ML19257C620
| ML19257C620 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 01/15/1980 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| References | |
| NUDOCS 8001290504 | |
| Download: ML19257C620 (1) | |
Text
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UNITED STATES y}
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NUCLEAR REGULATORY COMMISSION G J' s E REGION V S
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WALP.UT CREEK, CALIFORNIA 94596 JAN 151980 Docket ilo. 50-312 Sacramento Municipal Utility District P. O. Box 15830 Sacramento, California 95813 Attention: Mr. John J. Mattimoe Assistant General Manager Gent'. nen:
Enclosed is IE Bulletin tio.79-01B which requires action by you with regard to your power reactor facility with an operating license.
Should you have questions regarding this Bulletin or the actions required of you, please contact this office.
Sincerely,
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R. H. Engelken Director
Enclosures:
1.
IE Bulletin '40.79-01B with Enclosures 2.
List of Recently Issue 6 IE Bulletins cc w/o enclosures:
R. J. Rodriguez, SMUD L. G. Schwieger, SMUD 1829 011 8001290
t UtlITED STATES SSINS No.:
6820 NUCLEAR REGULATORY COMMISSION Accessions f!o.:
0FFICE OF INSPECTION AND Ef!FORCEMEllT 7910250528 WASHIf!GTON, D.C.
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u@bk January 14, 1980 IE Bulletin flo.79-01B ENVIRONMENTAL, QUALIFICATION OF CLASS IE EQUIPMENT Description of Circumstances:
IE Buin.n tio. 79-01 required the licensee _ to perfom a detailed review of the environnental qualification of Class IE electrical equipnent to ensure that the equipment will function under (i.e. during and following) postulated accident conditions.
The I;RC staff has completed the initial review of licensees' responses to Bulletin t!o. 79-01.
Based on this review, additional infomation is needed to facilitate completion of the f!RC evaluation of the adequacy of environmental qualification of Class IE electrical equipment in the operating facilities.
In addition to requesting nore detailed information, the scope of this Bulletin is expanded to resolve safety concerns relating to design basis environments and current qualification criteria not addressed in the facilities' FSARS.
These include high energy line breaks (HELB) inside and outside primary containment, aging, and submergence., "GUIDELIfiES FOR EVALUATING ErlVIR0t;MErlTAL QUALIFICATION OF CLASS IE ELECTRICAL EQUIPMENT It! OPERATII'G REACTORS", provides the guidelines and criteria the staff will use in evaluating the adequacy of the licensee's Class IE equipment evaluation in response to this Bulletin.
In general, the reporting problens encountered in the original responses and the additional infomation needed can be grouped into the following areas:
1.
All Class IE electrical equipment required to function under the postulated accident conditions, both inside and outside primary contain-ment, was not included in the responses.
2.
In many cases, the specific infomation requested by the Bulletin for each component of Class IE equipment was not reported.
3.
Different methods and/or formats were used in providing the written evidence of Class IE einctrical equipment qualifications.
Some licensees used the System Analysis Method which proved to be the most effective approach.
This method includes the following infomation:
a.
Identification of the protective plant systems required to function under postulated accident conditions.
The postulated accident conditions are defined as those environmental conditions resulting from both LOCA and/or HELB inside primary containment and HELB outside the primary containment.
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IE Bulletin fio.79-01B January 10, 1980 Page. 2 of 3 b.
Identification of the Class IE electrical equipment item; within each of the systems identified in Iten a, that are required to function under the postulated accident conditions.
c.
The correlation between the environmental data requirements specified in the FSAR and the environmental qualification test data for each Class IE electrical equipment item identified in Item b above.
4.
Additional data not previously addressed in IE Bulletin flo. 79-01 are needed to determine the adequacy of the environmental qualification of Class IE electrical equipnent.
These data address component aging and operability in a submerged condition.
Action To Be Taken By Licensees Of All Povier Reactor Facilities Uith An Operating License (Except those 11 SEP Plants Listed on Enclosure 1) 1.
Provide a " raster list" of all Engineered Safet, Feature Systems (Plant Pro-tection Systens) required to function under postulated accident conditions.
Accident conditions are defined as the LOCA/HELB inside containment, and HELB outside containment.
For each system within (including cables, EPA's terminal blocks, etc.) the master list identify each Class IE electrical equipment item that is required to function und accident conditions.
Pages 1 and 2 of Enclosure 2 are standard format; to be used for the " master list" with typical information included.
Electrical equipment items, which are components of systems listed in Appendix A of Enclosure 4, which are assumed to operate in the FSAR safety analysis and are relied on to mitigate design basis events are considered within the scope of this Bulletia, regardless whether or not they were classified as part of the engineered safety features when the plant was orginally licensed to operate.
The necessity for further up grading of nonsafety-related plant systems will be dependent on the outcome of the licensees and the f!RC reviews subsequent to TMI/2.
2.
For each. lass IE electrical equipment item identified in Item 1, provide written e idence of its environmental qualification to support the capability of the item to function under postulated accident conditions.
For those class IE electrical equipment items not having adequate qualifica-tion data available, identify your plans for determining qualifications of these items and your schedule for completing this action.
Provide this in the format of Enclosure 3.
3.
For equipment identifed in Items 1 and 2 provide service condition profiles (i.e., temperature, pressure, etc., as a function of time).
These data should be provided for design basis accident conditions and qualification tests performed. This data may be provided in profile or tabular fom.
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IE Bulletin No.79-01B January 14, 1980 Page 3 of 3 4.
Evaluate the qualification of your Class IE ele:trical equipment against the guidelines provided in Enclosure 4., "Intefim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment,"
provides supplemental information to be used with these guidelines.
For the equipment identified as having " Outstanding Items" by Enclosure 3, provide a detailed " Equipment Qualification Plan." Include in this plan specific actions which will be taken to determine equipnent qualification and the schedule for completing the actions.
~~ ~
5.
Identify the naximum expected flood level inside the primary containment resulting from postulated accidents.
Specify this flood level by elevation such as the 620 foot elevation.
Provide this infomation in the format of.
6.
Subnit a " Licensee Event Report" (LER) for any Class IE electrical equipment item which has been determined'as not being capable of neeting environmental qualification requirerents for service intended.
Send the LER to the approp-riate NRC Regional. Oft.ce within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of identification.
If plant opera-tion is to continue following identification, provide justification for such operation in the LER.
Provide a detailed written report within 14 days of identification to the appropriate NRC Regional Office.
Those itens which were previously reported to the NRC as not being qualified per IEB-79-01 do not require an LER.
7.
Complete the actions specified by this bulletin in accordance with the following schedule:
(a) Submit a written report required by Items 1, 2, and 3 withO 45 days fron receipt of this Bulletin.
(b) Subnit a written report required by Items 4 and 5 within 90 days from receipt cf this Bulletin.
This information is requested under the provisions of 10 CFP, 50.54(f).
Accordingly, you are requested to provide within the time periods specified in Items 7.a and 7.h above, written statements of the above information, signed under oath or affirmation.
Submit the reports to the Director of the appropriate NRC Regional Office.
Send a copy of your report to the U.S. Nuclear Regulatory Comission, Office of Inspection and Enforcenent, Division of Reactor Ope ations Inspection, Washington, D.C.
20555.
Approved by GAO, B180225 (R0072); clearance expires 7/31/80.
Approval was given under a blanket clearance specifically for identified generic problens.
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