ML19253C496
| ML19253C496 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 10/16/1979 |
| From: | Banks H CAROLINA POWER & LIGHT CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML19253C492 | List: |
| References | |
| GD-79-2575, NUDOCS 7912050629 | |
| Download: ML19253C496 (2) | |
Text
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Carolina Power & Light Company October 16, 1979 FILE: NG-3513 (B)
SERIAL: GD-79-2575 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Ssite 3100
- g Atlanta, Georgia 30303 E
BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1&2 E
LICENSE NOS. DPR-71 AND DPR-62
' 2' DOCKET NOS. 50-325 AND 50-324 RESPONSE TO INFRACTIONS OF NRC FEQUIREMENTS
Dear Mr. O'Reilly:
Brunswick Steam Electric Plant has reviewed IE Inspection Report 50-324/79-29 and 50-325/79-30 and finds that it does not contain any information of a proprietary nature.
The report identified one item which appeared to be in noncompliance with NRC requireme.:ts. This item and Carolina Power &
Light Company's response are addressed in the following text:
INFRACTION As required by 10CFR50 Appendix B, Criteria V, activities affecting quality shall be prescribed by documented instructions and procedures of a type appropriate to the circumstance. ANSI N18.7-1972, as committed to by CF&L Quality #ssurance Program, requires limitations on the parameters being controlled and appropriate corrective measures to return the parameters to the normal control band be specified.
Contrary to the above, on July 18, 1979, Unit No. I recirculation loop "B" was returned to service per operating procedure OP-2, Section F.
This section requires that the recirculation pump discharge valve be held open initially for a maximum of 2 seconds followed by a 10 second wait. In the performance of this procedure a power transient occurred that resulted in upscale APRM's tripping the reactor. The limitations in the procedure on opening the discharge valve were inadequate to limit the power transient and thus praclude challenging of the caf aty systems which resulted in a reactor trip.
CAROLINA POWER & LIGHT COMPANY'S RESPONSE jf Q}} OP-2 on the reactor recirculation system has been revised as follows: 1. Prior to starting a reactor recirculation pump with the reactor critical, insert control rods as necessary to c 29 [4 g
- C L 411 Fayetteville Street
- P. O. Box 1551
- Raleigh. N. C. 27602 f
7912050
Mr. James P. O' Reilly October 16, 1979 g obtain 2 10% margin between APRM reading and the APRM Rod Block Setpoints. 2. Reduce the running reactor recirculation pump speed to 2 50% prior to starting the idle recirculation pump. 3. When referring to the pump discharge valve, the wording has been changed from "open" to " jog". General Elec'-ic's recommended recirculation pump discharge valve jogging sequency was compoced with the "2 second jog and 10 second wait" and an evaluation was made. Our procedure as revised is more conservative than the GE procedure; therefore, the "2 second jog and 10 second wait" was not changed. A scram review meeting was conducted with those involved with the scram and plant management. The incident has been reviewed by all Operations personnel. Yours very truly, H. R. Banks Manager Nuclear Generation CSB/eaj* 1504 051 .}}