ML20086B309
| ML20086B309 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/12/1995 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20086B306 | List: |
| References | |
| GL-89-01, GL-89-1, NUDOCS 9507050288 | |
| Download: ML20086B309 (6) | |
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+4 UNITED STATES l
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NUCLEAR REGULATORY COMMISSION f
WASHINGTON. D.C. 2aa88 "1
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S K FTY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 188 AND 170 TO FACILITY OPERATING LICENSE NOS. DPR-66 AND NPF-73 DUOVESNE LIGHT COMPANY l
OHIO EDISON COMPANY PENNSYLVALIA POWER COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDISON COMPANY i
BEAVER VALLEY POWER STATION. UNIT NOS. 1 AND 2 DOCKET NOS. 50-334 AND 50-412 i
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1.0 INTRODUCTION
By letter dated June 17, 1993, as supplemented October 20, 1993, the Duquesne Light Company (the licensee) submitted a request for changes to the Beavar Valley Power Station, Unit Nos. I and 2, Technical Specifications (TSs). The requested changes would incorporate,.rogrammatic controls for radiological effluents and radiological environmental monitoring in the Administrative Controls section of the TSs consistent with the requirements of 10 CFR 20.1301, 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 the procedural details of the Radio-logical Effluent Technical Specifications (RETS) from the TSs to the Offsite Dose Calculation Manual (0DCM) or to the Process Control Program (PCP) for solid radioactive wastes as appropriate. With these changes, the TSs related to RETS reporting requirements were simplified.
Finally, changes to the definitions of the ODCM and PCP were proposed consistent with these chcnges. Guidance on these proposed changes was provided to all power reactor licensees and applicants by Generic Letter (GL) 89-01, " Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program," dated January 31, 1989. The October 20, 1993, supplemental letter provided clarifying information.
The May 23, 1995, supplemental letter provided typed final TS pages for issuance of these amendments and included minor editorial i
changes.
Neither the October 20, 1903, nor the May 23, 1995, letter changed the initial proposed no significant hazards consideration determination cr expanded the scope of the original Federal Reaister notice.
I 9507050208 950612 PDR ADOCK 05000334 P
' i 2.0 EVALUATION 2.1 Removal of RETS from the Technical Soecifications Section 50.36 of Title 10 of the Code of Federal Regulations established the regulatory requirements related to the content of TSs.
The rule requires that TSs include items.in specific categories, including safety limits, limiting conditions for operation, and surveillance requirements; however, the rule does not specify the particular requirements to be included in a plant's TSs.
The NRC developed criteria, as described in the " Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors,"
(58 FR 39132) to determine which of the design conditions and associated surveillances need to be located in the TSs because the requirement is "necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the puulic health and safety." Briefly, those criteria are (1) detection of abnormal degradation of the reactor coolant pressure boundary, (2) boundary conditions for design basis accidents and transients, (3) primary success paths to mitigate design basis accidents and transients, and (4) functions determined to be important to risk or operating experience. The Commission's final policy statement acknowledged that its implementation may result in the relocation of existing TS requirements to licensee-controlled documents and programs.
The RETS provide the release limits and monitoring and reporting criteria for gaseous, liquid, and solid radioactive effluents.
Such releases are a byproduct of the use of a nuclear reaction for power generation. The RETS are not related to the detection of abnormal degradation of the reactor coolant pressure boundary, boundary conditions for design basis accidents and transients, or functions determined to be important to risk or operating experience.
In GL 89-01 the staff noted that it had examined the contents of the RETS in relation to the Commission's Interim Policy Statement of Technical Specifications Improvements and had determined that programmatic controls could be implemented in the Administrative Controls section of the TSs to satisfy the existing regulatory requirements for RETS.
The staff had also determined that the procedural details of the TSs on radioactive effluents and radiological environmental monitoring could be relocated to the ODCM, while the procedural details for solid radioactive waste could be relocated to the PCP. After relocation, future changes to these procedural details will be controlled by the controls for changes to the ODCM and PCP included in the Administrative Controls section of the TSs.
On this basis, the NRC staff concludes that the RETS do not need to be controlled by TSs, and changes to the RETS are adequately controlled by 10 CFR 50.59, " Changes, tests, and experiments." Should the licensee's determination conclude that an unreviewed safety question is involved, due to either (1) an increase in the probability or consequences of accidents or malfunctions of equipment important to safety, (2) the creation of a possibility for an accident or malfunction of a different type than any evaluated previously, or I
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! i (3) a reduction in the margin of safety, NRC approval and a license amendment would be required prior to implementation of the change. NRC inspection and enforcement programs also enable the staff to monitor facility changes and licensee adherence to Updated Final Safety Analysis Report (UFSAR) commitments and to take any remedial action that may be appropriate.
i The NRC staff has, concluded, therefore, that relocation of RETS is acceptable l
because (1) their inclusion in TSs is not specifically required by 10 CFR l
50.36 or other regulations, (2) the RETS are not required to avert an immediate threat to the public health and safety, and (3) changes that are deemed to involve an unreviewed safety question will require prior NRC approval in accordance with 10 CFR 50.59(c).
j 2.2 Imnlementation of RETS Reauirements in 00CM and PCP In GL 89-01 the staff provided model specifications and encouraged licensees to propose changes consistent with the GL. The licensee's proposed changes to i
the TSs are in accordance with the guidance provided in NRC GL 89-01 and are.
addressed below, i
(1)
The licensee has proposed to incorporate programmatic controls for radioactive effluents and radiological environmental monitoring in TS 6
6.8.4, " Procedures and Programs," as noted in the guidance provided in GL 89-01.
The programmatic controls ensure that programs are established, implemented, and maintained to ensure that operating procedures are provided to control radioactive effluents consistent with the requirements of 10 CFR 20.1301, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50.
(2)
The licensee has confirmed that the detailed procedural requirements i
addressing limiting conditions for operation, their applicability, 1
remedial actions, associated surveillance requirements, or reporting j
requirements for the following specifications have been prepared to 1
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 i
the new Administrative Controls in the TSs on changes to the ODCM and PCP so that they will be implemented in the 00CM or PCP when this amendment is issued.
SPECIFICATION IIILE 3/4.3.3.9 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3/4.3.3.10 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (This TS has been partially relocated to the 00CM and the remaining portion renumbered as TS 3/4.3.3.11) 3/4.11.1.1 RADI0 ACTIVE EFFLUENTS:
LIQUID EFFLUENTS CONCENTRATION
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3/4.11.1.2 RADI0 ACTIVE EFFLUENTS: LIQUID EFFLUENTS DOSE 3/4.11.1.3 RADI0 ACTIVE EFFLUENTS:. LIQUID WASTE TREATMENT-3/4.11.2.1 RADI0 ACTIVE EFFLUENTS: GASE0US EFFLUENT DOSE RATE l
3/4.11.2.2,
RADI0 ACTIVE EFFLUENTS: DOSE NOBLE GASES 3/4.11.2.3 RADI0 ACTIVE EFFLUENTS: DOSE, RADIO 10 DINES, RADI0 ACTIVE MATERIAL IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN N0BLE GASES 3/4.11.2.4 RADI0 ACTIVE EFFLUENTS: GASE0US RADWASTE TREATMENT 3/4.11.3 RADI0 ACTIVE EFFLUENTS: SOLID RADI0 ACTIVE WASTE 3/4.11.4 RADI0 ACTIVE EFFLUENTS: TOTAL DOSE 3/4.12.1 RADIOLOGICAL ENVIRONMENTAL MONITORING:. MONITORING PROGRAM 3/4.12.2 RADIOLOGICAL ENVIRONMENTAL MONITORING: LAND USE CENSUS 3/4.12.3 RADIOLOGICAL ENVIRONMENTAL MONITORING:
INTERLABORATORY COMPARISON PROGRAM 6.9.1.12 SEMI-ANNUAL RADI0 ACTIVE EFFLUENT.. RELEASE REPORT 6.16 MAJOR CHANGES TO RAD 10 ACTIVE WASTE TREATMENT SYSTEMS These procedural details that have been removed from the TSs are not l
required by the Commission's regulations to be included in TSs. They have been prepared for incorporation in the ODCM or PCP upon issuance of.
I this license amendment and may be subsequently changed by the licensee in accordance with 10 CFR 50.59 without prior NRC approval. Changes to the ODCM and PCP are documented and will be retained for the duration of j'
the operating license in accordance with Specification 6.10.2.n.
(3)
The licensee has proposed replacing the existing TSs in the Administrative Controls section of the TSs for the Annual Radiological Environmental Operating Report, TS 6.9.1.10, for the Process Control Program, TS 6.14, and for the Offsite Dose Calculation Manual, TS 6.15, with the updated specifications that were provided in GL 89-01. The requirements for the Semi-Annual Radioactive Effluent Release Report, TS l
7 6.9.1.12, were changed to annual and were included in TS 6.9.1.11.
This change reduces the regulatory burden for the licensee and is consistent with a revision to 10 CFR Part 50 (57 FR 39353, August 31,1992).
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1 t i The following specifications that are included under the heading of Radioactive Effluents have been retained in the TSr. This is in accordance with the guidance of GL 89-01.
i SPECIFICATION J11LE 3/4.3.3.11,
EXPLOSIVE GAS MONITORING INSTRUMENTATION (Retained applicable requirements from TS 3/4.3.3.10 and renumbered as TS 3/4.3.3.11) 3/4.11.1.4 LIQUID HOLDUP TANKS 3/4.11.2.5 GASEOUS WASTE STORAGE TANKS 3/4.11.2.6 EXPLOSIVE GAS MIXTURE On the basis of the above, the NRC staff finds that the changes included in the proposed TS amendment request are consistent with the guidance provided in GL 89-01 and that the licensee has adequately relocated the RETS requirements.
Because the control of radioactive effluents continues to be limited in accordance with operating procedures that must satisfy the regulatory requirements of 10 CFR 20.1301, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50, the NRC staff concludes that these changes are administrative in nature and there is no adverse impact on plant safety as a consequence. Accordingly, the NRC staff finds the proposed changes acceptable.
3.0 STATE CONSULTATIQH I
In accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendments. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20'and c ange surveillance requirements. The NRC staff has determined that the a nts involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (58 FR 41504). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
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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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors:
W. Meinke T. Dunning D. Brinkman Date: June 12, 1995 I
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