ML20071C066
| ML20071C066 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 02/24/1983 |
| From: | Utley E CAROLINA POWER & LIGHT CO. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0619, RTR-NUREG-619 LAP-83-34, NUDOCS 8303010452 | |
| Download: ML20071C066 (2) | |
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4 Cp&L Carolina Power & Light Company FE8 34 ggg3 SERIAL: LAP-83-34 Director of Nuclear Reactor Regulation At tention:
Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing United States Nuclear Regulatory Commission Washington, DC 20555' BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO.1 DOCKET NOS. 50-325 LICENSE NOS. DPR-71 BWR FEEDWATER AND CRD RETURN LINE N0ZZLE CRACKING
Dear Mr. Vassallo:
In our letter of October 7,1981 (Serial No. NO-81-1653), Carolina Power & Light Company (CP&L) submitted a schedule for the implementation of NUREG-0619 requirements for the Brunswick Steam Electric Plant, Unit Nos. I and 2.
Item 3 of that schedule stated that the Unit No. I control rod drive (CRD) return line would be cut and capped during the current refueling outage. Carolina Power & Light Company hereby revises the schedule for cutting and capping the Unit No.1 CRD return line to the next refueling outage on Unit No. 1, schaduled for 1984. This - schedule revision is based on the following:
1.
Due to the current inventory in the Unit No. I spent fuel pool and the inability to transfer spent fuel bundles to the Unit No. 2 pool, the Unit No. I core could not.be totally defueled during this outage as anticipated (approximately 88 bundles remain in the vessel). The water level reduction required to perform this task would require securing shutdown cooling and could present ALARA concerns.
High density fuel racks are currently scheduled to be installed in the spent fuel pool for Unit No. I prior to the next scheduled refueling outage, thereby providing adequate spent fuel storage for a complete core off-load.
2.
The remaining commitments of Item 3 are being performed (installation of equalizing valves, replacement of carbon steel pipe in the flow stabilizer loop, rerouting to the cooling water header, testing, and procedure changes).
Ultrasonic Testing (UT) will be performed on the inner' radius in lieu of the liquid penetrant test.
In addition, all of the welds on the stainless steel portion of the CRD return line have been ultrasonically tested during the present outage using the IEB 82-03 qualified Ur technique, and no indications have been noted. As the CRD jf cyC)l F43'03010452 830224 PDR ADOCK 05000325 ille Street
- P. O. Box 1551
- Raleigh, N. C. 27602 P
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'o D. B. Vassallo
' 2-return line has been isolated since 1979, and all other improvements are being incorporated, it is felt that the cutting and capping of this line can be delayed for an additional fuel cycle.
Carolina Power & Light Company has evaluated this schedule change and does not believe it will affect the health or safety of the public.
If you have any questicas on this schedule change, please contact a member of our staff.
Yours very truly,
//
E. E. Utley Executive Vice President Power Supply and
. Engineering & Construction RMP/WRM/ mag (6231WRM) cc:
Mr. D. O. Myers (NRC-BSEP)
Mr. J. P. O'Reilly ( NRC-RII)
Mr. S. D. MacKay (NRC) s
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