ML19350E910
| ML19350E910 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 06/08/1981 |
| From: | Zwetzig G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19350E906 | List: |
| References | |
| 50-312-81-15, NUDOCS 8106230644 | |
| Download: ML19350E910 (2) | |
Text
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O APPENDIX A NOTICE OF VIOLATION Sacramento Municipal Utility District Docket No. 50-312 As 'a result of the inspection conducted on April 1 - 30, 1981, and in accordance with tha Interim Enforcement Policy, 45 FR 66754 (October 7,1980), the following violation,sas identified.
10CFR50.55a(g)(1) states,inpart,"Foraboilingorpressurizedwater-cooled nuclear power facility whose construction permit was issued prior to January 1,'1971, components...shall meet the requirements of Paragraphs (g)
(4) and (g)(5) of this section to the extent practical.'.'
(Note: The construction permit for Rancho Seco was issued on October 11,1968).
10 CFR 50.55a(g)(4) states, in part, "Throughout the service life of a boiling or pressurized water-cooled nuclear power facility, components which are classified as ASME Code Class 1, Class 2, and Class 3, shall meet the requirements... set forth in section XI of (applicable) editions of the ASME Boiler and Pressure Vessel Code..."
By letter dated May 30, 1978, the Commission issued Amendment No. 20 to the facility license, making the above provisions effective October 18, 1979.
By letter dated October 17, 1979, the NRC issued a letter stat ng, in part:
"During the period between the date that the requirements of 10 CFR 50.55a(g) become effective for your facility and the date we complete our detailed review of your submittal you must comply with both your existing Technical Specifications and your proposed inservice inspection and testing program.
In the event conflicting requirements crise for some components, you must comply with the more restrictive requirements (e.g., shorter inspection intervals, increased number of parameters measured)..."
The licensee's proposed inservice inspection and testing prograin is described in his letters to the NRC dated December 24, 1979, and April 17 and May 30, 1980. ~his program defines the components that are to be tested, the measurenents that are to be made and the relief that has been requested from ce tain requirements of ASME Section XI. Among the pumps to be tested are the High Pressure Injection and Makeup Pumps. One of the parameters to be measured is bearing temperature. No relief was requested from this requirement.
ASME Section XI, Subsection IWP-3500(b) states:
"When measurement of bearing temperature is required, each pump shall be run until the bearing temperatures (IWP-4310) stabilize, and then the quantities specified shall be measured or cbserved and recorded. A bearing temperature shall be considered stable when three successive readings taken at 10 min intervals do not vary by more than 3%."
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, ASME Section XI, Subsection IWP-1100 states in part, "This Subsection provides the rules and requirements for inservice testing of Class 1, 2 and 3... pumps that are... required to perform a specific function in shutting down a reactor or in mitigating the consequences ot an accident and are provided with an emergency power source..."
Contrary to the above, the licensee's approved procedures for testing these pumps (SP 203.02A/B/C, Quarterly HPI System Surveillances) do not provide for achieving stabilized bearing temperatures.
Instead, the procedur s allos operation for as little as 15 minutes and require only one measure-i ment of bearing temperature.
In addition, the procedure is not conducted with only the safety-related lube oil cooling water supply in operation.
_(system supplied with emergency power). Accordingly, the procedure does not measure the capability of the pumps to operate following an accident which also includes a loss of offsite electrical power.
A review cf'the results of the surveillances performed between October 18, 1979, Land April 3,1981, by the Resident Inspector indicate that the above procedures were conducted as written and no supplemental measurements were recorded indicating achievement of stabilized bearing temperatures or capability to operate satisfactorily with only the safety-related lube oil cooler in operation.
As a result of the above, a degraded condition of the High Pressure Injection and Makeup pumps safety-related tube oil coolers was not detected by the surveillance procedures.
(Supplement 1).
This is a Severity Level IV violat 3
Pursuant to the provisions of 10 CFR 2.201 the Sacramento Municipal Utility District is required to submit to this office within thirty days of the date of this Notice, a written statement or explanation in reply, including:
(1) the corrective steps which have been taken and the results achieved; (2) corrective steps which will be taken to avoid further items of noncom-pliance; and (3) the date when full compliance will be achieved. Under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under oath or affirmation. Consideration may be given to extending your response time for good cause shown.
-H.
June 8. 1981 M
Dated G.QB. bletzigy A& ting Chief Reactor Projects Section #2