ML20087J792

LAR 95-04 to Licenses NPF-87 & NPF-89,moving Overtemp N-16 Limits from TS to Colr,Per GL 88-16.Changes in LAR 95-04 Originally Submitted in LAR 95-03 on 950512.LAR 95-03 Being Divided Into Four Separate LARs for Ease in Processing

ML20087J792
Person / Time
Site:	Comanche Peak
Issue date:	08/15/1995
From:	Kelley J, Terry C TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20087J795	List: ML20087J792 ML20087J807
References
GL-88-16, TXX-95214, NUDOCS 9508220172
Download: ML20087J792 (9)

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9 Log # TXX-95214 File # 916 (2.2) l

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Ref. # 10CFR50.90 RIELECTRIC 10CFR50.36 l

August 15, 1995 t

. C. lance Terry  !

Groep Vke Frenarnt.Narienr U. S. Nuclear Regulatory Commission  !

Attn: Document Control-Desk i Washington, DC 20555  :

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SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50 445 AND 50-446  ;

SUBMITTAL OF LICENSE AMENDMENT REQUEST 95 04 CYCLE-SPECIFIC PARAMETER LIMITS - OVERTEMPERATURE N 16 .;

REF: 1) TU Electric letter logged, TXX-95076 from C. L. Terry to the NRC dated May 12, 1995 l i;

Gentlemen:

Pursusnt to 10CFR50.90, TV Electric hereby requests an amendment to the  :

CPSES Unit 1 Operating License (NPF-87) and CPSES Unit 2 Operating License  ;

(NPF 89) by incorporating the attached changes into the CPSES Units 1 and l 2 Technical Specifications. These changes apply equally to CPSES Units 1 and 2. 1 The proposed changes in this license amendment request (LAR) were j originally submitted in LAR 95 03 on May 12, 1995 (reference 1). Based on  !

subsequent discussions with the NRC, LAR 95 03 is being divided into four l separate LARs for ease in processing by the NRC and to allow review of the i four basic changes separately. The changes which move the Overtemperature -!

N 16 limits from the Technicel Specifications to the Core Operating Limits. j Report are resubmitted herein. The proposed changes will result in  :

resource savings for TU Electric and the NRC by eliminating license amendment requests now required to change the values of these parameters.  ;

The proposed changes are consistent with the intent of Generic Letter (GL)  !

8816 which provides guidelines for the removal of cycle specific j parameter limits from the Technical Specifications.  !

Attachment 2 provides a detailed description of the proposed changes, a j safety analysis of the changes, and TU Electric's determination that the i proposed changes do not involve a significant hazard consideration. ,

Attachment 3 provides the affected Technical Specification pages (NUREG- l 1468), marked up to reflect the proposed changes.  ;

TU Electric requests approval of this proposed license amendment by }

February 29, 1996 with implementation of the technical specification i I

changes to occur within 30 days of approval.

l Q 0,^ f4 0 m , k 9508220172 950815 L PDR- ADOCK 05000445 PDR p 1{. '

j Energy Plass 1601 Bryan Suset Dallas.Tenee 75201 3. 'i i

TXX 95214  ;

Page_2 of 2

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In accordance with 10CFR50.91(b). TU Electric is providing the State of Texas with a copy of this proposed amendment.  ;

Should you have any questions, please contact Mr. Bob Dacko at (214) 812 8228. -

Sincerely, C. L. Terry  ;

i By:

.K J. Kelley, Jr.

Vice President of Nuclear -

Engineering and Support i

BSD/bd j Attachments: '

1. Affidavit

2. Description and Assessment .

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3. Affected Technical Specification page (NUREG-1468) as revised by all approved license amendments

Enclosure:

1. Generic Letter 8816 [

c. Mr. L. J. Callan, Region IV  !

Mr. T. J. Polich NRR l Mr. D. F. Kirsch, Region IV l Resident Inspectors, CPSES ,

i Pr. Arthur C. Tate Bureau of Radiation Control  :

Texas Department of Public Health  !

1100 West 49th Street Austin, Texas 78704 l

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l Attachinent I to TXX 95214  :

'Page 1 of 1 -

UNITED STATES OF AMERICA l i

NUCLEAR REGULATORY COMMISSION In the Matter of )

) t Texas Utilities Electric Compar:y ) Docket Nos. 50-445  :

) 50 446  :

(Comanche Peak Steam Electric ) License Nos. NPF-87 '

Station Units 1 & 2) ) NPF-89.

AFFIDAVIT

J. J. Kelley, Jr. being duly sworn, hereby deposes and says that he is'  !

3 Vice President of Nuclear Engineering and Support for TV Electric, the licensee herein: that he is duly authorized to sign and file with the Nuclear Regulatory Commission this License Amendment Request 95 04: that he is familiar with the content thereof; and that the matters set forth  :

therein are true and correct to the best of his knowledge. information and belief.

J. J. Kelley, Jr.

Vice President of Nuclear Engineering and Support STATE OF TEXAS )

)

COUNTY OF )

Subscribed and sworn to before me, on this IS O day of usT (U S .

Notary Public

/' DONALD rl. WOODLAN

. . Notcry Pubhc State M Tetis CUT =.4s lizoires 4-9-96

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. e Attachinent 2 to TXX-95214 Page 1 of 5  ;

l DESCRIPTION AND ASSESSMENT I. BACKGP,0VND TU Electric proposes to remove several cycle specific parameter limits ,

from the Technical Specification (TS) and to add these limits to the Core Operating Limits Report (COLR). The addition of these limits to the COLR is a result of the evolution from contractor performed reload analyses (Westinghouse) to TU Electric performed reload analyses. The content of t.ie current COLR was primarily based on the Westinghouse determination of what plant specific parameter limits should be in the COLR to support reload analyses using their methodologies. TU Electric has largely replaced the need for Westinghouse reload methodologies through the development and subsequent NRC approval of TV Electric reload methodologies. Part of the desirability of performing in house reload analyses is the ability to perform trade offs between operating margins and analytical design margins, whenever appropriate to optimize the economic performance of the plant while maintaining the required margin of safety. The removal of these parameter limits from the TS and their add: tion to the COLR improves the efficiency of this process.

The removal of these limits from the TS is consistent with the guidance provided in Generic Letter (GL) 88 16. " Guidance for Technical Specification Changes for Cycle-Specific Parameter Limits" (reference 1).

The limits presented in the COLR may be modified, provided the  !

requirements of Specification 6.9.1.6 are met (i.e., the modifications are determined using NRC approved methodologies and meet all applicable limits of the plant safety analysis). The proposed changes result in resource savings for TV Electric and the NRC by eliminating the periodic license amendment requests that would be required for changes to the values of these cycle specific parameters.

The changes contained in this request are plant specific and did not result from changes recommended in the improved Standard Technical Specifications for Westinghouse Plants. NUREG 1431. The CPSES Technical Specifications remain consistent with NUREG-1431.

II. DESCRIPTION OF TECHNICAL SPECIFICATIONS CHANGE REQUEST The affected Technical Specifications are:

1) 2.2.1. " Reactor Trip System Instrumentation Set points" The proposed changes remove all numerical values pertaining to the Overtemperature N-16 set point and add a referral to the COLR. The affected items are Functional Unit 7 and Notes 1 and 2 to Table 2.2-1.

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Attachinent 2 to TXX 95214 i Page 2 of 5 j

2) 6.9.1.6, " Core Operating Limits Report" The proposed changes modify Specification 6.9.1.6a by adding the removed parameter limits to the list of items contained in the COLR.

including a reference to the implementing Technical Specification.

In addition Specification 6.9.1.6b items 1) and 9) are revised to specify the removed parameter limits and their implementing specification.

In summary, TU Electric proposes to revise the CPSES Technical Specifications by removing the cycle specific parameter limits for Overtemperature N 16 reactor trip function from the Technical Specifications, adding this parameter to the list of parameter limits in the COLR, and adding the appropriate references to Administrative Controls section of the Technical Specifications.

III. ANALYSIS Recognizing that the accident analyses may change from cycle to cycle the NRC issued Generic Letter (GL) 88 16 which provides guidelines for the removal of cycle specific limits of selected parameters from the Technical Specifications. In order to remove cycle specific limits, the Generic Letter requires: (1) the addition of the definition of a named formal report that includes the cycle specific parameter limits that have been established using NRC approved methodology and consistent with all applicable limits of the safety analysis (2) the addition of an administrative reporting requirement to submit the formal report on cycle-specific parameter limits to the Commission for information, and (3) the modification of individual technical specification sections to note that the cycle specific parameters shall be maintained within the limits provided in the defined formal report.

TU Electric has previously defined the Core Operating Limits Report (COLR), in Specification 1.10, as the appropriate formal report for cycle-s)ecific parameter limits. Appropriate administrative controls requiring t1e use of NRC approved methodology and providing the reporting requirements for the COLR have also been previously defined in Specification 6.9.1.6.Section II above and Attachment 3 describe the modifications to the specific affected Technical Specification sections including appropriate references to the COLR.

The cycle-specific nature of the parameter limits for Overtemperature N 16 to be removed is discussed below:

The Overtemperature N 16 set point is calculated such that a reactor trip is initiated before conditions are reached which would violate the reactor core safety limits. In addition, an f t (Aq) trip reset function is provided in the N-16 set point equation (currently in Note 1 of Table 2.21) to account for axial power shapes which are more severe than those shapes considered in the development of the

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Attachment 2 to TXX-95214  ;

Page 3 of 5  ;

core safety limits. Therefore, changes in the core safety limits  ;

must be accompanied by a revision to the Overtemperature N 16 set i point equation. Separate from changes to the core safety limits, a <

revised core configuration may also result in axial power shapes i which require a revision to the f (aq) trip reset function.

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Administrative Controls j Consistant with the requirements of GL 88-16, the Administrative Controls i section of the Technical Specifications has been revised to ensure that the removed parameter limits are contained in the COLR, and that those limits are established using NRC approved methodology and are consistent with all applicable limits of the safety analysis.

Summary The limits on the parameters which are removed from the Technical Specifications and added to the CCLR must be developed or justified using -

NRC approved methodologies. All 1;cident analyses, performed in accordance with these methodologies, must meet the applicable, NRC-approved limits of the safety analysis. The removal of parameter limits from the Technical Specification and their addition to the COLR does not obviate the requirement to operate within those limits. Furthermore, any changes to these limits must be performed in accordance with Specification 6.9.1.6c. If any of the applicable limits of the safety analyses are not '

met, prior NRC approval of the change is required, just as is the case for ,

a license amendment request. For the more routine modifications, where .

NRC approved methodologies and limits of the safety analysis remain ,

applicable, the potentially burdensome and lengthy process of amending the  !

Technical Specifications may be avoided. These changes are essentially ';

administrative and the required level uf safety is maintained.

IV. SIGNIFICANT HAZARDS CONSIDERATIONS ANALYSIS TU Electric has evaluated whether or not a significant hazards consideration is involved with the proposed changes by focusing on the r three standards set forth in 10CFR50.92(c) as discussed below:

1. Do the proposed changes involve a significant increase in the probability or consequences of an accident previously evaluated?

The proposed changes remove cycle specific parameter limits from the Technical Specifications, add them to the list of limits contained  :

in the Core Operating Limits Report (COLR), and revise the 1 Administrative Controls section of the Technical Specifications. l The changes do not, by themselves, alter any of the parameter i limits. The changes are administrative in nature and have no  ;

adverse effect on the probability of an accident or on the i consequences of an accident previously evaluated. The removal of i parameter limits from the Technical Specifications does not i eliminate the requirement to comply with the parameter limits. 3

q Attachinent 2 to TXX-95214 Page 4 of 5 The parameter limits in the COLR may be revised without prior NRC approval. However Specification 6.9.1.6c continues to ensure that t1e parameter limits are developed using NRC approved methodologies and that applicable limits of the safety analyses are met. While future changes to the COLR parameter limits could result in event consequences which are either slightly less or slightly more severe than the consequences for the same event using the present parameter limits, the differences would not be significant and would be bounded by the requirement of specification 6.9.1.6c to meet the applicable limits in the safety analysis.

Based on the above, removal of the parameter limits from the Technical Specifications and the addition of these limits the list of limits in the COLR, thus allowing revision of the parameter limits without prior NRC approval, has no significant effect on the probability or consequences of an accident previously evaluated.

2. Do the proposed changes create the possibility of a new or different kind of accident from any accident previously evaluated?

The proposed changes remove certain parameter limits frem the Technical Specifications and add these limits to the list of limits in the COLR, removing the requirement for prior NRC approval of revisions to those parameters. The changes do not add new hardware or change plant operations and therefore cannot initiate an event nor cause an analyzed event to progress differently. Thus, the possibility of a new or different kind of accident is not created.

3. Do the proposed changes involve a significant reduction in a margin of safety?

The margin of safety, as it relates to a parameter limit, is the ,

difference between the acceptance criterion for that parameter and its failure value. The proposed changes do not affect the failure values for any system. Through the accident analyses, all relevant event acceptance criteria (as described in the NRC-approved analysis methodologies) are shown to be satisfied; therefore, th re is no impact on an event acceptance criteria. Because neither the failure values nor the acceptance criteria are affected, the proposed change has no effect on the margin of safety.

Based on the above evaluations TV Electric concludes that the activities associated with the proposed changes satisfy the no significant hazards consideration standards of 10CFR50.92(c) and accordingly, a no significant >

hazards consideration finding is justified.

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Attachment 2 to TXX 95214 Page 5 of 5 ,

i V. ENVIRONMENTAL EVALUATION TU Electric has evaluated the proposed changes and has determined that the changes do not involve (1) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of .

any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, s

, the proposed changes meet the eligibility criterion for categorical '

exclusion set forth in 10CFR51.22(c)(9). Therefore. pursuant to 10CFR51.22(b), an environmental assessment of the proposed change is not required.

VI. REFERENCES

1. Generic Letter 88-16 " Guidance for Technical Specification Changes {

for Cycle Specific Parameter Limits," October 4. 1988 '

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ATTACHMENT 3 AFFECTED TECHNICAL SPECIFICATION PAGES (NUREG 1468)

(Pages 2 5, 2 9. 2 10, 2 11. 6 20, 6 21) i i

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