ML20116N352

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Safety Evaluation Supporting Amend 107 to License DPR-50
ML20116N352
Person / Time
Site: Crane Constellation icon.png
Issue date: 04/24/1985
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20116N350 List:
References
NUDOCS 8505070144
Download: ML20116N352 (2)


Text

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.107 TO FACILITY OPERATING LICENSE NO. DPR-50 METROP0 TITAN EDIS0N COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION THREE MILE ISLAND NUCLEAR STATION, UNIT N0.1 DOCKET NO. 50-289 INTRODUCTION By letter dated September 24, 1984, GPU Nuclear Corporation requested changes to Appendix A of Facility Operating License No. DPR-50. The changes would modify existing Technical Specification 6.12, High Radiation Area, by 1)

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defining high radiation areas in accordance with 10 CFR 20.202(b)(3), and 2) indicating that the specifications for access to such high radiation areas apply to groups, as well as individuals.

In response to matters discussed during a December 11, 1984 telephone conversation between NRC and licensee

. staff members, on December 21, 1984, GPU Nuclear Corporation submitted a supplement to the requested change. This supplement incorporated the original changes, and also provided additional clarification of high radiation area access controls.

EVALUATION The requested changes to Technical Specification (TS) Section 6.12 would enhance and clarify the control measures currently required for access to high radiation areas. The September 24, 1984 submittal proposes a change to Section 6.12.1.a that would specifically refer to the definition of High Radiation Area as provided in 10 CFR 20.202(b)(3). Also, the proposed TS would extend to groups of individuals the specifications for individual access to high radiation areas. These changes are consistent with the Standard TSs.

The supplemental December 11, 1984 submittal provided additional clarification at the request of the NRC staff. First, the supplement makes clear the limitations on the use of a dose integrating device, namely that when such a device is used, the existing dose rate level in the area of concern must be established, and personnel using the device made knowledgeable of the levels. This proposed change is considered to be clarification of what would normally be expected. Second, the supplement specifically clarifies implied duties of the radiological control technician, namely that he/she provides positive control over activities within the high radiation area in addition to surveillance of the area. The proposed TS changes in the December,11 submittal are also consistent with the Standard TSs and therefore acceptable.

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. ENVIRONMENTAL CONSIDERATION This amendment involves only changes in administrative procedures and requirements. Accordingly, this amendment meets the eli categorical exclusion set forth in 10 CFR Section 51.22(gibility criteria for c)(10). Pursuant to 10 CFR.51.22(b), no environmental ' impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.

CONCLUSION We have concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) 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 4

and security or to the health and safety of the public.

Dated: April 24, 1985 Principal Contributor: John R. White s

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