required to.

-complete the STE document package?

f Phase II-l I.

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The Commission staff'will review the information provided in the marked 1up.STS document psckage' resulting fr-om the Phase I preparation.

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'2.

Applicant / staff meetings will be held to resolve noted'

. differences.of' position 6td other related comments from the app'ticant, vendor and A.E.

Eh4se II'(

1.

The Commission will provide a Proof and Review edition of the technical specification for final review by all parties based upon the resolution of coi..ments and positions in Phase II.

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2.

Final comments and corrections will be incorporated into the document as received.

3.

The Technical Specifications will be issued by the Commission as Appendix "A" of the Operating License, l

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