ML19331D362
| ML19331D362 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/07/1980 |
| From: | Furr B CAROLINA POWER & LIGHT CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| IEB-80-17, NO-A-1169, NUDOCS 8009020199 | |
| Download: ML19331D362 (2) | |
Text
v. e,
.a.
6, Form 244 Carolina Power & Light Company
. II A 9: 43 Brunswick Steam Electric Plant Company Carrespondence P. O. Box 10429 Southport, N. C.
28461 August 7, 1980 FILE: B09-13513 SERIAL: NO-A-1169 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 & 2 LICENSE NOS. DPR-71 AND DPR-62 DOCKET NOS. 50-325 AND 50-324 RESPONSE TO IE BULLETIN 80-17, SUPPLEMENT NO. 1
Dear Mr. O'Reilly:
In response to your letter of July 18, 1980, transmitting IE Bulletin 80-17, Supplement No.1, Carolina Power & Light Company submits the following information for the Brunswick Steam Electric Plant (BSEP):
Item #1 Al.
CP&L has conducted an analysis of the adequacy of the "as-built" BSEP SDV System and associated vent and drain systems. To date no design deficiencies have been noted which would preclude these systems from performing their required functions. Also enclosed are the latest available verified as-built isometric drawings of the SDV and associated vent and drain systems for Unit No. 1.
Isometric drawings for Unit No. 2 sill be sent upon completion of the detailed as-built inspection which is in progress.
BSEP is currently reworking pipe hangers and anchor bolts on the CRD Systems on both units and thus has delayed the final isometrics which will reflect this work.
After this work is complete, the remaining information will be forwarded to you.
A2.
Existing Emergency Instruction 2 (EI-2), Loss of Control Rod Shutdown Capability provides the operator with clear instructions fbr initiating l
Standby Liquid Control System (SLCS) if the control rod system is unable to shutdown or maintain the reactor in a suberitical condition or if the nuclear, l
engineer predicts a restart. Prior supervisory approval is not required to I
initiate the SLCS.
A3.
A new operations periodic test has been implemented to monitor for the presence of wLter in the scram discharge volume and scram instrument volume.
This test is conducted on a daily basis and prior to startup following a scram.
This test involves opening a low point drain to which a water manometer has been attached.
Should water be found at this location during this test or at other times as denoted by control room annunciators, the operators are directed 8 000020 i OG
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OFFICIAL OO "Y
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Mr. James P. O'Reilly August 7, 1980 by procedure to check the position of the scram discharge isolation test switch and the operability of dhe vent and drain valves.
If it appears that the SDV cannot be maintained drained or sufficient volume retained, action is taken to assure the plant shutdown.
A4.
El-2 has been revised to instruct the operator that the SLCS key is key number nine, located in the Shift Foreman's controlled key cabinet. This cabinet is located in the Control' Room and is readily accessible by the control operator.
AS.
Periodic Test 1.4 (P.T.1.4), developed to detect water in the Scram Discharge Volume (SDV), is currently being performed on a daily basis and will be continued on this periodicity until an acceptable, continuous monitoring method is implemented on the SDV.
We trust tha t this information satisfies the request of IE Bulletin 80-17, Supplement No. 1 Section A.
Very truly yours, l
p B. J. Furr Vice President Nuclear Operations RMP/lth Enclosure cc:
Mr. N. C. Moseley w/o enclosure
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