ML20245C230

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Application for Amend to License NPF-3,relocating cycle-specific Core Operating Limits from Tech Specs to Core Operating Limits Rept
ML20245C230
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 06/16/1989
From: Shelton D
TOLEDO EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20245C209 List:
References
GL-88-16, NUDOCS 8906260098
Download: ML20245C230 (5)
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Lipann Nuibar NPF-3

. Serial Number 1668-

' Enclosure' Page 1 APPLICATION FOR AMENDMENT' TO FACILITY OPERATING LICENSE NUMBER NPF-3 DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 Attached are requested changes to the Davis-Besse Nuclear Power Station, Unit No. 1 Facility Operating License No. NPF-3.. Also included are the Technical Description.and Significant Hazards Consideration.

.The proposed changes (submitted under cover letter Serial Number'1668) concern:

Table'of Contents; Section 1.41, Core Operating Limits Report (New);.Section 3/4.1.1.3,'Hoderator Temperature Coefficient; Section'3/4.1.3.6, Regulating Rod Insertion'Limitst.Section 3.1.3.7, Rod Program; Section 3.1.3.8, Xenon Reactivity; Section 3/4.1.3.9, Axial Power Shaping Rod Insertion Limits;

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Section 3/4.2.1,.' Axial-Power Imbalanc~e; Section 3/4.2.4,-Quadrant Power Tilt; Section 6.9.1.7, Core Operating Limits Report.(New); Figures 3.1-2a and b, Regulating Group Position Limits, Four RC Pumps; Figures'3.1-3a and b,

~ Regulating. Group Position Limits, Three RC Pumps; Figure 3.1-4, control Rod Core. Locations and Group Assignments;. Figures 3.~1-Sa, b and c, APSR Position Limits; Figure 3.2-1,. Axial Power Imbalance Limits, Four RC Pumps; Figure 1

3.2-2, Axial Power Imbalance Limits,.Three RC Pumps; and Table 3.2-1, Quadrant Power Tilt Limits.

For: D. C. Shelton Vice President Nuclear By: -

T. J. ye , Technical Services Director Sworn and subscribed before me this 16th day of June, 1989.

Lk N6tary Public, State of Ohio r

LAURIE A.HINKLE Notary Pubfr.. State of Ohio e b kDobk$$ohoh46

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Ligtnsa Numb:r NPF-3 'l Serial Number 1668 '

Enclosure Page 2 The followinglinformation is provided to support issuance of the requested changes to the Davis-Besse Nuclear Power Station, Unit No. 1 Operating License Number NPP-3, Appendix A, Technical Specifications.

A. Time Required to Implement: This change is to be implemented prior to Hode 4 entry during startup from the sixth refueling outage.

B. Reason for Change (License Amendment Request Number 89-0008):

Generic Letter 88-16 provided guidance for removal of cycle-specific core operating limits from the Technical Specifications and relocation of these limits to a Core Operating Limits Report, if the limits are determined-using an NRC approved methodology. This will allow removing an unnecessary burden on the licensee and the NRC in the preparation of a license amendment to change these limits at each refueling.

[ C. Technical

Description:

See attached Technical Description (Attachment 1).

D. Significant Hazards Consideration: See attached Significant Hazards Consideration (Attachment 2).

E. Methodology - Rod Program (Attachment 3).

F. Sample Core Operating Limits Report (Attachment 4).

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, Lic:nsa Nu;b:r NPF-3 Serial Number 1668

-Attachment 1 Page 1 TF.CHNICAL DESCRIPTION DESCRIPTION OF PROPOSED TECHNICAL SPECIFICATION CHANGE This Technical Description addresses the proposed removal of cycle' specific core operating limits from Technical Specifications (TS) in accordance with NRC Generic Letter 88-16, dated October 4, 1988. The limits vill be relocated to a CORE OPERATING LIMITS REPORT and the CORE OPERATING LIMITS REPORT will be

, defined in the Definitions Section of TS. In addition, a new administrative reporting requirement for the CORE OPERATING LIMITS REPORT will be added to the existing-reporting requirements of TS. The proposed amendment revises various Section 3/4 Specifications and applicable Bases to state that the cycle-specific parameters shall be maintained within the limits provided in the CORE OPERATING LIMITS REPORT and also make various editorial changes consistent with this proposed amendment. ,

SYSTEMS AFFECTED The proposed change affects Technical Specifications related to the nuclear fuel and associated components. However, relocating the operating limits is administrative only and:does not affect the hardware design.

DOCUMENTS AFFECTED Davis-Besse Nuclear Power Station, Unit No. 1 Operating License, Appendix A, Technical Specifications Sections:

Table of Contents; (Nev) 1.41 Core Operating Limits Report; 3/4.1.1.3 Moderator Temperature Coefficient; 3.1.3.6 Regulating Rod Insertion Limits; 4.1.3.6 Regulating Rod Insertion Limits; 3.1.3.7 Rod Program; 3.1.3.8 Xenon Reactivity; 3.1.3.9 Axial Power Shaping Rod Insertion Limits; 4.1.3.9 Axial-4 Power Shaping Rod Insertion Limits; 3.2.1 Ax_al Power Imbalance; 4.2.1 Axial Power Imbalance; 3.2.4 Quadrant Power Tilt; 4.2.4 Quadrant Power Tilt; (New) 6.9.1.7 Core Operating Limits Report Figures 3.1-2a and b Regulating Group Position Limits, Four RC Pumps; 3.1-3a and b Regulating Group Position Limits, Three RC Pumps;'3.1-4 Control Rod Core Locations and Group Assignments; 3.1-Sa, b and c APSR Position Limits; 3.2-1 Axial Power Imbalance Limits, Four RC Pumps; 3.2-2 Axial Power Imbalance Limits, Three RC Pumps Table:

3.2-1 Quadrant Power Tilt Limits  !

I SAFETY FUNCTION OF THE SYSTEMS AFFECTED j 1

The safety function of the affected TS is to ensure operation of the core within prescribed limits. With these prescribed limits, assurance is maintained that the control rod assemblies provide trippable reactivity, shutdown margin capability and maintain peaking within acceptable limits;  ;

the core generates power for a specified duration and at a specified maximum j level; and the fuel is arranged such that safety limits are not violated.

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Serial Numb r 1668 Attachment 1 Page 2 EFFECTS ON SAFETY 1 On October 4, 1988 the NRC issued Generic Letter 88-16. The Generic Letter l provides for the removal of cycle-specific operating limits from TS provided these limits are determined using an NRC approved methodology. The .y requirements to preserve the limits are to remain within the TS.

J Babcock & Wilcox_(B&W) has previously submitted to and received approval from NRC for Topical Reports BAV-10122A, Revision 1, " Normal Operating Controls" ]

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(reference 2, NRC Safety Evaluation Report (SER) dated April 20, 1984), and BAV-10118A, " Core Calculational Techniques and Procedures (reference 3, NRC SER dated September 25, 1979). Topical Report BAV-10122A, Revision 1, describes the methodology used by B&W to determine the operating limits for axial power imbalance ranges, control rod insertion ranges, axial power shaping rod insertion changes and quadrant power tilt limits. Topical Report BAV-10118A describes the methodology used by B&W to establish limiting conditions for operation for the moderator temperature coefficient.

Attachment 3 describes the methodology B&V uses for calculating programmed rod =

positions for TS 3.1.3.7 Rod Program. This is the same methodology as used previously for the DBNPS. As this methodology is not included in BAV-10118A, it is requested that this methodology be approved with this change request as it vill be utilized in determining the parameters to be used in the CORE OPERATING LIMITS REPORT for the Rod Program. It should be noted that this ,

methodology has also been requested to be approved in Florida Power i Corporation's submittal for Crystal River Unit 3 dated March 22, 1989.  !

The cycle-specific core operating limits calculated in accordance with the approved methodologies vill be included in the CORE OPERATING LIMITS REPORT.

The report vill be provided to the NRC per the requirements of proposed TS 6.9.1.7. Controlled copies of the CORE OPERATING LIMITS REPORT vill be maintained and revised as required by future reload cycles. Attachment 4 provides a sample copy of the CORE OPERATING LIMITS REPORT for information only.

Relocating the cycle-specific core operating limits to the CORE OPERATING LIMITS REPORT is an administrative change only and vill not impact the methodology used by B&W to determine the limits. Therefore, there is no impact or effect on safety.

UNREVIEVED SAFETY OUESTION CONCLUSIONS The following conclusions are provided as a result of Toledo Edison's review of the proposed changes to the Davis-Besse Nuclear Power Station, Unit No. 1, Operating License, Appendix A, Technical Specifications and Bases.

The proposed-action would not increase the probability of occurrence of an accident previously evaluated in the USAR because there are no hardware changes or design modifications which would affect the probability of an accident. The relocation of the core operating limits to a new document does not change the method of limit determination and is, therefore, an administrative change only. (10CFR50.59(a)(2)(i))

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Lic;na Numb:r NPF-3 Serial Number 1668 Attachment 1 Page 3 The proposed action vould not increase the consequence of an accident previously evaluated in the USAR because relocating the core operating limits to a new document is administrative in nature. (10CFR50.59(a)(2)(i))

The proposed action vould not increase the probability of occurrence of a malfunction of equipment important to safety because there are no hardware i

changes or design modifications which would affect the probability of a malfunction. The relocation of the core operating limits to a new document does not change the method of limit determination and is, therefore, an administrative change only. (10CFR50.59(a)(2)(i))

The proposed action would not increase the consequence of a malfunction of equipment important to safety because relocation of the core operating limits to a new document is administrative in nature. (10CFR50.59(a)(2)(i))

The proposed action vould not create a possibility for an accident of a different type than any evaluated previously in the USAR because there are no hardware changes or design modifications. The relocation of the core operating limits to a new document does not change the method of limit determination and is, therefore, an administrative change only.

(10CFR50.59(a)(2)(ii))

The proposed action would not create a possibility for a malfunction of equipment of a different type than any evaluated previously in the USAR because there are no hardware changes or design modifications. The relocation of the core operating limits to a new document does not change the method of limit determination and is, therefore, an administrative change only.

(10CFR50.59(a)(2)(ii))

The proposed action would not reduce the margin of safety as defined in the basis for the Technical Specifications because the operating limits vill be determined using the same methodology as in previous core operating limit calculations. (10CFR50.59(a)(2)(iii))

Pursuant to the above, this change to the Technical Specifications does not involve an unreviewed safety question.

REFERENCES

1) Davis-Besse Nuclear Power Station, Unit No. 1 Operating License, Appendix A, Technical Specifications.
2) Normal Operating Controls, G. E. Hanson, May, 1984 (BAV-10122A, Rev. 1)
3) Core Calculational Techniques and Procedures, J. J. Romano, December, 1979 (BAV-10118A)

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