ML20235A699
| ML20235A699 | |
| Person / Time | |
|---|---|
| Site: | Monticello, Brunswick, 05000000 |
| Issue date: | 09/18/1987 |
| From: | Sylvester E Office of Nuclear Reactor Regulation |
| To: | Utley E CAROLINA POWER & LIGHT CO. |
| Shared Package | |
| ML20235A701 | List: |
| References | |
| TAC-59075, TAC-59076, NUDOCS 8709230390 | |
| Download: ML20235A699 (3) | |
Text
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'tg, SEP 181987 Docket. Numbers: 50-325/324 DISTRIBUTION iDocket a J. Partlow NRC &'Cocal PRRs Mr. E. E. Utley PD 21 r/f ACRS (10)
Senior Executive Vice President S. Varga Power Supply and Engineering & Construction G. Lainas Carolina Power & Light Company E. Adensam P. O. Box 1551 P. Anderson Raleigh, North Carolina 27602 J. Hayes E. Sylvester
Dear Mr. Utley:
E. Jordan
SUBJECT:
COMPLIANCE WITH ATWS RULE 10 CFR 50.62 RELATING TO ARI AND RPT SYSTEMS, BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 (TAC NOS. 59075 & 59076)
By letters dated October 10, 1985, April 14, June 18, July 2R and 24, August 24, 1987, you provided an evaluation of the manner in which the Brunswick Steam Electric Plant (BSEP) would comply with the ATWS Rule (10 CFR 50.6?, " Requirements for Reduction of Risk from Anticipated Transients Without Scram (ATWS) Events for Light-Water-Cooled Nuclear Power Plants").
These submittals contained information on the installation of an Alternate Rod Injection System (APsI), the Liquid Control System (SLCS) proposed modification to the existing Standby
, and the adequacy of the BSEP Reactor Coolant Recirculating Pump Trip System (RPT) design relative to the NRC-approved Monticello design. The latter information utilized PRA analyses to demonstrate the adequacy of the BSEP design.
We have completed our evaluation of your submittals on the ARI and the RPT.
The evaluation of the SLCS will be completed at a later date. The ericlosed Safety Evaluation provides the result of our review.
The staff has determined that the ARI system proposed is acceptable in all areas, except that the system is not operable while being tested at power.
The system should be modified so that surveillance testing can be performed while at power and that such testing does not prevent the ARI system from responding to either a manual or an automatic ARI initiation signal.
8709230390 B70910' l
PDR ADOCK 05000324 P
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= CP&L's proposed design to upgrade the RPT sensor hardware is acceptable, but the original RPT design employing a single trip coil in each breaker is not acceptable. The BSEP design should be upgraded to provide redundant trip coils, i.e., the Monticello approved design, or two breakers with single trip coils to trip each recirculation pump.
We therefore request that you provide your commitment and schedule for upgrading the ARI and RPT within 60 days of receipt of this letter.
Sincerely,
/5 Ernest D. Sylvester, Project Manager Project Directorate 11-1 Division of Reactor Projects - I/II
Enclosures:
As stated cc: w/ Enclosure See next page 1
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Mr. E. E. Utley.
Brunswick Steam Electric Plant
-Carolina Power.& Light Company Units 1 and 2 i
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cc:
Mr. P. W. Howe Mr. C. R. Dietz Vice President Plant General Manager Brunswick Nuclear Project Brunswick Nuclear Project Box 10429 Box 10429'
'i Southport, North Carolina '28461 Southport, North Carolina 28461 Thomas A. Baxter, Esquire Mr. H. A. Cole Shaw, Pittman, Potts & Trowbridge Special Deputy Attorney General 2300 N Street, N. W.
State of North Carolina Washington, D. C.
20037 Post Office Box 629
,h Raleigh, North Carolina 27602 Mr. Mark S. Calvert Associate General Counsel Mr. Robert P. Gruber Carolina Power & Light Company Executive Director
' Post Office' Box 1551 Public Staff - NCUC Raleigh, North Carolina 27602 Post Office Box 29520 Raleigh,' North Carolina 27626-0520 Mr. Christopher Chappell, Chairman Board of Commissioners
-Post Office Box 249
' Bolivia, North Carolina 28422 Mrs. Chrys Baggett State Clearinghouse Budget and Management 116 West Jones Street Raleigh, North Carolina 27603 Resident Inspector U. S. Nuclear Regulatory Commission Star Route 1 Post Office Box 208 Southport, North Carolina 28461 Regional Administrator, Region II U. S. Nuclear Regulatory' Commission l
101 Marietta Street, Suite 2900 Atlanta, Georgia 30303 Mr. Dayne H. Brown, Chief
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Radiation Protection Branch J
Division of Facility Services N. C. Department of Human Resources L
701 Barbour Drive
'Raleigh, North Carolina 27603-2008 I
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