ML19290A355
| ML19290A355 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/27/1976 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19290A352 | List: |
| References | |
| NUDOCS 7911060591 | |
| Download: ML19290A355 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION W ASHINGToN. D.
C.
20555 5
METROPOLITAN EDISON COMPANY g
ha-JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 11 TO FACILITY LICENSE NO. DPR-50 THREE MILE ISLAND NUCLEAR STATION, UNIT 1 DOCKET NO. 50-289 Introduction By letter dated December 23, 1975, Metropolitan Edison Company, Jersey Central Power and Light Company, and Pennsylvania Electric Company proposed changes to the Technical Specifications appended to Facility Operating License No. DPR-50, for the Three Mile Island Nuclear Station, Unit 1 (TMI-1). The proposed changes involve changes to the administrative controls including changes to the reporting requirements.
Discussion The proposed changes would be administrative in nature and would affect the conduct of operation. The proposed changes are intended to provide uniform license requirements. Areas covered by the proposed uniform specifications include licensee staffing qualifications and management procedures involved with operating the reactor, reporting requirements, abnormal occurrence definition change, and a respiratory protection program.
Members of the facility staff should meet the requirements set forth in Regulatory Guide 1.8, " Personnel Selection and Training" which endorses proposed ANSI N18.1, which was subsequently issued as ANSI N1S.1-1971.
Provisions for independent review of facility operations should be in accord with Regulatory Guide 1.33, " Quality Assurance Program Requirements" which endorses proposed standard ANS 3.2, which was subsequently issued as ANSI 18.7-1972.
In Section 208 of the Energy Reorgani:ation Act of 1974 " abnormal occurrence" is defined as an unscheduled incident or event which the Commission determines is significant from the standpoint of public health or safety.
The term
" abnormal occurrence" is reserved for usage by NRC.
" Reporting of Operating Information - Appendix A Technical Specifications,"
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Revision 4, enut.erates required reports consistent with Section 203.
The prsposed change to required reports identifies the repcrts required of all licenser s.ot already identified by the regulatiens and those uni;uc to this facility. The proposal..ould formalize present reportine and would delete any reports no longer needed by the :GC far assessment of safety related activities.
In addition, a radiatica protection progra:
delineates usa of respiratory equipment in the event person:'el are to te exposed to concentrations in excess of Part 20 concentrations.
Evaluation Consistent with the guidance of Regulatory Guide 1.16, tN nromed reyrt-ing require:..ents cc not iJantify any event as er " abnorm,'. c:currence."
Instead, the proposed change identifies two tyces of " rep artable occurrena.
- One type reportab'c occurrence r: quires prompt notification with written folle..t.p t ithin 24 hcurs and the second type requires a written report withln 30 days. The proposed reporting requirements aise delete reporting of information no longer required by the SRC and duulicction of reported informatien. These changes effectuate the unifornity of required reports and desired format in a manner that will permit more rapid rccognition of potential prcblems.
We feel that identifying ninimun acceptable quali fications for facility personnel as sec forth in the proposed change would assure capacle performance from the facility staff.
Other administrative requirements also restated by the specifications assure uniformity and conformance to the desired features in the review, staffing, and procedures.
Incorporating the respiratory protection program currently accepted by the NRC assures that a consistent method of using respiratory equipment is immediately available whencver needed.
Similar changes are being cpproved for all po.eer reactor licensees, so all licensees will have the sa.r.e requirements presented in a uniform manner.
lie have concluded that the proposal improves the licensce's program for evaluatin; plant performance and the reporting of the operating inferntien needed by the Commission to assess safety related activities and is acceptme The facility staff qualifications and training program conform to Regulatory Guide 1.0 and therefore are acceptable. 'Ihe administrative procedures and facility review and audit are consistent with Regulatory Guide 1.33 and are acceptable. The modified reporting program is consistent with the guidance provided by Regulatory Guide 1.16, " Reporting of Operating Infornaticc. -
Technical Specifications," Revision 4 The administratice controls are consistent with requirements being incorporated in Technical Specificaticn; for new licensed facilities.
1556 130 We have determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact. Having made this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR 351.5(d)(4), that an environmental statement, negative declaration, or environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the change does not involve a significant increase in the probability or consequences of accidents previously considered and does not involve a significant decrease in a safety margin, the change does not involve a significant ha:ards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Date: S'hi 2 7 'F 1556 131
j UNITED STATES NUCLEAR REGULATORY CO:0!ISSION DOCFET NO. 50-259 METROPOLITAN EDISO.\\ CC:3 A' Y JERSEY CENTRAL PCNER A.' D LIGliT COMPET PEN: 5YLVANIA ELECTRIC CCMPANY NOTICE CF ISSUANCE OF AMENDNENT TO FACILITY OPERATING LICENSE Notice is hereby given that the U. S. Nuclear Regulatory Commission (the Cornission) has issued Amendment No. 11 to Facility Operating License No. DPR-50 issued to Metropolitan Ediscn Company, Jersey Central Power and Light Company, and Pennsylvania Electric Company which revised Technical Specifications for operation of the Three Mile Island Nuclear Station, Unit 1, located in Dauphin County, Pennsylvania. The amend-ment becomes effective 30 days after the date of issuance.
The amendment revises the administrative control section of the Technical Specifications for the Three Mile Island Nuclear Station, Unit 1.
The application for the amendment complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Commission has made apprcpriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment.
Prior public notice of this amendment is not required since the amendment does not involve a significant ha:ards consideration.
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- The Commission has determined that the issuance of this amend-ment will not result in any significant environmental impact and that pursuant to 10 CFR 951.5(d)(4) an environmental statement, negative declaration or environmental impact appraisal need not be prepared in connection with issuance of this amendment.
For further details with respect to this action, see (1) the application for amendment dated December 23, 1975, (2) Amendment No. 11 to License No. DPR-50, and (3) the Commission's related Safety Evaluation. All of these items are available for public inspection at the Commission's Public Document Room,1717 H Street, N.W., Washington, D.C. and at the Government Publications Sectiva, State Library of Pennsylvania, Box 1601 (Education Building), Harrisburg, Pennsylvania.
A copy of items (2) and (3) may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, D.C.
- 20555, Attention: Director, Division of Reactor Licensing.
Dated at Bethesda, afaryland, this 27 day of January 1976.
FOR THE NUCLEAR REGULATORY CONNISSION vh
' J
/
s Robert W. Reid, Chief Operating Reactors Branch #4 Division of Reactor Licensing 1556 133