ML17285A266
| ML17285A266 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 02/16/1989 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML17285A265 | List: |
| References | |
| GL-83-28, NUDOCS 8902270470 | |
| Download: ML17285A266 (5) | |
Text
ENCLOSURE 1
SAFETY EVALUATION REPORT GENERIC LETTER 83-28 ITEN 2. 1 (PART 2)
WASHINGTON NUCLEAR PLANT NO.
2 DOCKET NO.
397
- 1. 0 INTRODUCTION P
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 start-up.
In this case, the reactor was tripped manually by the operator almost coincidentally with the automatic trip.
Following these incidents, on February 28, 1983, the NRC Executive Director for Operations (EDO), directed the staff to investigate the report on the generic implications of these occurrences at Unit 1 of the Salem Nuclear Power Plant.
The results of the staff's inquiry into the generic implications of these events 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 8902270470 8902ib PDR ADOCK 05000397 P
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 ATWS events.
This report is an evaluation of the response submitted by Washington Public Power Supply System, the licensee for the WNP-2, for Item 2.1 (Part 2) of Generic Letter 83-28.
The actual documents
- reviewed, as part of this evaluation, are listed in the r eferences at the end of this report.
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 WNP-2 provided responses to Generic Letter 83-28, Item 2.1 (Part 2) in submittals dated November 18, 1983 and tray 17, 1985.
The licensee stated that he has established, implemented and is maintaining a Contractor/Vendor Information (CVI) file system to insure that vendor information received by WNP-2 for all safety-related equipment including the reactor trip components is controlled and available for use throughout the life of the plant.
The CVI file was created initially during the construction/procurement phase of the plant and is a file which is indexed on equipment part numbers controlled in a computerized equipment list, known as the WNP-2 Master Equipment List (MEL).
MEL provides direct reference to a CVI file item which contains pertinent engineer-ing test, or maintenance information that was obtained during procurement or construction.
The licensee has extensively reviewed the CVI file to ensure the technical information received from the vendors is accurate with regard to the WNP-2 specific installation.
As a result of equipment qualification inquiries and data collection coupled with spare parts and corrective maintenance contact with vendors, virtually all safety-related equipment including the reactor trip components has the latest documentation and updates available.
Each update has been reviewed and screened for WNP-2 applicability before insertion into the CVI system.
3.0 CONCLUSION
Based on our review of these responses, we find the licensee's statements confirm that a vendor interface program exists with the NSSS vendor for components that are required for performance of the reactor trip function.
This program meets the requirements of Item 2.1 (Part 2) of Generic Letter 83-28, and is, therefore, acceptable.
4.0 REFERENCES
1.
NRC Letter, D.
G. Eisenhut to all Licensees 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, G.
C. Sorensen, Washington Public Power Supply System to A. Schwencer, NRC, November 18, 1983.
3.
- Letter, G.
C. Sorensen, Washington Public Power Supply System to W. R. Butler, NRC, Hay 17, 1985.
Principal Reviewer:
S.
Rhow, SICB
4
~ly r
II
'I