ML17310A616

Proposed Tech Specs Section 6.9.1.10 Re Sys 80 Inletflow Distribution to List of Methods Used to Determine Core Operating Limits

ML17310A616
Person / Time
Site:	Palo Verde
Issue date:	09/08/1993
From:	ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
Shared Package
ML17310A614	List: ML17310A613 ML17310A616
References
NUDOCS 9309170176
Download: ML17310A616 (10)

Text

ENCLOSURE PROPOSED AMENDMENTTO TECHNICAL SPECIFICATION SECTION 6.9.1.10 .

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A. DESCRIPTION OF AMENDMENT REQUEST The proposed amendment would add a supplement to the analytical methodology listed in PVNGS Unit 1 Technical Specifications Section 6.9.1.10, item d.

Current wording:

d. "Modified Statistical Combination of Uncertainties," CEN-356(V)-P-A Revision 01-P-A, May 1988 (Methodology for Specification 3.2.4, DNBR Margin and 3.2.7 Axial Shape Index).

Proposed wording:

d. "Modified Statistical Combination of Uncertainties," CEN-356(V)-P-A Revision 01-P-A, May 1988 and "System 80' Inlet Flow Distribution," Supplement 1-P to Enclosure 1-P to LD-82-054, February 1993 (Methodology for Specification 3.2.4, DNBR Margin and 3.2.7 Axial Shape Index).,

B. PURPOSE OF THE TECHNICAL SPECIFICATION Specifications Section 6.9.1.10 lists the analytical methods used to I'echnical determine the core operating limits. Plant operation is limited in accordance with the values of cycle-specific parameter limits that are established using these NRC approved methodologies. The methodology listed in item d is used for Specifications 3.2.4, DNBR Margin and 3.2.7, Axial Shape Index.

C. NEED FOR THE TECHNICAL SPECIFICATION AMENDMENT The methodology supplement, "System 80' Inlet Flow Distribution," Supplement 1-P to Enclosure 1-P to LD-82-054, February 1993, was submitted to the NRC on March 30, 1993, for review and approval. This methodology supplement describes a revised core inlet flow distribution for use with ABB-Combustion Engineering (ABB-CE) Statistical Combination of Uncertainty methodology for assessing core thermal margin, as applied to ABB-CE System 80' units.

The NRC Staff has been reviewing this methodology supplement, and has indicated that approval will be forthcoming. In order to utilize this methodology supplement following NRC approval, it is necessary to add it to the list of analytical methods in Technical Specifications Section 6.9.1.10 by a Technical Specification amendment.

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D. SAFETY ANALYSIS OF THE PROPOSED AMENDMENT REQUEST This proposed amendment would add a methodology supplement to the analytical methods used to determine the core operating limits. The supplement was submitted to NRC for review on March 30, 1993, and is expected to be approved by for use at PVNGS prior to issuance of this Technical Specification amendment. Since NRC staff will have reviewed and approved the supplement, this proposed amendment to add the supplement to the list of analytical methods in Technical Specifications Section 6.9.1.10 is considered to be administrative in nature.

E. NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION The Commission has provided standards for determining whether a significant hazards consideration exists as stated in 10 CFR 50.92. A proposed amendment to an operating license for a facility involves a no significant hazards consideration if operation of the facility in accordance with a proposed amendment would not: (1)

Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Involve a significant reduction in a margin of safety. A discussion of these standards as they relate to this amendment request follows:

Standard 1 Involve a significant increase in the probability or consequences of an accident previously evaluated.

The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. The proposed change is administrative in nature and does not involve any change to the configuration or method of operation of any plant equipment that is used to mitigate the consequences of an accident. Also, the proposed change does not alter the conditions or assumptions in any of the Final Safety Analysis Report (FSAR) accident analyses. Since the FSAR accident analyses remain bounding, the radiological consequences previously evaluated are not adversely affected by the proposed change. Therefore, it can be concluded that the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

Standard 2 Create the possibility of a new or different kind of accident from any accident previously analyzed.

The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. The proposed change is administrative in nature and does not involve any change to the configuration or 2of3

method of operation of any plant equipment that is used to mitigate the consequences of an accident. Accordingly, no new failure modes have been defined for any plant system or component important to safety nor has any new limiting failure been identified as a result of the proposed change. Therefore, it can be concluded that the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

Standard 3 Involve a significant reduction in a margin of safety.

The proposed change does not involve a significant reduction in a margin of safety.

The proposed change is administrative in nature and does not adversely impact the plant's ability to meet applicable regulatory requirements. Therefore, it can be concluded that the proposed change does not involve a significant reduction in a margin of safety.

F. ENVIRONMENTALIMPACT CONSIDERATION DETERMINATION The proposed Technical Specification amendment is administrative in nature. The proposed amendment involves no change in the amount or type of any effluent that may be released offsite, and there is no increase in individual or cumulative radiation exposure. As such, operation of PVNGS Unit 1 in accordance with the proposed amendment does not involve an unreviewed environmental safety question.,

8. MARKED-UP TECHNICAL SPECIFICATION PAGE 6-20a

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FOR INFORMATION 0 LY ADMINISTRATIVE CONTROLS 6.9.1.9'ore operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

Shutdown Margin KN

- Any CEA Withdrawn for Specification 3.1. 1.2 1

b. Moderator Temperature Coefficient BOL and EOL limits for Specification 3.1.1.3 C. Boron Dilution Alarms for Specification 3.1.2.7

d. Movable Control Assemblies - CEA Position for Specification 3.1.3.1

e. Regulating CEA Insertion Limits for Specification 3.1.3.6

f. Part Length CEA Insertion Limits for Specification 3.1.3.7

g. Linear Heat Rate for Specification 3.2.1

h. Azimuthal Power Tilt - T for Specification 3.2.3 DNBR Margin for Specification 3.2.4 Axial Shape Index for Specification 3.2.7 6.9.1.10 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:

a~ "CE Method for Control Element Assembly Ejection Analysis,"

CENPD-0190-A, January 1976 (Methodology for Specification 3.1.3.6, Regulating CEA Insertion Limits).

b. "The ROCS and DIT Computer Codes for Nuclear Design," CENPD-266-P-A, April 1983 (Methodology for Specifications 3.1.1.2, Shutdown Hargin KN 1 Any CEA Wi thdrawn; 3. l. l. f 3, Moderator Temperature Coef i ci ent BOL and EOL limits and 3.1.3.6, Regulating CEA Insertion Limits).

C. "Safety Evaluation Report related ~ the Final Design of the Standard Nuclear Steam Supply Reference Systems CESSAR System 80, Docket No.

STN 50-470, "NUREG-0852 (Novenber 1981), Supplements No. 1 (March 1983),

No. 2 (September 1983), No. 3 (December 1987) (Methodology for Specifications 3. 1. 1.2, Shutdown Margin KN 1 - Any CEA Withdrawn;

3. l. 1.3, Moderator Temperature Coefficient BOL and EOL limits;

3. 1.2.7, Boron Dilution Alarms; 3.1.3.1; Movable Control Assemblies - CEA Position; 3.1. 3. 6, Regulating CEA Insertion Limits; 3.1.3.7, Part Length CEA Insertion Limits and 3.2.3 Azimuthal Power Tilt - T ).

d. "Hodified Statistical Combination of Uncertainties," CEN-356(V)-P-A Revision Ol-P-A, Hay 1988 (Methodology for Specification 3.2.4, DNBR Margin and 3.2.7 Axial S ape Index).

and "Sys4e~ go lnl<4 F(om l)is(>>ibg4ioz," S~) j(caen 4 )- p +0 Enclosure I-l 4o L'b- 3'2-os/, F'~p>>

PALO VERDE - UNIT 1 6-20a AMENDHEHT NO 69

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