ML20207T009
| ML20207T009 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/13/1987 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| References | |
| GL-83-28, NUDOCS 8703230051 | |
| Download: ML20207T009 (5) | |
Text
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a-March 13, 1987
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Docket No. 50-289 i
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- Mr. Henry D. Hukill, President
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and Director - TMI-1 E
GPU Nuclear Corporation P. O. Box 480 Middletown, Pennsylvania 27057
Dear Mr. Hukill:
SUBJECT:
Request For Additional Information Related to i
Items 2.1 and 2.2 of Generic Letter 83-28 (Salem ATWS Responses)
GPU Nuclear has responded to Items 2.1 (Parts 1 and 2) and 2.2 (Part 1) of Generic letter 83-28 by letters dated November 8, 1983 and August 5, 1985.
However, NRC Staff review of these responses indicates additional information, as described in the enclosed request for additional information (RA1), is
.necessary to complete our review. You are requested to have your staff coordinate a schedule for responding to the enclosure with your assigned Project Manager, Mr. Thierry Ross (301-492-8324).
The reporting 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, 6l$9 - Oyp John F. Stolz, Director PWR Project Directorate #6 Division:of PWR Licensing-B
Enclosure:
Request for Additional Information cc w/ enclosure:
See next page Distribution:
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'O Mr._ Henry D.-Hukill Three Mile Island Nuclear Station.
- GPU Nuclear Corporation Unit No. 1 CC:
Mr. R. J. Toole Mr. Richard Conte 0&M Director,-TMI-I Senior Resident Inspector (TMI-1)
GPU huclear Corporation U.S.N.R.C.
Middletown, Pennsylvania 17057 P.O. Box 311 Middletown, Pennsylvania 17057 Richard J. McGoey_
Manager, PWP Licensino Pegional Administrator, Pegion I GPU Nuclear Corporation U.S. Nuclear Regulatory Commission 100 Interpace Parkway 631 Park Avenue Parsippany, New Jersey 70754 King of Prussia, Pennsylvania 19406 Mr. C. W. Smyth_
Mr. Robert B. Borsum TMI-1 Licensing Manager Babcock & Wilcox GPU Nuclear Corporation Nuclear Power Generation Division P. O. Box 480 Suite 220, 7910 Woodmont Avenue Middletown,-Pennsylvanie 17057 Bethesda, Maryland 20814 Ernest L. Blake, Jr., Esq.
Governor's Office of State Plannico Shaw, Pittman, Pntts & Trowbridce and Development 2300 N Street, N.W.
ATTN: Coordinator, Pennsylvania Washington, D.C.
20037 State Clearinghouse P. O. Box 1323 Sheldon J. Wolfe, Esq., Chairman Harrisburo, Pennsylvania 17120 Atomic Safety and Licensing Poard U.S. Nuclear Regulatory Commission Mr. Larry Hochendoner Washington, D.C.
20555 Dauphin County Commissioner Dauphin County Courthouse Mr. Frederick J. Shon Front and Market Streets Atomic Safety and Licensing Board Harrisburg, Pennsylvania 17101 U.S. Nuclear Pegulatory Commission Vashingten, D.C.
20555 Fr. David D. Maxwell, Chairman Board of Supervisors Dr. Osc6r H. Paris Londonderry Township Atomic Safety and Licensino Board RF0#1 - Geyers Church Road U.S. Nuclear Regulatory Commission Middletown, Pennsylvania 17057 Washington, D.C.
20555 Mr. Thomas M. Gerusky, Director Atomic Safety 8 Licensing Board Panel Pureau of Radiation Protection U.S. Nuclear Pegulatory Commission Pennsylvan16 Department of Washinoton, DC 20555 Environmental Resources P. O. Box 2063 Atomic Safety & Licensing Appeal Harrisburg, Pennsylvania 17120 Board Panel (8)
U.S. Nuclear Regulatory Commission Thomas Y. Au, Esq.
Washington, D.C.
20555 Office of Chief Counsel Department of Environmental Pesources Docketing and Service Section 505 Executive House Office of the Secretary P. O. Box 2357 U.S. Nuclear Regulatory Commission Harrisburo, Pennsylvania 17120 Washington, D.C.
20555 Ms. Louise Bradford TMIA 1011 Green Street Harrisburg, Pennsylvania 17102
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. Rruce W. Churchill,':Esq.,
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- s. 4 Three File Island Unit-1 Reovest for Additional-Information Related To Items ?.1-(Parts 3 and ?) and ?.? (Part 1) of Gereric Letter 82-78 A.
Item ?.1 (Part li Equipment Classification (Peactor Trip System Components)
Item P.1 (Part 1) requires applicants to confirr that all components wbese
. function is required to trip the reactor are identified es safety-related on documents, prncedures. and information handling systems used in the plant to control safety-related activities,' including naintenance, work orders, and parts replacement.
The licensee's sutanittals stated that the reactor trip system components fall within the scope of systems identified as "important-to-safety" which includes the reactor protection systen and the trip portion of the control rod drive system. Furthermore, the licensee stated that a review of a variety of documents such as plant surveillance procedures, maintenance procedures end work requests associated with reactor trip components indicates that a quality classificetion of important-to-safety or safety-related is identifieu.on each document.
Based on the licensee's submittals, the NPC staff detennines that all components to trip the reactor have not been identified as safety-related.
The licensee is requested to provide a discussion of how the licensee's program is equivalent to the staff position or specifically describe how their procran deviates from the staff position and include a justification for each deviation.
B.
Item ?.1 (Part ?) Vendor Interface Program and Feedback System u
The licensee should describe their interface program with B&W, as well as a feedback system, which addresses how this program accomplishes the followino:
1) applies to all safety-related Reactor Trip System components;
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ensures receipt of vendor Equipment Technical Informaticn l
(ETI) is acknowledged or otherwise verified; 3) ensures the vendor is contacted on a periodic basis to to determine that all ETI has been received; 4) includes means to assure FTI is kept current and complete, preferably throuch the use of controlled procedures for adding, deleting or revising this iriformation; l
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_conteins rocedures to review, evaluate, and incorporate
-(relevant parts) ETI into plant procedures and inttructions.
C.
Item 2.2 (Part'I) Equipment ClassiIication (Programs For All
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Safety-Relatec Components)
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(1)
Itsm 7.7.1 - Program The licensee's responses (see item 2.1 Part 1) do not confirm that all safety-related components are designated as safety-related on plant documents such as procedures, system descriptions, test and maintenance instructions, operating procedures, and in information handling systems so person'nel performing activities that affect such safety-related components are aware they are working on safety-related components and are guided by safety-related procedures and constraints.
The licensee is requested to provide a discussion of how their program is equivalent to the staff's position or describe how their program deviates from the staff position and include a,iustification for each deviation.
(?) Item ?.2.1 - Criteria For Identifyino Components-The licensee's response does not state whether the results of the study of the present classification program resulted in modifications to the equipment classification system.
The licensee needs to state whether review of the pouipment cl6ssification prooram has resulted in modifications to the program.
If so, the modifications should be described.
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