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Application for Amend to License NPF-86,incorporating Programmatic Controls in TS for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements
	ML20217Q097
Person / Time
Site:	Seabrook
Issue date:	03/05/1998
From:	Feigenbaum T; NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:	; NRC
Shared Package
ML20217Q094	List: ML20217Q091; ML20217Q097; ML20217Q103; ML20217Q111;
References
	NUDOCS 9803110371
	Download: ML20217Q097 (8)
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, d se s This License Amendment Request is submitted by North Atlantic Energy Service Corporation pur iant to 10CFR50.90. The following information is enclosed in support of this License ,

Am ,ndment Request: I e Section 1 -

Introduction and Safety Assessment for Proposed Change

. Section 11 -

Markup of Proposed Change e Section 111 -

Retype of Proposed Change e Section IV -

Determination of Significant Hazards for Proposed Change

. Section V - Proposed Schedule for License Amendment issuance and Effectiveness

. Section VI -

Environmentallmpact Assessment Sworn and Subscribed 2 day of .1998 M T d C.Feigenbaum /

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Notary Public Executive Vice President and Chief Nuclear Officer 9803110371 980?OS PDR ADOCK 0500? 143 !

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Section I Introduction and Safety Assessment for the Proposed Changes i

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I. INTRODUCTION AND SAFETY ASSESSMENT OF PROPOSED CHANGES A. Introduction i

License Amendment Request (LAR) 97-08 proposes changes to Seabrook Station's Radiological Effluent Technical Specifications (TS) and Administrative Controls section of the Technical Specifications, as a.ithorized by NRC Generic Letter (GL) 89-01, " Implementation Of Programmatic Controls For Radiological Effluent Technical Specifications (RETS) 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." The proposed amendment will incorporate programmatic controls in the Technical Specifications for radioactive effluents and for environmental monitoring conforming to the applicable regulatory requirements. This will allow relocation of existing procedural details of the current RETS to the Offsite Dose Calculation Manual (ODCM). Procedural details associated with solid radioactive wastes will be relocated to the Process Control Program (PCP). Refer to Table I for an ovewiew of the specific changes proposed to the Technical Specifications.

B. Safety Assessment of Proposed Changes The proposed line-item improvements to Technical Specifications (fS) relative to the RETS are consistent with the guidance provided in Generic Letter 89-01.

The amendment will provide programmatic controls for RETS consistent with regulatory requirements and allow relocation of procedural details, consisting of the limiting conditions for operation (LCOs),

their applicability, remedial actions, surveillance requirements and the Bases section of the TS for these requirements, to the appropriate licensee-controlled document (s). Relocation of the procedural details to the appropriate licensee-controlled document isjustified since they no longer meet the criteria of 10 CFR 50.36 for inclusion in TS.

The NRC revised 10 CFR 50.36 on July 19, 1995 to meet the intent of a previously issued policy i statement, " Final Policy Statement on Technical Specification improvements for Nuclear Power i Reactors,"(58 FR 39312), which provided a specific set of four (4) objective criteria to determine which of the design conditions and associated surveillances should be located in TSs as limiting conditions for operation. The NRC recognized that implementation of these additional criteria may cause some requirements presently in TSs to no longer merit inclusion in TSs. The proposed RETSs to be relocated are candidates for no longer meriting inclusion in TSs since they do not meet the four objective criteria specified in 10 CFR 50.36. The design conditions contained within the proposed RETSs to be relocated are not: (1) installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary; (2) a process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier; (3) a structure, system or component (SSC) that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier; and,(4) a SSC which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.

)

Page 2

Future changes to the reiocated RETSs in either the ODCM or PCP will be governed by the programmatic and administrative controls specified in the Administrative Controls section of TS.

Therefore, a comparable level of administrative control will continue to be applied to those design conditions and associated surveillances being relocated to the ODCM or PCP.

One other significant change is made to the ODCM, Part A. The current wording requires prior NRC review and approval of all proposed changes made to Part A. Part A consists of the Radioactive Liquid Waste Sampling and Analysis Program, the Radioactive Gaseous Waste Sampling and Analysis Program, and the Radiological Environmental Monite-:. g Prograni. These programs are to assure that the amount of radioactive effluents released to the environment and resultant exposure to members of the public are maintained as low as is reasonably achievable and within the limits of the respective Technical Specifications. The requirement to obtain NRC review and approval prior to implementation of proposed changes predates the NRC initiative in GL 89-01 to place the responsibihty for the procedural details of the required effluent and environmental monitoring programs directly with the licensee. GL 89-01 states that the NRC staff does not intend to repeat technical reviews of the relocated procedural

, details because their consistency with the applicable regulatory requirements is a matter of record from l past NRC reviews of RETS. The procedural details associated with these programs, which are currently contained in the ODCM, are addressed in GL 89-01, Supplement 1, as procedural details which merit l relocation to the ODCM. Therefore, since the procedural details for sampling and analysis associated with the aforementioned programs are presently contained in the ODCM the requirement to obtain NRC approval prior to any changes to Part A is no longer applicable and will be removed so as to meet the

! intent of GL 89-01. As previously stated, future changes to the ODCM will be governed by the l programmatic controls specified in the Administrative Controls section of TS.

i Summarv l

i The proposed changes transfer procedural requirements for radiological effluent and environmental monitoring from the Technical Specifications to other licensee-controlled documents (ODCM and PCP),

along with the addition of programmatic and administrative controls for these procedural requirements being placed in the Administrative Controls Section of the Technical Specifications. The content of existing technical requirements concerning RETS is not affected by the proposed changes. The proposed i changes will not reduce the accuracy or reliability of the dose calculations or setpoint determinations l performed under the existing ODCM since none of these methods are affected by the proposed changes.

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