ML17055E580
| ML17055E580 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/17/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17055E579 | List: |
| References | |
| GL-83-28, NUDOCS 8903230419 | |
| Download: ML17055E580 (8) | |
Text
ENCLOSURE 1
SAFETY EVALUATION REPORT GENERIC LETTER 83-28 ITEN 2.1 PARTS 1 AND 2 NINE NILE POINT UNIT 1 DOCKET NO. 50-220
1.0 INTRODUCTION
On February 25, 1983, both of the scram circuit breakers at Unit 1 of the Salem Nuclear Power Plant failed to open upon an automatic reactor trip signal from the reactor protection system.
This incident was terminated manually by the operator about 30 seconds after the initiation of the automatic trip signal.
The failure of the circuit breakers was determined to be related to the sticking of the undervoltage trip attachment.
Prior to this incident, on February 22, 1983, at Unit 1 of the Salem Nuclear Power Plant, an automatic trip signal was generated based on steam generator low-low level during plant startup.
In this case, the reactor was tripped manually by the operator almost coincidentally with the automatic tr ip.
Following these incidents, on February 28, 1983, the NRC Executive Director for Operations (EDO), directed the staff to investigate and report on the generic implications of these occurrences at Unit 1 of the Salem Nuclear Power Plant.
The result of the staff's inquiry'into the generic implications of the Salem, Unit 1 incidents are reported in NUREG-1000, "Generic Implications of the ATWS Events at the Salem Nuclear Power Plant".
As a result of this investigation, the Commission (NRC) requested (by Generic Letter 83-28 dated July 8, 1983) all licensees of operating reactors, applicants for an operating
- license, and holders of construction permits to respond to generic issues raised by the analyses of these two ATMS events.
This report is an evaluation of the responses submitted by Niagara Mohawk Power Corporation, the licensee for Nine ltile Point Unit 1, for Item 2.1 (Parts 1 and 2) of Generic Letter 83-28.
Item 2.1 (Part
- 1) requires the 89032304i9 8903i7
- PDR ADOCK 05000220 P
PGC
licensee to confirm that all reactor trip system components are identified, classified and treated as safety-related as indicated in the following statement:
Licensees and applicants shall confirm that all components whose functioning is required to trip the reactor are identified as safety-related on documents, procedures, and information handling systems used in the plant to control safety-related activities, including maintenance, work orders, and parts replacement.
Item 2. 1 (Part 2) requires the licensee to confirm that an interface has been established with the NSSS vendor or with the vendors of each of the components of the Reactor Trip System which includes:
o periodic communication between the licensee/applicant and the NSSS vendor or the vendors of each of the components of the Reactor Trip
- System, and, o
a system of positive feedback which confirms receipt by the licensee/applicant of transmittals of vendor technical information.
- 2. 0 EVALUATION The licensee for Nine Mile Point Unit 1 responded to Generic Letter 83-28, Item 2.1 (Parts 1 and 2) in their submittals dated November 8, 1983, November 30, 1984 and December 31, 1985.
The licensee reviewed the equipment classification list (g-List) used at the Nine Mile Point Unit 1.
The review included verification that components in the Reactor Protection System (RPS) are classified as safety related except for the RPS Motor Generator Sets.
The RPS Motor Generator Sets are currently classified as non-safety related and remaining Reactor Protection System components are protected from malfunction by electrical protection assemblies that are classified safety related.
The present classification list ((}-List) delineates the applicable quality
A
requirements on a system basis, with updates for individual components.
The licensee started a project to convert the g-List to a component level list.
This project will provide a clea~ definition to those structures and components, subject to the requirements of the licensee's guality Assurance program and consistent with General Electric's criteria and the Nine Mile Point Unit I licensing basis.
Administrative controls consisting of documents, procedures and information handling systems are used.in the station to control safety-related activities including maintenance, work requests, parts replacements, and modifications.
Nine Mile Point Unit 1 has an ongoing program to ensure that vendor information is complete, current and controlled throughout the life of the plant, and appropriately referenced in procedures.
This program is conducted in three parts.
The first part is the Operations Assessment
- Program, which receives, reviews and acts on applicable information from the reactor trip system supplier.
The information consists of General Electric Service Information Letters (SILs),
Service Advice Letters, Technical Information Letters (TILs) and Product Experience Reports (PERs).
Together with the licensee's current participation in the General Electric Operations Engineers
- Program, an acceptable level of communication, feedback and equipment performance improvement is achieved.
The second part of the program is the Administrative Control of Technical Manuals.
Nine Mile Point Unit 1 uses a "controlled copy" program to assure that the technical manuals available for use are the current revision.
The licensee completed a program for periodic audit of the controlled copies.
The third part of the program is the periodic review of maintenance procedures which includes a check to assure that the guidance of the "controlled copy" technical manual is referenced or incorporated in the procedure.
- 3. 0 CONCLUSION Based on the review of these responses, we find that a program exists for identifying, classifying, and treating components (that are required for performance of the reactor trip function), and that a vendor interface program exists with the NSSS vendor for components that are required for the successful performance of the reactor trip function.
These programs meet the requirement of Item 2.1, Parts 1 and 2 of Generic Letter 83-28, and are, therefore, acceptable.
4.0 REFERENCES
1.
NRC Letter, D. G. Eisenhut to all Licensee of Operating Reactors, Applicants for Operating Licenses, and Holders of Construction Permits, "Required Actions Based on Generic Implications of Salem ATWS Events (Generic Letter 83-28)," July 8, 1983.
2.
Letter T. E. Lempges, Niagara Mohawk Power Corp, to D. B. Vassallo,
- NRC, November 8, 1983.
3.
Letter T. E.
- Lempges, Niagara Mohawk Power Corp, to D. B. Yassallo,
- NRC, November 30, 1984.
4.
Letter C. V. Mangan, Niagara Mohawk Power Corp. to J. A. Zwolinski, NRC, December 31, 1985.
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