ML20206P117
| ML20206P117 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/22/1986 |
| From: | Sylvester E Office of Nuclear Reactor Regulation |
| To: | Utley E CAROLINA POWER & LIGHT CO. |
| References | |
| NUDOCS 8608270101 | |
| Download: ML20206P117 (4) | |
Text
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. August 22, 1986 Docket Nos. S.0-325/324 Mr. E. E. Utley Senior Executive Vice President Power Supply and Engineering & Construction Carolina Power & Light Company Post Office Box 1551 Raleigh, North Carolina 27602
Dear Mr. Utley:
SUBJECT:
REACTOR COOLANT SYSTEM LEAK DETECTION INSTRUMENTATION Re:
Erunswick Steam Electric Plant, Units 1 and 2 By letter dated March 17, 1986, you requested a revision to the Technical Specifications (TS) for Brunswick Steam Electric Plant (BSEP), Units 1 and 2.
The proposed revision would delete from the TS tag numbers for reactor coolant system leakage detection instruments that are not part of the safety-related leakage detection system.
In our review of this amendment application we find that we need the information requested in the Enclosu're to complete our review. Please respond to this request within 45 days of receipt of this letter.
i Th2 renorting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, Ori&' ' ' hr Ernest D. Sylvester, Project Manager BWR Project Directorate #2 Division of BWR Licensing
Enclosure:
As stated cc w/ enclosure:
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r Nr. E. E. Utley Brunswick St'eam Electric Plant Carolina Pcwer & Light Company Units 1 and 2 CC:
Mr. F. W. Howe Mr. C. R. Dietz Vice President Plant General Manager Brunswick Nuclear Project Brunswick Nuclear Project Box 10429 Box 10429 Southport, North Carolina 28461 Southport, North Carolina 28461 Thomas A. Baxter, Esquire Mr. H. A. Cole Shaw, Pittman, Potts & Trowbridge Special Deputy Attorney General 1800 M Street, N. W.
State of North Carolina Washington, D. C.
20036 P.O. Box 629 Raleigh, North Carolina 27602 Mr. D. E. Hollar Associate General Counsel Mr. Robert P. Gruber Carolina Power & Light Company Executive Director Post Office Box 1551 Public Staff - NCUC s
Raleigh, North Carolina 27602 P.O. 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 Connission Star Route 1 Post Office Box 208 Southport, North Carolina 28461 Regional Administrator, Region II U. S. Nuclear Regulatory Connission 101 Marietta Street, Suite 2900 Atlanta, Georgia 30303 Dayne H. Brown, Chief Radiation Protection Branch Division of Facility Services N. C. Department of Human Resources 701 Barbour Drive Raleigh, North Carolina 27603-2008
b REQUEST FOR ADDITIONAL INFORMATION RELATING TO REACTOR PRESSURE B3UNDARY LEAKAGE DETECTION SYSTEM CAROLINA POWER AND LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT UNITS 1 AND 2 DOCKET NOS. 50-324 AND 50-325
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BACKGROUND i
i The Reactor Coolant Pressure Boundary (RCPB) Leakage Detection System is to 1
j detect and, to the extent practical, identify the source of leakage of reactor coolant. The system is designed to the requirements of General Design Criterion 30, " Quality of Reactor Coolant Boundary," and with the guidelines 4
of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems," and the guidelines of Standard Review Plan (NUREG-0800) Section 5.2.5, " Reactor Coolant Pressure Boundary Leakage Detection." These documents
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provide the guidance for both safety-related and nonsafety-related leakage l
detection syste'rns. While some of the systems identified are not
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safety-related, thej are nonetheless important to safety, and as such provide a measure of increased assurance that reactor coolant leakage from the RCPB j
will be detected in a timely manner.
In conformance with the guidelines of the Regulatory Guide 1.45, only one RCPB ieakage detection system is required l
to be safety-related, i.e., seismic Category I and Class 1E powered. The other required systems referenced in the Regulatory Guide are important to safety.
I j-In a submittal dated March 17, 1986, the licensee has requested the elimination of the square root converters (tag numbers G16-FY-K600 and G16-FY-K602) from the plant Technical Specifications on the basis that they I
are not a part of the safety-related RCPB leallage detection system. These i
square root converters provide input to a flow recorder and are associated with I
the primary dbstainment sump flow integrating system referenced in Technical Specification.4.4.3.1.b and the drywell and equipment drain sump flow system l
referenced in Technical Specification 4.4.3.2.a.
In order to complete our j
review of the proposed change, we need the information below.
l
o, 2-QUESTION 1.
Provide a discussion which demonsteates that thc square root converters and the associated recorders are not important to safety; i.e., that the control room operators would not use the information provided by these components in their assessment of the leakage from the RCPB.
2.
Provide a figure / drawing which shows the physical relationship (i.e.,
relative location) of this flow recorder to the other RCPB leakage detection system instrumentation identified by Regulatory Guide 1.45.
3.
Provide a discussion of the plant's design features with respect to compliance with the guidelines of Regulatory Guide 1.45 without reliance on these square-root converters and the related flow recorders; O
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