ML20066H478

Amends 93 & 86 to Licenses DPR-42 & DPR-60,respectively, Revising Tech Specs by Adding Ref to Administrative Section

ML20066H478
Person / Time
Site:	Prairie Island
Issue date:	02/11/1991
From:	Marsh L Office of Nuclear Reactor Regulation
To:
Shared Package
ML20066H480	List: ML20066H478 ML20066H503
References
NUDOCS 9102210082
Download: ML20066H478 (16)

Text

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UNITED STATES l

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NUCLEAR REGULATORY COMMISSION j

e W ADHINGTON, D. C. 706M t

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NORTHERN STATES POWER COMPANY DOCKET NO. 50-282 PRAIRIE _ ISLAND NUCLEAR GENERATING PLANT,_ UNIT NO.1 AMENDMENT TO FACILITY OPERATING _ LICENSE t

Amendment No. 93 License No. DPR-42 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Northern States Power Comparty (the--licensee)datedSeptember 13, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regula-tions set forth in 10 CFR Chapter I; B.

The facility will o>erate in conformity with the application the provisions of tie Act, and the rules and regulations of Ihe Comission; C.

There is reasonable assurance (1) that the activities authorized by this anendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this awndment will not be inimical to the common defense and security or to the health and safety of the public; and

-E.

The issuance of this aniendnent is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license-is amended by changes to the Technical S)ecifica-tiens as indicated in the attachment to this license amendment, tie paragraph l

2.C.(2) of facility Operating License No. DPR-42 is hereby amended to read as follows:

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Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 93, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMNISSION b.k M&d5 he)

L. B. Marsh. Director Project Directorate 111-1 DivisionofReactorProjects111/IV/V Office of Nuclear Reactor Regulation Attachunt:-

Changes to the Technical Specifications Date of Issuance: February 11, 1991 l.

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ATTACHMENT TO LICENSE AMENDMENT NO. 93 g,g if FACILITY OPERATING LICENSE NO. DPR-42 1

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DOCKET NO. 50 282 i

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-Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT TS - ix TS - ix TS.6.7 - 4 TS.6.7 - 4 TS.6.7 - 5 TS.6.7 - 5 TS.6.7 --6 TS.6.7 - 6 TS.6.7 - 7 l

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TABl1 OF CONTENTS (Continued)

TS SECTION TITLI PACE i

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1 6.7 Reporting Requirements TS.6.7 1 A. Routine Reports TS 6.7 1 l

1. Annual Report TS.6.7 1

a. Occupational Exposure Report TS.6.7 1

b. Report of Safety and Relief Valve Tailures and Challenges TS.6.7 1

c. Primary Coolant Iodine Spike Report 75.6.7 1

2. Starcup Report TS.6.7 2

3. Monthly Operating Report TS.6.7 2

4. Semiannual Radioactive Effluent Release Report TS.6.7 3

5. Annual Summaries of Meteorological Data TS.6.7 4

6. Core Operating Limits Report TS.6.7 4 B. Reportable Events TS 6.7 5 C. Environmental Reports TS 6.7 6

1. Annual Radiation Environmental Monitoring Reports TS.6.7 6

2. Environmental Special Reports

-TS 6.7 6

3. Other Environmental Reports TS.6.7 7 (non radiological, non. aquatic)

D. Special Reports TS.6.7 7 Prairie Island Unit i Amendment No. E0, 59, 63. 73.

Ed. 91, 92, 93

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TS.6.7 4 6'.7.A.5. Annual Summaries of Meteoroforical Data An Annu*.'. summary of meteorological data shall be submitted for the previous calendar year in the form of joint frequency distributions of wind speed, vind direction, and atmospheric stability at the request of the Commission.

6.7,A.6. [g.g.e Doeratinz LimLts Recort

a. Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

1. Heat Flux Hot Channel Factor Limit (PRPT), Nuclear Enthalpy g

RiseHotChannelTactorLimit(rfH)PPDH,K(Z)andV(Z)

(Specifications 3.10.14.1, 3.10.8.2 and 3.10.B.3)

2. Axial flux Difference Limits and Target Band (Specifications 3.10.B.4 through 3.10.8.9)

3. Shutdown and Control Bank Insertion Limits (Specification 3.10.D)

4. Reactor Coolant System riov Limit (Specification 3.10.J)

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

NSPNAD 8101.A ' Qualification of Reactor Physics Methods for Application to PI Units' (latest approved version)

NSPNAD.8102.A. ' Prairie Irland Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units' (latest approved version)

WCAP.9272.P.A,

• Westinghouse Reload Safety Evaluation Methodology', July, 1985 WCAP-10054 P.A, ' Westinghouse Small Break ECCS Ev:.luation Model Using the NOTRUMP Code' August, 1985 WCAP.10924.P.A, ' Westinghouse Large. Break LOCA Best. Estimate Methodology *, December, 1988 WCAP.10924.P.A Volume 1. Addendum 4 ' Westinghouse Large Break thCA Best Estimate Methodology', August 1990 Prairie Island Unit 1 Amendment No. E#, 57, 73, 91, 72, 93

TS.6.7 5 9

XN.NF 77 57 (A), XN.NT.77 57, Supplement 1 (A), ' Exxon Nuclear Power Distribution Control for Pressurized Water Reactors Phase II*, May, 1981 i

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal sechanical limits, core thermal.h*'drau11e limits ECCS limits, nuclear limita such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

d. The CORE OPERATING LIMITS REPORT, including any mid. cycle revisions or supplements tFereto, shall be supplied upon issuance, for each reload cycis, to the NRC Document Control Desk with copies to the Regional Administrator aad Resident Inspector.

B. REPORTABLE INENTS The following actions shall be taken for REPORTABLE EVENTS:

The Commission shall be notified by a report submitted pursuant a.

to the requirements of Section 50.73 to 10 CTR Part 50, and b.

Each REPORTABLE EVENT shall be revieved by the Operationa Committee and the results of this review shall be submitted to the Safety Audit Committee and the Vice President Nuclear Generation.

Prairie Island Unit 1 Amendment No. 5#, 59, 73, 91, 92, 93

TS.6.7 6 C. Environnental Reports The reports listed below shall be submitted to the Administrator of the appropriate Regional NRC Office or his designate:

1.

Annual Radiation Environnental Monitorine. Report (a) Annual Radiation Environmental Monitoring Reports covering the operation of the program during the previous calendar year shall be submitted prior to May 1 of each year.

(b) The Annual Radiation Environmental Monitoring Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriato), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment.

The reports shall also include the results of land use censuses required by Specification 4.10.B.1.

If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

(c) The Annual Radiation Environmental Monitoring Reports shall inciv i summarized and tabulated results in the format of e

Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period.

In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.

The

.issing data shall be submitted as soon as possible in a supplementary report.

(d) The reports shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a tablo giving distances and directions from one reactor; and the results of licensees participation in the Interlaboratory Comparison Program, required by Specifiestion 4.10.C.1.

2.

Environmental Sneelal Recorts (a) When radioactivity levels in samples exceed limits specified in Table 4.10 3, an Environmental Special Report shall be submitted within 30 days from the end of the affected calendar quarter.

For certain cases involving long analysis time, determination of quarterly averages may extend beyond the 30 day period.

In these cases the potential for exceeding the quarterly limits will be reported within the 30 day period to be followed by the Environmental Special Report as soon as practicable.

Prairie Island Unit 1 Amendment No. 92, 93

TS.6 7 7 f

3.

Other Environmental Reoorts (non radiolorical. non acuacie)

Written reports for the following items shall be submitted to the appropriate NRC Regional Administrator:

a.

Environmental events that indicate or could result in a significant environmental impact casually related to plant operation. The following are examples:

excessive bird impaction; onsite plant or animal disease outbreaks; unusual mortality of any species protected by the Endangered Species Act of 1973; or increase in nuisance organisms or conditions. This report shall be submitted within 30 days of the event and shall (a) describe, analyze, and evaluate the event, including extent and magnitude of the impact and plant operating characteristics, (b) describe the probable cause of the event, (c) indicate the action taken to correct the reported event, (d) indicate the corrective action taken to preclude repetition of the event and to prevent similar occurrences involving similar components or systems, and (e) indicate the agencies notified and their preliminary responses.

b.

Proposed changes, test or experiments which may result in a significant increase in any adverse environmental impact which was not previously reviewed or evaluated in the Final Environmental Statement or supplements thereto.

This report shall include an evaluation of the environmental impact of the proposed activity and shall be submitted 30 days prior to implementing the proposed change, test or experiment.

D.

Snecial Reoorts Unless otherwise indicated, special reports required by the Technical Specifications shall be submitted to the appropriate NRC Regional Administrator within the time period specified for each report.

Prairie Island Unit 1 Amendment No. 93

e mob UNITED STATES I

NUCLEAR REGULATORY COMMISSION WASHl8WGTON, D. C. 20666 9

NORTHERN STATES POWER, COMPANY DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT._ UNIT NO. 2 AMENDMENT TO FACILITY OPERATING _ LICENSE Amendment No. 86 License No. DPR-60 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Northern S'.ates Power Company (thelicensee)datedSeptember 13, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's tvles and regulations set forth in 10 CFR Chapter It B.

The facility will o)erate in conformity with the application, the provisions of tie Act, and the rules and regulations of the Commission; C.

Thereisreasonableassurance(1)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and(ii)thatsuchactivitieswillbe and safety of the public,ith the Comission's regulations; conducted in compliance w o

D.

The issuance of this amendment will not be inimical to the common defense and security or tu the health and safety of the public; and E.

The issuance of this amendment-is in accordance with 10 CFR-Part 51 of the Comission's regulations and all applicable requirements have been satisifed.

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-60 is hereby amen,ded to read as follows:

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' Technical Specifications The Technical Specifications contained in Appendix A, as revised through Anwndment No. 86, f acility in accordance with the Technical Specifications.

are hereby incorporated in the license. The licensee shall operate the 3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY ComISSION g 2 5. W " (A.-)

L. B. Marsh, Director i

Project Directorate 111-1 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation Attachment thanges to.the Technical Specifications-Date of Issuance: February ii. 1991 i

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w ATTACHMENT TO LICENSE AMENDMENT NO. 86 FACILITY OPERATIWG LICENSE NO. DPR-60 DOCKET NO 50-306

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Revise Appendix A Technical Specifications by removing the pages identified below and inserting t M attached pages. The revised pages are identified by amendment number and contn marginal lines indicating the area of change.

REMOVE INSERT i

TS - ix TS - ix TS.6.7 - 4 TS.6.7 - 4 TS.6.7 - 5 TS.6.7 - 5 TS.6.7 - 6 TS.6.7 - 6 TS.6.7 - 7 k

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TS 1x TABLE OF CONTENTS (Continued)

Li,SECTION TITLE PACE 6.7 Reporting Requirements TS.6.7 1 A. Routine Reports TS.6.7 1

1. Annual Report TS.6.7 1

a. Occupational Exposure Report TS.6.7-1

b. Report of Safety and Relief Valve Failures and Challenges TS.6.7 1

c. Primary Coolant Iodine Spike Report TS.6.7 1

2. Startup Report TS.6.7 2

3. Monthly Operating Report TS.6.7 2

4. Semiannual Radioactive Effluent Release Report TS.6.7 3

5. Annual Sur.aaries of Meteorological Data TS.6.7 4

6. Core Operating Limits Report TS.6.7 4 B. Reportable Events TS.6.7 5 C, Environmental Reports TS.6.7 6

1. Annual Radiation Environmental Monitoring Reports TS.6.7 6

2. Environmental Special Reports TS.6.7 6

3. Other Environmental Reports TS.6.7 7 (non radiological, non aquatic)

D. Special Reports TS.6.7 7 Prairie Island Uqt Amendment No. 44, 54, zy,t &,6

,e 73, 84, 85, 86

TS.6.7 4 6.7.A.5, Annual Summaries of Meteorolonical Data An annual suausary of meteorological data shall be submitted for the previous calendar year in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability at the request of the Commission.

6.7.A.6. core Deeratine timits Renert

a. Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

1. Heat Flux Hot Channel Factor Limit (Fq

), Nuclear Enthalpy Rise Hot Channel Factor Limit (F

), PFDH, K(Z) and V(Z)

(Specifications 3.10.I.1, 3.10.8.2 and 3.10.8.3)

2. Axial Flux Difference Limits and Target Band (Specifications 3.10.8.4 through 3.10.B.9)

3. Shutdown and Control Bank Insertion Limits (Specification 3.10.D)

4. Reactor Coolant System Flow Limit (Specification 3.10.J)

b. The analytical-methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following docum6nts:

NSPNAD 8101.v., " Qualification of Reactor Physics Nethods for Application :.4 '!?%)nitc*.f, latest approved version)

NSPNAD 8102.A. ' Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units' (latest approved version)

WCAP 9272.P.A. " Westinghouse Reload Safety Evaluation Methodology', July,1985 WCAP.10054 P.A, ' Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code", August, 1985 l

WCAP 10924.P.A. ' Westinghouse Large. Break LOCA Best Estimate Methodology', December, 1988 l

WCAP 10924.P.A. Volume 1. Addendum 4, ' Westinghouse Large - Break LOCA Best Estimate Methodology', August 1990

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4 Prairie Island Unit 2 Amendment No. (8, 53, 66, 8#, 85, 86

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TS.6.7 5 XN.NF.77 57 (A), XN.NT.77 57, Supplement 1 (A), ' Exxon Nuclear Power Distribution Control for Pressurized Water Reactors Phase !!*, May, 1981

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal. mechanical limits, core thermal. hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

d. The CORE OPERATING LIMITS REPORT, including any mid. cycle revisions or supplements thereto, shall be supplied upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

S. R_EPORTABLE IT'ENTS The following actions shall be taken for REPORTABLE EVENTS:

The Commission shall be notified by a report submitted pursuant a.

to the requirements of Section 50.73 to 10 CFR Part 50, and b.

Each REPORTA$ll EVENT shall be reviewed by the Operations Committee and the results of this review shall be submitted to the Safety Audit Committee and the Vlee President Nuclear Ceneration.

Prairie Island Unit 2 Amendment No. 48, 53, 66, 84, E5, 86

TS.6 7 6 C. Environmental Recorts The reports listed below shall be submitted to the Administrator of the appropriate Regional NRC Office or his designate:

1.

Annual Radiation invironmental Monitorine Revert (a) Annual Radiation Environmental Monitoring Reports covering the operation of the program during the previous calendsr year shall be submitted prior to May 1 of each year.

(b) The Annual Radiation Environmental Monitoring Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report per*od, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment.

The reports shall also include the results of land use censuses required by Specification 4.10.B.1.

If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

(c) The Annual Radiation Environmental Monitoring Reporta shall include suemarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period.

In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

(d)

The reports shall also include the following: a summary description of the radiological environnental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensees participation in the Interlaboratory Comparison Program, required by Specification 4.10.C.1.

2.

Environmental Scecial Reoorta (a) When radioactivity levels in samples exceed limits specified in Table 4.10 3, an Environmental Special Report I

shall be submitted within 30 days from the end of the affected calendar quarter.

For certain cases involving long analysis time, determination of quarterly averages may extend beyond the 30 day period.

In these cases the potential for exceeding the quarterly limits will be reported within the 30 day period to be followed by the Environmental Special Report as soon as practicable.

Prairie Island Unit 2 Amendment No. 85, 86

=.

l TS.6 7 7 3.

Other Environmental Reports (non radiolorical. non.acuatie)

Written reports for the following items shall be submitted to the appropriate NRC Regional Administrator:

Environmental events that indicate or could result in a a.

significant environmental impact casually related to plant operation.

The following are examples:

excessive bird impaction; onsite plant or animal disease outbreaka; unusual mortality of any species protected by the Endangered Species Act of 1973; or increase in nuisance organisms or conditions. This report shall be submitted within 30 days of the event and shall (a) describe, analyse.

and evaluate the event, including extent and magnitude of the impact and plant operating characteristics, (b) describe the probable cause of the event, (c) indicate the action taken to correct the reported event, (d) indicate the corrective action taken to preclude repetition of the event and to prevent similar occurrences involving similar components or systems, and (e) indicate the agencies notified and their preliminary responses, b.

Proposed changes, test or experiments which may result in a sigtiificant increase in any adverse environmental impact which was not previously reviewed or evaluated in the Final Environmental Statement or supplements thereto.

This report shall include an evaluation of the environmental impact of the proposed activity and shall be submitted 30 days prior to implementing the proposed change, test or experiment.

D.

Soeelal Recorts Unless otherwise indicated, special reports required by the Technical Specifications shall be submitted to the appropriate NRC Regional Administrator within the time period specified for each report.

Prairie Island Unit 2 Amendment No. 86

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