ML20141G794

Proposed Tech Specs,Ensuring Requirements for Radiation Protection Program Uniform for Units 1 & 2

ML20141G794
Person / Time
Site:	Indian Point
Issue date:	12/19/1985
From:	CONSOLIDATED EDISON CO. OF NEW YORK, INC.
To:
Shared Package
ML20141G768	List: ML20141G763 ML20141G778 ML20141G794
References
NUDOCS 8601100414
Download: ML20141G794 (6)

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'A1TACINENT A APPLICATION FOR AMENDMENT TO PROVISIONAL OPFRATING LICENSE Technical Specification Page Revisions Consolidated Edison Company-of New York, Inc.

Indian Point Unit No. 1 Docket No. 50-3 Provisional Operating License No. DPR-5 Ikcember, 1985 9601100414 851219 . ,.

PDR ADOCK 0 % 3

3.0 Administrative and Procedural Safeguards 3.1 Organization 3.1.1 The organization for ' facility management and technical support shall be as shown in Figure 3.1.

3.1.2 The Facility Organization shall be shown in Figure 3.2. 'Ihe Support Facilities Supervisor is responsible for operations at the Unit No. I facility.

3.1.3 The Vice President-Nuclear Power shall be responsible for overall facility activities as shown in Figure 3.2 and shall delegate in writing the succession to this responsibility during his absence.

3.1.4 The operaticn of the facility, the operating organization, the procedures for operation, and modifications to the facility shall be subject to review by the Station Nuclear Safety Committee.

The committee shall report to the Vice President-Nuclear Power.

3.1.5 The Nuclear Facilities Safety Committee shall function to provide independent review and audit of designated activities in areas of nuclear -engineering, chemistry, radiochemistry, metallurgy and non-destructive testing, instrumentation and control, radiological safety, mechanical and electrical engineering, administrative controls and quality assurance practices, and radiological environmental effects.

3.1.6 All fuel handling shall be under the direct supervision of a licensed operator.*

3.2 Operating Instructions and Procedures 3.2.1 No fuel will be loaded into the reactor core or moved into the reactor containment building without prior review and authorization by the Nuclear Regulatory Commission.

3.2.2 Detailed written instructions setting forth procedures used in connection with the operation and maintenance of the nuclear power plant shall conform to the Technical Specifications.

3.2.3 Operation and maintenance of equipment related to safety when there is no fuel in the reactor shall be in accordance with written instructions.

• Licensed operator for IP-1 or IP-2.

Amendment No.

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~f-4.0 OPERATING LIMITATIONS

~4.1 Ceneral 4.1.1' Whenever any operation is being performed that^ could' result in the release of radioactivity or create a change in radiation levels, supporting- facilities shall be maintained and operated as required in these Technical Specifications.

4.1.2 The concentration of radioactive materials released in liquid or gaseous form . to unrestricted areas shall not exceed the Release of radioactive limits specified in 10 CFR Part 20.

liquids and gases- shall also be consistent with the requirements of 10 CFR Part 50, Appendix I, as specified in Specifications 3.9 and 4.10 of Appendix A to the Indian Point Unit No. 2 Facility Operating License No. DPR-26.

4.1.3 All . radioactive waste material shall be handled in accordance with 10 CFR Part 20. In addition, solid radioactive waste

, shall be controlled as specified in Specifications 3.9.D and 4.10.D of Appendix A to the Indian Point Unit No. 2 Facility Operating License No. DPR-26.

4.1.4 Radiation monitoring systems shall be maintained operational for: '(1) nuclear services building sewage, (2) chemical systems building sewage, (3) sphere foundation sump, (4) secondary purification blowdown cooling water, and (5) area radiation monitors. If monitoring systems are not operational, effluent sampling and/or local monitoring shall be accomplished to replace the non-operating system. In addition, Unit I radioactive effluent monitoring instrumentation shall be operable as specified in Specification 3.9 of Appendix A to Indian Point Unit No. 2 Facility Operating License No. DPR-26.

4.1.5 The Indian Point site meteorological monitoring system shall be maintained and operated as specified in Specifications 3.15 and 4.19 of Appendix A to the Indian Point Unit .No. 2 Facility Operating License No. DPR-26.

4.1.6 The Indian Point site Radiological Environmental Monitoring Program 'shall be conducted as specified in Specification 4.11 of Appendix A to the Indian Point Unit No. 2 Facility Operating License No. DPR-26.

4.1.7 The. Indian Point site Radiation Protection Program shall be conducted as specified in Specification 6.11 and 6.12 of Appendix A to the Indian Point Unit No. 2 Facility Operating License DPR-26.

4.2 _ Operations Limits 4.2.10 Spent Fuel Storage and llandling 4.2.10.3 All irradiated fuel shall be stored in the racks provided in the Fuel llandling Building storage pools.

Amendment No.

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l ATTAONENT B APPLICATION FOR AMENINENT

[ TO PROVISIONAL OPERATING LICENSE i

i Safety Assessment I

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?I Consolidated Edison Company of New York, Inc.

!' Indian Point Unit No. 1 Docket No. 50-3 December, 1985 g.

Safety Assessment Description of Change and Evaluation:

The proposed change revises the Indian Point Unit No.1 (IP-1) Technical Specifications by deleting Section 3.2.6 and adding Section 4.1.7 to assure that, with respect to the Radiological Protection Program, the IP-1 technical specifications are consistent with Unit No. 2 (IP-2) requirements.

Currently, the IP-1 and IP-2 technical specifications requirements pertaining to personnel radiation protection are dissimilar. The IP-1 site currently has technical specifications which require personnel radiation protection procedures in accordance with 10 CFR Part 20. The existing IP-2 technical specifications contain requirements for establishing personnel radiation protection procedures pursuant to 10 CFR Part 20, and in addition, specifies alternative methods of controlling access to high radiation areas. The basis for allowing alternative access methods is found in Section 203(c)(3) of 10 CFR Part 20. This section states in part that:

"Any hicensee, or applicant, may apply to the Commission for approval of methods not included in paragraph (c)(2) of this section for controlling access to high radiation areas. The Commission will approve the proposed alternative if the licensee or applicant demonstrates that the alternative methods of control will prevent unnuthorized entry into a high radiation area....."

Since the IP-1 technical specifications do not specify similar alternative high radiation access methods, it has led to different procedures and differing application of area access requirements between IP-1 and IP-2. This can result in personnel confusion as to which requirement applies.

Since the proposed change refers to and is similar to the existing IP-2 Technical Specification radiological protection requirements it is consistent with previously NRC approved alternative methods for high radiation area access control in accordance with 10 CFR Part 20.203(c)(5) and the model Standard Technical Specifications. Thus, we have determined that it does not involve a significant reduction in a margin of safety and will not compromise the health and safety of the public.

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l Basis For No Significant Hazards Consideration Determination:

l Re ' Commission has s provided guidance concerning the application of the standards for determining whether a significant hazards consideration exists by providing certain criteria. Consistent with the Conmission's criteria for determining whether a proposed amendment to an operating  ;(

license involves no significant hazard consideration,10 CFR 50.92 (48 FP, p -

14870), we have determined that the proposed change will not increase the probability;.or the consequences of an accident previously evaluated, or +

. create the possibility of a new or different kind of accident from any

( accident previously evaluated, or involve a signific. int reduction in a -

margin of safety. The proposed amendment does < r.ot involve a change in l .'

configuration or operation of Indian Point Unit JNo.1 (IP-1). Thus, it 3 l does not increase the probability or consequences of an accident or introduce the possibility of a new or different kind of accident from any l previously evaluated. The IP-1 Technical Specifications- requirement >

l relating to radiation protection is being revised to ensure that it is i .

I_ consistent with pre-established and implemented practices at IP-2. Thus, n there would be no significant reduction in the margin of safety. ,

Therefore, we havb determined that the applica tion involves no ,1 l significant hazards 6 nsideration. .

?. c l De proposed chance has been reviewed by the Indian Point' Unit No. 2 l Station Nuclear Safety Committee and the Consolidated Fdison' Nuclear >

l Facility Safety Committee. Both committees concur that this change .does <

not represent a significant hazards consideration and will not. cause any s change in the types or increase in the amounts of effluents or'any change

, in the authorized power level of the facility. y ,

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