ML20078B356

LAR to Licenses DPR-42 & DPR-60,changing Submittal Frequency of Radioactive Effluent Release Rept from Semiannual to Annual & Revising Submittal Schedule to Require Submittal by May 1st of Each Yr

ML20078B356
Person / Time
Site:	Prairie Island
Issue date:	10/17/1994
From:	Wadley M NORTHERN STATES POWER CO.
To:
Shared Package
ML20078B351	List: ML20078B348 ML20078B356 ML20078B362
References
NUDOCS 9410250139
Download: ML20078B356 (6)

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l UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET NO. 50-282 50-306 REQUEST FOR AMENDMENT TO OPERATING LICENSES DPR-42 & DPR-60 LICENSE AMENDMENT REQUEST DATED October 17, 1994 l Northern States Power Company, a Minnesota corporation, requests authorization for changes to the Prairie Island Operating License and Appendix A as shown on j the attachments labeled Exhibits A, B, and C. Exhibit A describes the l

proposed changes, reasons for the changes, and the supporting safety evaluation /significant hazards determination. Exhibit B contains current Prairie Island Technical Specification pages marked up to show the proposed changes. Exhibit C contains the revised Technical Specification pages.

This letter contains no restricted or other defense information.

i i NORTHERN STATES POWER COMPANY By /$fhU m /

M. D. Wadley -

Plant Manager Prairie Island 'uclear Generating Plant On this/[ day h of 8 7 before me a notary public in and for said County, personally appeared W. D. Wadley, Plant Manager, Prairie Island Nuclear Generating Plant, and being first duly sworn acknowledged that he is authorized to execute this document on behalf of Northern States Power Company, that he knows the contents thereof, and that to the best of his knowledge, information, and belief the statements made in it are true and that it is not interposed for delay.

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j MMKlI4 K. LaCORE

NOTARYPUEIC4NNNE90TA l , HEISIIP9iCOUNTY l . . . . . Mr.Comminnan Espres hn. 31,2000

.!.. . . . . . . . . . ., . . . .j .. . . .f3 3 3 9410250139 941017 PDR ADOCK 05000282 P PDR

LICENSE AMENDMENT REQUEST DATED October 17, 1994 Change Radioactive Effluent Report Submittal from Semiannual to Annual EXHIBIT A Description of the Proposed Changes, The Reasons for Requesting the Changes, and the Supporting Safety Evaluation /Significant Hazards Determination Pursuant to 10 CFR Part 50, Sections 50.59 and 50.90, the holders of Operating Licenses DPR-42 and DPR-60 hereby propose the following changes to the Facility Operating Licenses and Appendix A, Technical Specifications:

Background

l On August 31, 1992, the Federal Register published a change to 10CFR50.36a which required licensees to, " submit a report to the Commission annually that specifies the quantity of each of the principal radionuclides released to i unrestricted areas in liquid and in gaseous effluents during the previous 12 months of operation" In conformance to this change, this license amendment request proposes to change the submittal f;;equency of the Radioactive Effluent i Release Report from semiannual to annual.

To accommodate the extended submittal frequency, this amendment also proposes to revise the submittal schedule to require submittal by May 1 of each year in lieu of the current submittal schedule within 60 days after January 1st and j July 1st.

The proposed amendments include changing the title of the annual report to,

" Annual Radioactive Effluent Report".

I Proposed Chances and Reasons for Channes The proposed changes to Prairie Island Operating License Appendix A, Technical Specifications are described below, and the specific wording changas are shown in Exhibits B and C.

1. SURVEILLANCE REQUIREMENTS. SECTION 4.10. RADIATION ENVIRONMENTAL MONITORING l PROGRAM. Specifications A.S. and B.2. Change " Semiannual" to " Annual" and delete " Release" Justification: This change will implement the revision to 10CFR50.36a by making the plant Technical Specifications report submittal frequency consistent with the regulation. This will also make the report title consistent with the title used by industry.

2. Table TS.4.17-3. (Pare 4 of 4) TABLE NOTATION. Note d. Change " Semiannual" to " Annual" and delete " Release".

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1 Justification: This change will implement the revision to 10CFR50.36a by making the plant Technical Specifications report submittal frequency consistent with the regulation. This will also make the report title consistent with the title used by industry.

3. Table TS.4.17-4. (Pare 3 of 3) TABLE NOTATION. Note f. Change " Semiannual" to " Annual" and delete " Release".

Justification: This change will implement the revision to 10CFR50.36a by making the plant Technical Specifications report submittal frequency consistent with the regulation. This will also make the report title consistent with the title used by industry.

4. ADMINISTRATIVE CONTROLS. SECTION 6.5. PLANT OPERATING PROCEDURES. D.1. and '

E.1: Change " Semi-Annual" to " Annual" Delete " Release" from D.l.

Justification: This change will implement the revision to 10CFR50.36a j by making the plant Technical Specifications report submittal  !

frequency consistent with the regulation. This will also make the report title consistent with the title used by industry.

5. ADMINISTRATIVE CONTROLS. SECTION 6.7. Reporting Recuirements. A.4: Change ,

" Semi-annual" to " Annual" in the subsection title and delete j

" Release" In the first paragraph change "six months" to " calendar year" and substitute "by May 1st" for "within 60 days after January 1st and July 1st". l In the second paragraph delete " release" and make " reports" singular.

l In the third paragraph, delete "to be submitted 60 days after January l 1 of each year". Replace "This same" with "The" and change "these reports" to "the report" In the fourth paragraph, delete "to be submitted 60 days after January l 1 of each year" In the first line of the fifth paragraph replace " release reports" with

" report".

In the first line of the sixth paragraph replace " releases reports" with l l

" report".

Justification: These changes are requested to implement the revision to 10CFR50.36a by making the plant Technical Specifications report submittal frequency consistent with the regulation. The proposed changes to the submittal dates recognize that a single report would be submitted each twelve months rather than each six months. This will also make the report title consistent with the title used by industry.

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j Safety Evaluation l

1 i The proposed amendments te the Technical Specifications for Prairie Island

Units i and II are requested to implement the changes to 10CFR50.36a. These requested amendments do not affect any administrative controls over radioactive effluents, nor do they involve any physical alterations to the Units with respect to radioactive effluents. Also, the requested amendments do not change the methods by which any safety-related system performs its function.

Other technical specifications and other regulations define release limits and notification requirements to the NRC, Environmental Protection Agency, and State Agencies. Any significant release of radioactivity would be reported within one hour with a followup written notification within 30 days. Also the NRC Resident Inspector Program and NRC Regional regulatory programs will assure timely NRC awareness, almost on a day to day basis, of plant operations. The requested changes will not impair the NRC's ability to review information.

Prairie Island's most recent Semiannual Radioactive Report was submitted on August 26, 1994. In accordance with existing Technical Specifications, the next report will be a semiannual report submitted 60 days after January 1,  ;

1995 for the third and fourth quarters of 1994. If the requested amendments '

for change from semiannual to annual submittal are approved by the NRC Staff by July 1, 1995, the initial submittal of an annual report containing the radioactive effluent data will be made by May 1, 1996. The initial annual report will present the data for the four quarter period representing 1995.

These requested license amendments do not affect the plant design or operation nor do they result in a change to the configuration of any equipment. There will be no change in types or increase in the amount of effluents released offsite, as a result, these proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated.

Determination of Sinnificant Hazards considerations The proposed changes to the Operating License have been evaluated to determine whether they constitute a significant hazards consideration as required by 10 CFR Part 50, Section 50.91 using the standards provided in Section 50.92. This analysis is provided below:

1. The proposed amendment will not involve a significant increase in the probability or conseauences of an accident previously evaluated The proposed license amendments are requested to implement a revision to 10CFR50.36a. The requested amendment does not alter any I administrative controls over radioactive effluents, nor do they affect  !

any accident evaluations. Also, the requested amendments do not involve any physical alterations to the plant with respect to radioactive effluents. The proposed changes would only affect the  ;

reporting requirements concerning routine data for radioactive i Page 3 l

i effluents.

Therefore, the probability or consequences of an accident previously evaluated are not affected by any of the proposed amendments.

2. The proposed amendment will not create the possibility of a new or different kind of accident from any accident previously analyzed The proposed license amendments are requested to implement a revision l to 10CFR50.36a. The requested amendment does not alter any l administrative controls over radioactive effluents, nor do they involve any physical alterations to the plant with respect to radioactive effluents. Also, the requested amendments do not change the method by which any safety-related systam performs its function.

The proposed changes would only affect the reporting requirements concerning routine data for radioactive effluents.

Therefore, the possibility of a new or different kind of accident from any accident previously evaluated would not be created.

3. The proposed amendment will not involve a significant reduction in the margin of safety The proposed license amendments are requested to implement a revision  !

to 10CFR50.36a. The requested amendment does not alter any administrative controls over radioactive effluents, nor do they involve any physical alterations to the plant with respect to j radioactive effluents. The proposed changes would only affect the  ;

I reporting requirements concerning routine data for radioactive  ;

! effluents. The operation of systems and equipment remains unchanged.

Therefore, a significant reduction in the margin of safety would not l be involved.

l l Based on the evaluation described above, and pursuant to 10 CFR Part 50, Section 50.91, Northern States Power Company has determined that operation the '

l Prairie Island Nuclear Generating Plant in accordance with the proposed license amendment request does not involve any significant hazards considerations as defined by NRC regulations in 10 CFR Part 50, Section 50.92. I Environmental Assessment Northern States Power Company has evaluated the proposed changes and determined that:

1. The changes do not involve a significant hazards consideration, or

2. The changes do not involve a significant change in the types or

, significant increase in the amounts of any effluents that may be ,

released offsite, or l i

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3. The changes do not involve a significant increase in individual or cumulative occupational radiation exposure.

Accordingly, the proposed changes meet the eligibility criterion for categorical exclusion set forth in 10 CFR Part 51 Section 51.22(c)(9).

Therefore, pursuant to 10 CFR Part 51 Section 51.22(b), an environmental assessment of the proposed changes is not required.

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