ML15238A784
| ML15238A784 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/11/1983 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML15238A783 | List: |
| References | |
| CON-NRC-03-79-118, CON-NRC-3-79-118 NUDOCS 8304140481 | |
| Download: ML15238A784 (5) | |
Text
SAFETY EVALUATION REPORT BY THE OFFICE OF NUCLEAR REACTOR REGULATION ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT OCONEE NUCLEAR STATION, UNITS NO. 1, 2:AND 3 DUKE POWER COMPANY DOCKETS NOS. 50-269, 50-270 AND 50-287 INTRODUCTION General Design Criteria 1 and 4 specify that safety-related electrical equipment in nuclear facilities must be capable of performing its safety related function under environmental conditions associated with all normal, abnormal, and accident plant operation. In order to ensure compliance with the criteria, the NRC staff required all licensees of operating reactors to submit a re-evaluation of the qualification of safety-related.electrical equipment which may be exposed to a harsh environment.
BACKGROUND On February 8, 1979, the NRC Office of Inspection and Enforcement (IE) issued to all licensees of operating plants (except those included in the systematic evaluation program (SEP)) IE Bulletin (IEB) 79-01, "Environ mental Qualification of Class IE Equipment."
This Bulletin, together with IE Circular 78-08 (issued on May 31, 1978), required the licensees to perform reviews to assess the adequacy of their environmental qualifica tion programs.
On January 14, 1980, NRC issued IE Bulletin 79-01B which included the DOR guidelines and NUREG-0588 as attachments 4 and 5, respectively.
Subsequently, on May 23, 1980, Commission Memorandum and Order CLI-80-21 8304140481 830411 PDR ADOCK 05000269 P
-2 was issued and stated the DOR guidelines and portions of NUREG-0588 form.
the requirements that licensees must meet regarding environmental qualification of safety-related electrical equipment in order to satisfy those aspects of 10 CFR 50, Appendix A, General Design Criterion (GDC) 4.
Supplements to IEB 79-018 were issued for further clarification and definition of the staff's needs.
These supplements were issued on February 29, September 30, and October 24, 1980.
In addition, the staff issued orders dated August 29, 1980 (amended in September 1980) and October 24, 1980 to all licensees. The August -order required that the licensees provide a report, by November 1, 1980, docu-_
menting the qualification of safety-related electrical equipment. The October order required the establishment of a central file location for the maintenance of all equipment qualification records. The central file was mandated to be established by December 1, 1980. The staff subsequently issued Safety Evaluation Reports (SERs) on enviromental qualification of safety-related electrical equipment to licensees of all operating plants in mid-1981. These SERs directed licensees to "either provide documentation of the missing qualification information which demonstrates that safety-related equipment meets the DOR Guide lines or NUREG-0588 requirements or commit to a corrective action (re-qualification, replacement (etc.))."
Licensees were required to respond to NRC within 90 days of receipt of the SER. In response to the staff SER issued in 1981, the licensee submitted additional information regarding the qualification of safety-related electrical equipment..
-3 EVALUATION The acceptability of the licensee's equipment environmental qualification program was resolved for the Division of Engineering by the Franklin Research Center (FRC) as part Aof the NRR Technical Assistance Program in support of NRC operating reactor licensing actions.
The consultant's reviews are documented in the reports "Review of Licensees' Res6lutions of Outstanding Issues from NRC Equipment Environmental Qualification Safety Evaluation Reports," which are attached.
We have reviewed the evaluation performed by our consultant contained in the enclosed Technical Evaluation Reports (TERs) and concur with its bas~s and findings.
CONCLUSIONS Based on the staff's review of the enclosed Technical Evaluation Reports, the following conclusions are made regarding the qualification of safety-related electrical equipment.
The major qualification deficiencies that have been identified in the enclosed FRC TERs (Tables 4-1, 4-2, 4-3..and 4-4) must be resolved..by the licensee. Items requiring special attention by the licensee are summarized below:
a Submission of information within thirty (30) days for items in NRC categories I.B, II.A,and IV for which justification for continued operation was not previously submitted to NRC or
- FRC,
-4 Resolution of the staff concern regarding the radiation dose inside and outside containment (Section 4.3.3.3 of the FRC TERs).
As...a result of the staff review, we conclude that
- the valves.estimated'by the staff (2 x 107 rads gamma and 3 x 10 8 rads beta based on NUREG-0588, Revision 1) be imposed as estimates of the integrated doses at the centerline of the containment and that all equipment be qualified accordingly.
The staff is continuing to review the licensee's environmental qualification program. If any additional qualification deficiencies were identified during the course of this review, the licensee would be required to reverify the justification for continued operation. The staff will review this infor mation to ensure that continued operation until completion of the licensee's environmental qualification program will not present undue risk to the public health and safety. The licensee must provide the plans for quali fication or replacement of the unqualified equipment and the schedule for accomplishing its proposed correction action in accordance with 10 CFR 50.49.
PROPRIETARY REVIEW Enclosed in the FRC Technical Evaluation Reports (TERs) are certain identi fied pages on which the information is claimed to be proprietary.
During the preparation of the enclosed TERs, FRC used test reports and other documents supplied by the licensee that included material claimed to be proprietary. NRC is now preparing to publicly release the FRC
-5 TER and it is incumbent on the agency to seek review of all claimed proprietary material.
As such, the licensee is requested to -review the enclosed TERs and notify NRR whether any portions of the identified pages still require proprietary protection. If so, the licensee must clearly identify this information and the specific rationale and justi fication for the protection from public disclosure, detailed in a written response. The level of specificity necessary for such continued protection should be consistent with the criteria enumerated in 10 CFR 2.790(b) of the Commission's regulations.