ML19340A115
| 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: |
| References | |
| NUDOCS 7911250039 | |
| Download: ML19340A115 (4) | |
Text
CoCKET NWrE R u.s. NUCLEAR f;EGULAToRY POMMISSloN j O
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NRC DISTR'IBUTION PoR PART 50 DOCKET MATERIAL FROM:
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Duke Power Company 6/21/77 Mr. Edson G. Case Charlotte, North Carolina DATE RECEIVED William O. Parker, Jr.
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- the Amdt. to OL/ Change to tech specs.....
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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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DUKE POWER COMPANY Powen 13 cit.ntwo -
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June 21, 1977 WCr PatSicgwy Tc;gewowc Aata 704 Srca= peocucno's 373-4083 Q\\'~~L-9
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Mr. Edson G.: Case, Acting Director
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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, h
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William O. Parker,. Jr y MST:ge-Attachment
Juna 21,.1977 y
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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
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. to sign and file with the Nuclear Regulatory Commission this request for 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 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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. My Commission Expires:
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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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