ML20215H175

Recommends Issuance of Fuel Load & Precritical Testing License Based on Encl Rept, Initial OL Readiness Assessment for Braidwood Station,Unit 1. Util Ready to Load Fuel & Capable of Safely Performing Tests

ML20215H175
Person / Time
Site:	Braidwood
Issue date:	10/17/1986
From:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20215H178	List: ML20215H175 ML20215H180
References
NUDOCS 8610230001
Download: ML20215H175 (3)

Text

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+ po 007 1 7 1986 Docket No. 50-456 MEMORANDUM FOR: Harold R. Denton, Director, Office of Nuclear Reactor Regulation FROM: ' James G. Keppler, R'egional Administrator, Region III

SUBJECT:

BRAIDWOOD STATION, UNIT 1 FUEL LOAD AND PRECRITICAL TESTING LICENSE RECOMMENDATION This is to recommend the issuance of a Fuel Load and Precritical Testing. License for Braidwood Unit 1 pursuant to the provisions of 10 CFR 50.57(c).

The bases for this recommendation are contained in an extensive Readiness Assessment Report, which is attached. The results of that evaluation are summarized below and form the basis for our recommendation.

1. The construction and preoperational testing programs have verified that Braidwood Unit 1 has been constructed substantially in conformance with the construction permit and the appl? cation, as amended, the provisions of the Act, and the rules and regulations of the Commission, as required by 10 CFR 50.57(a)(1) and (2).

2. A Region III staff evaluation has concluded that Commonwealth Edison Company (CECO) is ready to load fuel and is capable of safely performing precritical testing of Braidwood Unit 1. Included in this evaluation were preoperational tests and testing exceptions identified in the attachments.to the September 19, 1986-letter from Mr. Dennis Farrar to Mr. Harold Denton. These exceptions shall be completed in accordance with the scheduled commitments contained in those attachments.

3. Region III has worked closely with NRR in reviewing CECO's application for a Fuel Load and Precritical Testing License pursuant to 10 CFR 50.57(c).

This has included a review of licensee special procedures to ensure subcriticality is maintained. The proposed licensee program appears to provide reasonable assurance that the reactor will remain subcritical by an adequate margin during all evolutions authorized by this license.

4. Each Region III professional was requested by memorandum dated July 11, 1986, to identify concerns which might restrain the issuance of a license, beyond those already addressed by inspection reports. No concerns were identified.

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Harold R. Denton 2 GCT 17 6 Highlights of the evaluation include:

• In excess of 22,000 inspection hours have been devoted to the Braidwood site since issuance of a construction permit in December 1975.

• Reviews of the proposed Technical Specifications (TS) and the surveillance test program, as part of our preoperational inspections, have provided reasonable assurance that the TS are compatible with and accurately reflect the as-built plant status.

• NRC' investigation and inspection of allegations raised to Region III with respect to Braidwood Unit 1 construction have identified no significant hardware impact and no unresolved safety issues relative to the issuance of a Fuel Load and Precritical Testing License.

• Based on our inspections and reviews, we have concluded that the quality assurance program at Braidwood including the special construction assessment program (BCAP), has provided adequate assurance that the plant has been constructed substantially in accordance with re'gulatory requirements and will suppor.t safe facility operation.

In addition, we plan to continue our inspections and evaluations to monitor Ceco's preparation and the plant's suitability for subsequent low power licensing. During the next several months, we plan to conduct inspections to evaluate the effectiveness of the special procedures implemented by the licensee to maintain the reactor subcritical. This will include both a review of the administrative control over valves which could cause boron dilution as well as other procedures implemented to maintain boron concentration.

In conclusion, I find that Braidwood Station, Unit 1, has been constructed substantially in accordance with Construction Permit CPPR-132, with the FSAR, and with NRC regulations. I also find that Commonwealth Edison Company is ready to load fuel and commence safe ~ precritical operation of the facility.

Origianal Signed by James G. Keppler James G. Keppler Regional Administrator

Attachment:

Region III Readiness Assessment Report for Braidwood See Attached Distribution RIII RIII RI]

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Harold R. Denton 3 ,0 01 1 't 1900 Distribution cc w/ attachment:

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