ML19290C931
| ML19290C931 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 02/01/1980 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | Jackie Jones CAROLINA POWER & LIGHT CO. |
| References | |
| NUDOCS 8002150089 | |
| Download: ML19290C931 (4) | |
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FEBRUt,RY l 1990 Docket Nos. 50-325 and 50-324 Mr. J. A. Jones Executive Vice President Carolina Power & Light Company 336 Fayetteville Street Raleigh, North Carolina 27602
Dear Mr. Jones:
During our continuing review of your responses to our November 29, 1978 letter concerning Containment Purging, we have identified the enclosed additional information as being required in order that we can complete our evaluation of the electrical override / bypass circuitry aspects. The enclosed request for additional information is in addition to that.provided in our August 29, 1979 letter and should be responded to within 60 days of your receipt of this letter.
In addition, we are forwarding a copy of our Electrical Review Criteria for your use in developing your response to our concerns.
Thank you for your cooperation.
Sincerely, N'
M" hom
/ Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Enclosures:
1.
Request for Additional Information 2.
Electrical Review Criteria cc w/ enclosures:
see next page 8 0 0 215 0 0f59
Mr. J. A. Jones Carolina Power & Light Company cc:
Richard E. Jones, Esquire Carolina Power & Light Company 336 Fayetteville Street Raleigh, North Carolina 27502 George F. Trowbridge, Esmiire Shaw, Pittman, Potts & Trowbridge 1800 M Street, N. W.
Washington, D. C.
20036 John J. Burney, Jr., Esquire Burney, Burney, Sperry & Barefoot 110 North Fifth Avenue Wilmington, North Carolina 28401 Resident Inspector V. S. Nuclear Regulatory Commission P. O. Box 1057 Southport, North Caro'ina 28461 Southport - Brunswick County Library 109 W. Moore Street Southport, North Carolina 28461 Mr. Fred Tollison Plant Manager P. O. Box 458 Southport, North Carclina 28461 1
ENCLOSURE 1 R_EOUEST FOR ADDITIONAL INFORMATION FOR CONTAINMENT PURGE SYSTEM AND CONTAINMENT VENTING SYSTEM FOR BRUNSWICK STEfM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET N05. 50-325 AND 50-324 1.
We believe that the instrumentation and controls used for the protection of public health and safety should satisfy the requirements for reactor protection systems. Accordingly, please provide a modified design or,
analysis for the radiation monitors that initiate containment isolation to justify the present design.
2.
Provide the electrical schematics for the CAC isolation valves.
3.
Describe any differences between the CAC actuation circuits and other safety actuation circuits.
4.
Your letter of January 19, 1979 states that there are no manual overrides "except for those controlled by plant procedures".
Identify these overrides and their eJfect on safety actuation signals.
5.
Describe, in greater detail than in your Licensee E0ent Report 2-79-023 of June 22, 1979, your interim fix.
Provide sketches as needed to clarify.
Also provide a description and sketches of your permanent modification, showing where changes have been made and addressing the following topics:
a.
single failure b.
signal overrides that do not override any other signals c.
switch characteristics and prevention of accidental actuation of overrides d.
annunciation of overridden status at the system level e.
prevention of automatic reopening of the isolation valves.
Et; CLOSURE 2 ELECTRICAL REVIEW CPITERIA The primary intent of this evaluation is to determine if the following t;RC staff criteria are met for the safety signals to all Durge and ventilation isolation valves:
(1) Criterion no.1 - The overriding" of one tyoe of safety actuation signal (e.g., radiation) must rot cause the blocking of any other type of safety actuation signal (e.g., pressure) to the isolction valves.
(2) Criterion no. 2 - Sufficient physical features (e.g., key lock switches) are provided to facilitate adecuate administrative controls.
(3) Criterion no. 3 - The systein-level annunciation of the overridden status is provided for every safety system impacted when any override is active.
Incidental to this review, the following additional NRC staff design criteria were used in the evaluation:
(1) Criterion no. 4 - Diverse signals should be provided to initiate isola-tion of the containment ventilation system.
Specifically, containment high radiation, safety injection actuation, and containment high pressure should automatically initiate CVI. This is in conformance with Branch Technical Position 6.4 of Section 6.2,4 of the Standard Review Plan.
(2) Criterion no. 5 - The instrumentation and control systems orovided to initiate CVI should be designed and qualified as safety-grade equipment.
(3) Criterior, no. 6 - The overriding or resetting
- of the isolation actuation signal should not cause the automatic reopening of any isolation / purge valve.
- Tne following definition is given f,r clarity of use in this evaluation:
Override: The signal is still pret a.it, and it is blocked in order to perform a function cont. 'ry to the signal.
Reset:
The signal has come and r:
.0, and the circuit is Leing cleared to return it to the nonnal condition.