ML17284A641
| ML17284A641 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 06/01/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML17284A640 | List: |
| References | |
| 50-397-97-13-01, 50-397-97-13-1, EA-97-573, NUDOCS 9806040395 | |
| Download: ML17284A641 (2) | |
Text
NOTICE OF VIOLATION Washington Public Power Supply System Washington Nuclear Project-2 Docket No. 50-397 License No. NPF-21 EA 97-573 During an NRC inspection completed January 12, 1998, violations of NRC requirements were identified. In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, these violations are listed below:
A.
10 CFR 50.59 (a)(1) requires that the holder of a license authorizing operation of a production or utilization facility may make changes in the facility as described in the safety analysis report without prior Commission approval unless the proposed change involves an unreviewed safety question.
10 CFR 50.59(a)(2) requires that a proposed change shall be deemed to involve an unreviewed safety question ifthe probability of occurrence of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased.
FSAR Table 3.2-1 specifies the reactor core isolation cooling system as a Safety Class 1
or 2 system.
FSAR Section 3.2.3.2 defines Safety Class 2 systems as those systems.
that are necessary to accomplish the function of providing emergency core cooling and removing residual heat from the reactor.
FSAR Section 5.4.6.2.3 specifies that the reactor core isolation cooling system is designed as Seismic Category I equipment and Section 5.4.6.2.4 specifies that the system is designed to meet Safety Class 1
requirements.
FSAR Table 7.1-1, "Design and Supply Responsibility of Safety-Related
- Systems," lists the reactor core isolation cooling system as a safety-related system required for safe shutdown.
Contrary to the above, in 1985, without prior Commission approval
~ a change was made to the facility as described in the safety analysis report involving an unreviewed safety question.
The reactor core isolation cooling system, a system required for safe shutdown, was downgraded from safety-related to nonsafety-related which also redesignated the system such that it was no longer Seismic Category I. This change constituted an unreviewed safety question in that it increased the probability of occurrence of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report.
(01013) 10 CFR 50.55a(f) requires inservice tests to verify the operational readiness of pumps and valves, whose function is required for safety, to comply with the requirements set forth in Section XI of the appropriate edition and addenda of the ASME Boiler and Pressure Vessel Code.
Article IWV-1100 of the ASME Code provides the rules and requirements for inservice testing to assess operational readiness of certain ASME Code'Class 1, 2, and 3, valves which are required to perform a specific function in shutting down a reactor to the cold shutdown condition or in mitigating the consequences of an accident.
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