ML20035D254
| ML20035D254 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/05/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20035D253 | List: |
| References | |
| NUDOCS 9304120350 | |
| Download: ML20035D254 (3) | |
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UNITED STATES
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.....a SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.173 TO FACILITY OPERATING LICENSE NO. DPR-50 METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION THREE MILE ISLAND NUCLEAR STATION UNIT N0. 1 DOCKET NO. 50-289
1.0 INTRODUCTION
By letter dated May 19, 1992, as supplemented November 30, 1992, January 29, and February 12, 1993, GPU Nuclear Corporation (GPUN/ licensee) proposed to incorporate programmatic controls for radiological effluents and radiological environmental monitoring in the Administrative Controls section of the Three Mile Island, Unit 1 (TMI-1) Technical Specifications (TS) consistent with the requirements of 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50. At the same time, the licensee proposed to transfer portions of the procedural details of the Radiological Effluent Technical Specifications (RETS) from the TS to the Offsite Dose Calculation Manual (ODCM) or to the Process Control Program (PCP) for solid radioactive wastes as 4
appropriate.
With these changes, the specifications related to RETS reporting requirements were simplified.
Finally, changes to the definitions of the ODCM and PCP were proposed consistent with these changes. Guidance on these proposed changes was provided to all power reactor licensees and applicants by Generic letter 89-01 dated January 31, 1989.
The January 29, and February 12, 1993 letters provided errata pages that did not change the initial no significant hazards consideration determination or expand the scope of the original Federal Reaister notice.
2.0 EVALUATION The licensee's proposed changes to the TS are in accordance with the guidance provided in Generic Letter 89-01 and are addressed below.
(1)
The licensee has proposed to incorporate programmatic controls for radioactive effluents and radiological environmental monitoring in Specification 6.8.4, " Procedures and Programs," of the TS as noted in the guidance provided in Generic Letter 89-01. The programmatic controls ensure that programs are established, implemented, and maintained to easure that operating procedures are provided to control radioactive effluents consistent with the requirements of 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix 1 to 10 CFR Part 50.
9304120350 930405 PDR ADOCK 05000209 p
. (2)
The licensee has confirmed that the detailed procedural requirements addressing Limiting Conditions for Operation, their applicability, remedial actions, associated surveillance requirements, or reporting requirements for the following specifications have been prepared to implement the relocation of these procedural details to the ODCM or PCP.
These changes to the ODCM and PCP have been prepared in accordance with the new Administrative Controls in the TS on changes to the ODCM and PCP so that they will be implemented in the ODCM or PCP when the proposed amendment is issued.
SPECIFICATION JJJT1[
3/4.22.3 RADI0 ACTIVE EFFLUENTS: SOLID RADIOACTIVE WASTES 3/4.22.4 RADI0 ACTIVE EFFLUENTS: TOTAL DOSE 3/4.23.1 RADIOLOGICAL ENVIRONMENTAL MONITORING: MONITORING PROGRAM 3/4.23.2 RADIOLOGICAL ENVIRONMENTAL MONITORING: LAND USE CENSUS 3/4.23.3 RADIOLOGICAL ENVIRONMENTAL MONITORING: INTERLABORATORY.
COMPARISON PROGRAM 6.9.3.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.4.1 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.17 MAJOR CHANGES TO LIQUID, GASEOUS, AND SOLID RADWASTE TREATMENT SYSTEMS These procedural details that will be removed from the TS are not required by the Commission's regulations to be included in TS. They have been prepared for incorporation in the ODCM or PCP upon issuance of l
the proposed license amendment and may be subsequently changed by the licensee without prior NRC approval. Changes to the ODCM and PCP are I
documented and will be retained for the duration of the operating i
license in accordance with Specification 6.10.30.
l (3)
The licensee has proposed replacing the existing specifications in the Administrative Controls section of the TS for the Annual Radiological Environmental Operating Report, Specification 6.9.3.1, for the Semiannual (now annual) Radioactive Effluent Release Report, Specification 6.9.4.1, for the Process Control Program, Specification 6.13, and for the Offsite Dose Calculation Manual, Specification 6.14, with the updated TS that were provided in Generic Letter 89-01.
(4)
The licensee has requested a deletion to Part "b" of the ACTION statement for TS 3.22.1.1, " Liquid Effluent - Concentration," and TS 3.22.2.1, " Gaseous Effluent - Dose Rate." Part "b" requires the plant to be shutdown, if releases of liquid or gaseous effluent cannot be immediately restored to within TS limits.
This requested deletion is consistent with NUREG-1301, "Offsite Dose Calculation Manual Guidance:
Standard Radiological Effluent Controls for Pressurized Water Reactors."
The licensee has also proposed that the Bases reference to infant be revised to child to be consistent with NUREG-1301.
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' r The licensee provided a supplement to the original amendment request on November 30, 1992, to incorporate changes resulting from NRC-initiated revisions to 10 CFR 36(a)(2) made effective on October 1, 1992. This rule change revised effluent release reporting requirements from semiannual to annual.
Conforming changes were proposed to the THI-l TS.
These changes are considered to be strictly administrative to comply with changes to the NRC's regulations.
On the basis of the above, the staff finds that the changes included in the proposed TS amendment request are consistent with the guidance provided in Generic Letter 89-01.
Because the control of radioactive effluents continues to be limited in accordance with operating procedures that must satisfy the regulatory requirements of 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50, the NRC staff concludes that this change is administrative in nature and there is no impact on plant safety as a conse.
quence. Accordingly, the staff finds the proposed changes acceptable.
3.0 STATE CONSULTATION
t In accordance with the Commission's regulations, the Pennsylvania State i
official was notifieo of the proposed issuance of the amendment. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment relates to changes in recordkeeping, reporting, or administrative procedures or requirements.
The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on the Commission's finding (57 FR 61112). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(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 the amendment.
5.0 CONCLUSION
The Commission has 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, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common i
defense and security or to the health and safety of the public.
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Principal Contributor:
J. Zimmerman T. Dunning i
Date:
April 5, 1993
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