ML20206D186
| ML20206D186 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 04/06/1987 |
| From: | Tiernan J BALTIMORE GAS & ELECTRIC CO. |
| To: | Mcneil S Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, NUDOCS 8704130267 | |
| Download: ML20206D186 (4) | |
Text
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BALTIMORE GAS AND ELECTRIC CHARLES CENTER P. O. BOX 1475 BALTIMORE, MARYLAND 21203 JOSEPH A.TIERNAN vict PREslOENT NUCLLAR ENERGY April 6,1987 U. S. Nuclear Regulatory Commission Office of Muclear Reactor Regulation Washington, DC 20555 ATTENTION:
Mr. Scott Alexander McNeil, Project Manager PWR Project Directorate #8 Division of PWR Licensing-B SUB3ECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Request for Additional Information Concerning BG&E Responses to Generic Letter 83-28
REFERENCES:
(a)
Letter from Mr. S. A. McNeil (NRC), to Mr. 3. A. Tiernan (BG&E),
dated February 17,1987, same subject (b)
Letter from Mr. A. E. Lundvall, Jr. (BG&E), to Mr. D. G. Eisenhut (NRC), dated November 5, 1983, " Required Actions Based on Generic Implications of Salem ATWS" Gentlemen:
This is in response to Reference (a). Enclosure 1 provides the additional information you requested regarding items 2.1.2 and 2.2.1 of Generic Letter 83-28, " Required Actions Based on Generic Implications of Salem ATWS Events."
Should you have further questions regarding this reply, we will be pleased to discuss them with you.
Very truly yours, 49/424 -
JAT/SRC/ dim Enclosure Q
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I 8704130267 870406 g
a.
Mr. Scott A. McNeil April 6,1987-
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cc:
D."A. Brune, Esquire
- 3. E. Silberg, Esquire.
T. E. Murley, NRC A. C. Thadani, NRC T. Foley/D. A. Trimble, NRC 6
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ENCLOSURE 1 Item 2.1.2 NRC Request Please describe the method of positive feedback (e.g., return receipts) BG&E utilizes to acknowledge to Combustion Engineering (C-E) the BG&E receipt of the C-E Availability Data. Program Infobulletins which contain technical information.
BG&E Response C-E ADP. Infobulletins are distributed by C-E to several BG&E supervisors on-site. As of November 30,- 1986, the Principal Engineer - Licensing.& Operational Safety has been designated to receive in.the future a copy with an attached return receipt. Previously, other appropriate supervisors signed for receipt of the Infobulletins. ' He will sign this receipt and return - the form to the C-E office responsible for distributing the Infobulletins. This acknowledges to C-E the receipt of the information..
The C-E Quarterly Reports to BG&E list allInfobulletins distributed during the quarter.
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This could potentially alert the appropriate supervisor of any information not received or lost in routing.
Item 2.2.1 NRC Request 1.
Are all safety-related components contained on the Q-List?
2.
Are all safety-related components designated as safety-related on plant riocuments such as procedures, system descriptions, test and maintenance instructions, operating procedures, and in information handling systems? This is necessary so personnel performing activities -
affecting safety-related components are aware that they are working on safety-related components and will be guided by safety-related procedures and constraints.
3.
Please confirm whether the information handling system consists of a single, concise, unambiguous listing of all safety-related components and parts.-
BG&E Response 1.
All safety-related components are contained in the Q-List. The safety-related components are defined as those instruments and equipment necessary to ensure:
a) The integrity of the reactor coolant system pressure boundary, I
F XNCLOSURE 1 b) The capability to shutdown the reactor and maintain it in a safe condition, c) The capability.to prevent or mitigate the consequences of an accident which -
could result in potential off-site exposures.to individuals in excess of exposures specified in 10 CFR100, or d) Other items specified by the Nuclear Engineering Services Department.
In Reference (b), item 1.c above referred to 10 CFR20. When safety-related components were first defined for our Q-List,10 CFR 20 was the only codified guidance in existence providing exposure level limits. Then 10 CFR 100 was established, and a more appropri-ate guidance became available to support our definition. At that time the Q-List definition was revised. Our earlier submittal to the NRC for Generic Letter 83-28 reflected the original definition. This response supersedes item I in Reference (b).
2.
The control of safety-related activities is provided by Quality Assurance Procedures. These in turn are implemented by specific departmental procedures.
In all cases these procedures control safety-related systems, structures, equipment, components, materials or services as specified in the Q-List. Specific orocedures and their applicability to various elements of the Calvert Cliffs Quality Assurance Program were described in Reference (b).
This description discussed those documents designating safety-related activities.
3.
The Q-List provides the source of information establishing the scope of safety-related systems, structures, equipment, components, materials or services. The Q-List includes the following documents:
a) Red-Lined Piping and Instrumentation diagrams, and b) Computerized list of safety-related systems, equipment and components.
The noted documents provide the source for establishing safety-related systems, equipment and components.
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