ML19340A115

Forwards Proposed Tech Spec 5.3.3.1 Re Unit 1,Cycle 4 Operation within Applicable Fuel Design & Performance Criteria.Forwards Revised Page for BAW-1447, Oconee Unit 1,Cycle 4 Reload Rept.

ML19340A115
Person / Time
Site:	Oconee
Issue date:	06/21/1977
From:	Parker W DUKE POWER CO.
To:	Case E Office of Nuclear Reactor Regulation
Shared Package
ML19340A116	List: ML19340A115 ML19340A123
References
NUDOCS 7911250039
Download: ML19340A115 (4)

Text

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NRC DISTR'IBUTION PoR PART 50 DOCKET MATERIAL FROM: oATE oF oCCUMENT TO: Duke Power Company 6/21/77 Mr. Edson G. Case Charlotte, North Carolina DATE RECEIVED William O. Parker, Jr. 6/27/77 P NoTo RIZE D PROP INPUT FORM NUMBER CF COPIES RECEIVED M ETTEn halGINAL

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the Amdt. to OL/ Change to tech specs.....

following: concerns operation of Oconee 1 Cycle 4 operation with revised page 3-1 for report BAW-1447, "Oconee Unit 1, Cycle 4 Reload Report"...

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9 Mr. Edson G.: Case, Acting Director ...- ".4 Office of Nuclear Reactor Regulation- r

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Washington, D. C. 20555 7 ',.s N,c N A w Re: 'Oconee Unit ~l Docket No. 50-26 0$[6f0GD uCC. ~V ,:.lyg'q g g Q act

Dear Sir:

My letter of March 30, 1977 provided proposed Technical Specification amendments _and: supporting documentation to assure _ operation of the Oconee Unit 1 Cycle 4 core within applicable fuel design and performance criteria. Subsequent to thisisubmictal, a progjam has been initiated to remove _one'of the axial power ~ shaping rod (APSR) assemblies for destructive examination in order to obtain more information relative to the ef fects of irradiation on the material properties. Since this assembly ~has seen three cycles of irradiation exposure, a replacement APSR assembly with an equivalent poison worth will be inserted in its place. To. compensate for this poison worth loss, the new component will

.be identical to the_ standard B&W design except that'it will have fifteen silver-indium-cadmium (Ag-In-Cd) poison rods and one Inconel-718 rod.

An evaluation of the nuclear, mechanical and thermal hydraulic considera-tions of this program have been conducted and it is considered that safe operation of the reactor will.not be adversely affected.

It is_ requested that this letter be considered as a supplement to the March ~30, 1977 letter supporting the operation of Oconee 1 Cycle 4 operation. Additionally, pursuant to 10CFR50.90, it is requested that Technical Specification 5.3.3.1 be revised as indicated on the attached Technical Specification replacement page to incorporate this change.

A revised page 3-1 is also. attached for report BAW-1447, "Oconee Unit 1,

- Cycle-4' Reload Report".

Very truly yours, hWilliam O. Parker, . Jr y

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MST:ge-Attachment

. .- . Juna 21,.1977 ,, y P:ga - 2;.

WILLIAM 0. PARKER, JR.,t being duly sworn, . states that he is Vice President of Duke Power Company;.that he is authorized on the part of-said Company

. to sign and file with the Nuclear Regulatory Commission this request for

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amendment of the Oconee Nuclear-Station Facility Operating Licenses DPR-38,

- DPR-47, and DPR-55; and. that all statements and matters set forth therein

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! are true and correct to the best of his knowledge.

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41. a QN William O. Parker, Jr., Cice President

.i Subscribed and sworn to-before me this 21st day of June, 1977.

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AAAR Notary Public s.

. My Commission Expires:

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3. GENERAL DESCRI? TION The Oconee Unit 1 reactor core is' described in detail in section 3 of the Oconee Nuclear Station, Uni: 1, Final . Safety Analysis Reportl.

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The Cycle 4 core, comprising -batches 4', 5, and 6, contains 177 fuel assemblies, each of which 'is a 15.by 15. array containing 208 fuel rods,16 control rod guide tubes,'and one incore inst'r=nent guide tube. The fuel pin clad' ding is .

cold-worked Zircaloy-4 with an OD of 0.430 inch and a vall thickness of 0.0265 inch. The fuel consists of dished-end, cylindrical pellets of uranium dioxide which are 0.370 inch in diameter. (See Tables 4-1 and 4-2 for additional data.) The fuel assemblies in batches 4, 5, and 6 have an average nominal fuel loading of 463.6 kg of uranien. The undensified nominal active fuel lengths and theoretical densities vary between bacches and are presented in Tables 4-1 and 4-2.

Figure 3-1 is the core loading diagram for Oconee 1, Cycle 4 The initial enrichments of batches 4A and 43 were 2.60 and 3.20 we % 235U, respectively.

3atches 5 and 6 are enriched to 2.75 and 2.795 v: % 235g, respectively. All the batch 3 assemblies will be discharged at the end of Cycle 3. The batch 4A, 43', . and 5 assemblies will be shuffled to new locations at the beginning of Cycle 4 The fresh batch 6 assemblies will occupy the periphery of :he core. Figure 3-2 is an eighth-core =ap showing-the asse=bly burnup and en-richment distribution.at che'beginning of Cycle 4.

Reactivity control is supplied by 61 full-leng:h Ag-In-Cd control rods and by

. soluble boron shim. In addition to the full-length control rods, eight axial power . shaping rods are provided for additional control of the axial power cis-tribution. One APSR will be a new centrol rod assembly identical to the standard, design except that it will have fif teen Ag-In-Cd poison rods and one Inconel-718 rod; The Cycle 4 locations of the 69 control rods and the '

group designations are indicated in Figure 3-3. The tore locacions of the total pa :ern (69 control rods) for Cycle 4 are identical to those of the o

reference cycle indicated in the Oconee 1, Cycle 3 ReIcad Report.- The group 'designa: ions,1however, differ between Cycle 4 and the reference cycle -in order to' minimice power peaking.

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